WorldWideScience

Sample records for nuclear damage analisis

  1. Legal analysis at the Law for Civil liabilities by nuclear damage; Analisis juridico a la Ley de responsabilidad civil por danos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez G, A

    2000-07-01

    The present work has the objective to analyse in specific terms the legal regime of the Civil liability by nuclear damage. It has been the intention of that this compilation is the initiation of a large way which awake the interests of jurists and specialists dedicated to study the aspects as the liability by nuclear damage, compensation guarantee, risk and nuclear damage among others. The peaceful applications of the nuclear energy require the necessity of a legal ordinance that it is updated according to the nuclear technology development that the regulations of the common law do not cover. This work is initiated mentioning some antecedents of the nuclear energy law in Mexico. Also is realized the study of the elemental concepts and definitions about the subject as the evolution of the legal figure in the National law frame where the jurist must do an incursion in the nuclear field and make use of scientific and technical terminology. It was analysed and it was made the reflection of the legal figure of liability, its exoneration cases, about the concepts of risk and nuclear damage overcoming the conceptual error among them. It is talked about the study of nuclear damage and its repairing as financial guarantee to compensate to the people injured by a nuclear accident. Finally, it was treated about the legal analysis and proposals of additions and reforms for updating the Nuclear damage liability Law, concluding with general contributions to the Law resulting products of this work. (Author)

  2. Nuclear damage - civil liability

    International Nuclear Information System (INIS)

    Simoes, A.C.

    1980-01-01

    An analysis is made of the civil liability for nuclear damage since there is a need to adjust the existing rules to the new situations created. The conventions that set up the new disciplining rules not considered in the common law for the liability of nuclear damage are also mentioned. (A.L.) [pt

  3. Risk of nuclear damage

    International Nuclear Information System (INIS)

    Kienzl, K.

    1997-01-01

    Following the opening and words of welcome by Mr. Fritz Unterpertinger (unit director at the Austrian Federal Ministry for the Environment, Youth and Family; BMUJF) Mrs Helga Kromp-Kolb (professor at the Institute for Meteorology and Physics of the University of Natural Resources Science Vienna) illustrated the risks of nuclear damage in Europe by means of a nuclear risk map. She explained that even from a scientific or technical point of view the assessment of risks arising from nuclear power stations was fraught with great uncertainties. Estimates about in how far MCAs (maximum credible accident) could still be controlled by safety systems vary widely and so do assessments of the probability of a core melt. But there is wide agreement in all risk assessments conducted so far that MCAs might occur within a - from a human point of view - conceivable number of years. In this connection one has to bear in mind that the occurrence of such a major accident - whatever its probability may be - could entail immense damage and the question arises whether or not it is at all justifiable to expose the general public to such a risk. Klaus Rennings (Centre for European Economic Research, Mannheim, Germany) dealt with the economic aspects of nuclear risk assessment. He explained that there are already a number of studies available aiming to assess the risk of damage resulting from a core melt accident in economic terms. As to the probability of occurrence estimates vary widely between one incident in 3,333 and 250,000 year of reactor operation. It is assumed, however, that a nuclear accident involving a core melt in Germany would probably exceed the damage caused by the Chernobyl accident. The following speakers addressed the legal aspects of risks associated with nuclear installations. Mrs Monika Gimpel-Hinteregger (professor at the Institute for Civil Law in Graz) gave an overview on the applicable Austrian law concerning third party liability in the field of nuclear energy

  4. Fatigue damage of nuclear facilities

    International Nuclear Information System (INIS)

    2001-01-01

    The conference on the fatigue damage of nuclear facilities, organized by the SFEN (french society of nuclear energy), took place at Paris the 23. of november 2000. Eleven papers were presented, showing the state of the art and the research programs in the domain of the sizing rules, safety, installations damage, examination and maintenance. (A.L.B.)

  5. Terrorism and nuclear damage coverage

    International Nuclear Information System (INIS)

    Horbach, N. L. J. T.; Brown, O. F.; Vanden Borre, T.

    2004-01-01

    This paper deals with nuclear terrorism and the manner in which nuclear operators can insure themselves against it, based on the international nuclear liability conventions. It concludes that terrorism is currently not covered under the treaty exoneration provisions on 'war-like events' based on an analysis of the concept on 'terrorism' and travaux preparatoires. Consequently, operators remain liable for nuclear damage resulting from terrorist acts, for which mandatory insurance is applicable. Since nuclear insurance industry looks at excluding such insurance coverage from their policies in the near future, this article aims to suggest alternative means for insurance, in order to ensure adequate compensation for innocent victims. The September 11, 2001 attacks at the World Trade Center in New York City and the Pentagon in Washington, DC resulted in the largest loss in the history of insurance, inevitably leading to concerns about nuclear damage coverage, should future such assaults target a nuclear power plant or other nuclear installation. Since the attacks, some insurers have signalled their intentions to exclude coverage for terrorism from their nuclear liability and property insurance policies. Other insurers are maintaining coverage for terrorism, but are establishing aggregate limits or sublimits and are increasing premiums. Additional changes by insurers are likely to occur. Highlighted by the September 11th events, and most recently by those in Madrid on 11 March 2004, are questions about how to define acts of terrorism and the extent to which such are covered under the international nuclear liability conventions and various domestic nuclear liability laws. Of particular concern to insurers is the possibility of coordinated simultaneous attacks on multiple nuclear facilities. This paper provides a survey of the issues, and recommendations for future clarifications and coverage options.(author)

  6. Civil liability for nuclear damage

    International Nuclear Information System (INIS)

    1963-01-01

    An international Convention on Civil Liability for Nuclear Damage was adopted in Vienna on 19 May 1963 by a sixty-nation conference convened by the International Atomic Energy Agency. The Convention, which is subject to ratification by the States signing it, will come into force three months after the deposit of the fifth instrument of ratification. The Convention is designee only to establish minimum rules regarding civil liability for nuclear damage; it may thus well be described as a framework convention, the main provisions of which represent the essential common denomination acceptable to as many States as possible. It leaves wide scope for national legislation and regional arrangements with a view to implementing these provisions The Convention does not purport to create a uniform civil law in this field, but it contains the minimal essential for protection of the public and forms the legal basis for uniform world-wide liability rules

  7. Nuclear damage compensation and energy reform

    International Nuclear Information System (INIS)

    Yokemoto, Masafumi

    2013-01-01

    Nuclear damage compensation and energy reform were closely related. Nuclear damage compensation cost should be part of generation cost of nuclear power. Extend of nuclear damage compensation was limited by compensation standard of Tokyo Electric Power Co. (TEPCO) following guidelines of Dispute Reconciliation Committee for Nuclear Damage Compensation. TEPCO had already paid compensation of about two trillion yen until now, which was only a part of total damage compensation cost. TEPCO had been provided more than 3.4 trillion yen by Nuclear Damage Liability Facilitation Cooperation, which would be put back by nuclear operators including TEPCO. TEPCO could obtain present raising funds and try to reconstruct business with restart of nuclear power, which might disturb energy reform. Present nuclear damage compensation scheme had better be reformed with learning more from Minamata disease case in Japan. (T. Tanaka)

  8. Legal protection against nuclear damage

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-04-15

    The IAEA Director General appointed an international Panel of Experts to go into the question of Civil Liability and State Responsibility for Nuclear Hazards. The Panel had before it certain basic postulates formulated after a preliminary and tentative consideration of the subject. From the viewpoint of the public, the first postulate is, of course, that the use of nuclear energy be regulated by adequate licensing and control mechanisms so as to prevent any accidents. To the extent, however, that nuclear damage cannot be prevented, there must be liability on the part of the enterprise which caused the damage and, where damage exceeds its liability or its financial resources there should be some assurance of compensation by the State. This should be so not only within the borders of one State, but especially also on an international basis. Security should be required for the possible liability of the enterprises connected with a nuclear incident. Litigation with respect to liability should be concentrated in the most convenient tribunal and be governed by a single clearly defined law. The methods of distribution should meet general standards of equity and be as expeditious as possible. Emergency measures, especially evacuation, first aid and decontamination, should be organized and financed without delay. At the same time, the liability of an enterprise should not exceed its reasonable financial capabilities. This means that a ceiling should be imposed upon the amount of third party liability to which an enterprise could be held. And the liability should generally be such as can be covered by adequate financial security. Uniformity in the treatment of victims of nuclear incidents in all these fields is a desirable goal. Yet, if a rule adopted on an international level or suggested by uniform legislation were to be viable, it should adapt itself to the social, economic and legal order already existing in individual States. This may mean that in certain fields it

  9. Legal protection against nuclear damage

    International Nuclear Information System (INIS)

    1959-01-01

    The IAEA Director General appointed an international Panel of Experts to go into the question of Civil Liability and State Responsibility for Nuclear Hazards. The Panel had before it certain basic postulates formulated after a preliminary and tentative consideration of the subject. From the viewpoint of the public, the first postulate is, of course, that the use of nuclear energy be regulated by adequate licensing and control mechanisms so as to prevent any accidents. To the extent, however, that nuclear damage cannot be prevented, there must be liability on the part of the enterprise which caused the damage and, where damage exceeds its liability or its financial resources there should be some assurance of compensation by the State. This should be so not only within the borders of one State, but especially also on an international basis. Security should be required for the possible liability of the enterprises connected with a nuclear incident. Litigation with respect to liability should be concentrated in the most convenient tribunal and be governed by a single clearly defined law. The methods of distribution should meet general standards of equity and be as expeditious as possible. Emergency measures, especially evacuation, first aid and decontamination, should be organized and financed without delay. At the same time, the liability of an enterprise should not exceed its reasonable financial capabilities. This means that a ceiling should be imposed upon the amount of third party liability to which an enterprise could be held. And the liability should generally be such as can be covered by adequate financial security. Uniformity in the treatment of victims of nuclear incidents in all these fields is a desirable goal. Yet, if a rule adopted on an international level or suggested by uniform legislation were to be viable, it should adapt itself to the social, economic and legal order already existing in individual States. This may mean that in certain fields it

  10. The law concerning liability for nuclear damage

    International Nuclear Information System (INIS)

    Kinouchi, Kazuo

    1978-01-01

    This treatise outlines the Law on Compensation for Nuclear Damage (Law No. 147, June 17, 1961) and the Law on Indemnity Agreement for Compensation of Nuclear Damage (Law, No. 148, June 17, 1961) which are both came into effect in March, 1962, and describes how these laws will be executed if an accident occurs actually in nuclear facilities. The first law which prescribes various provisions for compensation of nuclear damage is characterised as having the principle of no-fault liability and hence making a nuclear enterpriser responsible for securing adequate financial resources to indemnify general public for their damages from nuclear accidents. Thus, in compliance with the law a nuclear enterpriser should effect both the contract of the indemnity responsible insurance and the indemnity agreement for compensation of nuclear damage. The second law deals with the indemnity agreement which is concluded by a nuclear enterpriser with the government and constitutes a full measure for compensation of nuclear damage supplementing the indemnity responsible insurance. The indemnity agreement is to insure compensation liabilities for nuclear damages which the indemnity responsible insurance can not cover-that is, damages caused by earthquakes and volcanic eruptions, and also damages from normal operations of nuclear facilities and those occurs after 10 years of an accident. Then, the author describes in detail how these laws apply in a nuclear accident to damages to third parties and those to facilities of related nuclear enterpriser himself and to his employees. Finally, the author refers to the legal systems for compensation of nuclear damage in the United States, Britain, France and West Germany. (Matsushima, A.)

  11. Civil liability for nuclear and radiological damage

    International Nuclear Information System (INIS)

    Puig, D.

    2001-10-01

    The present work gives details of the nuclear damage, the accidents of Chernobil, three Mile Inland and Tokaimura with their respective legal consequences, the nature of the responsibility and bases for their establishment, conventions about civil responsibility for nuclear damages to regional and world level as well as other condition of conventions of the Ibero-American countries with regard to the approval of the conventions it has more than enough civil responsibility for nuclear and radiological accident damages

  12. Civil liability for nuclear damage law

    International Nuclear Information System (INIS)

    1974-01-01

    This Law has as its main objective to regulate civic responsability on damages or injuries that may be brought about by the usage of nuclear reactors and the use of nuclear substances or fuels and their consecuent wastes. The text of this law is consituted by 5 chapters that deal with the following subjects: CHAPTER ONE.- Objective and Definitions. CHAPTER TWO.-On Civic Responsability on Nuclear Damages or Injuries. CHAPTER THREE.- On the Limits of Responsability. CHAPTER FOUR.- On Prescription. CHAPTER FIVE.- General Regulations Concepts such as the following are defined concretely and precisely: Nuclear Accident, Nuclear Damage or Injury, Atomic Energy, Operator of a Nuclear Facility, Nuclear Facility, Radioactive Product or Waste Material, Nuclear Reactor, Nuclear Substances Remittance and Hazardous Nuclear Substance

  13. The law concerning indemnification of nuclear damage

    International Nuclear Information System (INIS)

    1977-01-01

    This Law aims at determining the basic system concerning indemnification for nuclear damage caused by the operation of reactors, fabrication, reprocessing and use of nuclear fuel materials as well as the transportation, storing or disposal of such materials or those contaminated by such materials (including fission products) accompanying these operations in view of protecting the sufferers and contributing to the wholesome development of atomic energy enterprises. The ''nuclear damage'' referred to in this Law is the damages caused by the action during the process of fission of nuclear fuel materials or the action of radiation or the poisonous action of said nuclear fuel materials or matters contaminated by said materials (those causing poisoning or deuteropathy in human bodies by taking in or inhaling such materials). Upon giving nuclear damage by the operation of reactors and others, the atomic energy entrepreneurs concerned are responsible for indemnifying the damage. Atomic energy entrepreneurs should not operate reactors without first taking the measures for indemnifying nuclear damages. Said measures are conclusion of nuclear damage indemnification responsibility insurance contract and nuclear damage indemnification contract or deposit, by which 6,000 million yen may be earmarked for such indemnification per factory, place of business or nuclear ship

  14. Convention on supplementary compensation for nuclear damage

    International Nuclear Information System (INIS)

    Chinese Nuclear Society, Beijing; U.S. Nuclear Energy Institute

    2000-01-01

    The Contracting parties recognize the importance of the measures provided in the Vienna Convention on Civil Liability for Nuclear Damage and the Paris Convention on Third party liability in the Field of Nuclear Energy as well as in national legislation on compensation for nuclear damage consistent with the principles of these conventions. The Contracting parties desire to establish a worldwide liability regime to supplement and enhance these measures with a view to increasing the amount of compensation for nuclear damage and encourage regional and global co-operation to promote a higher level of nuclear safety in accordance with the principle of international partnership and solidarity

  15. Analysis of the microstructural evolution of the damage by neutron irradiation in the pressure vessel of a nuclear power reactor BWR; Analisis de la evolucion microestructural del dano por irradiacion neutronica en la vasija de presion de un reactor nuclear de potencia BWR

    Energy Technology Data Exchange (ETDEWEB)

    Moranchel y R, M.

    2012-07-01

    Nuclear reactor pressure vessel type BWR, installed in Mexico and in many other countries, are made of an alloy of low carbon steel. The American Society for Testing and Materials (Astm) classifies this alloy as A533-B, class 1. Both the vessel and other internal structures are continuously exposed to the neutron flux from the reactions of fission in nuclear fuel. A large number of neutrons reach the vessel and penetrate certain depth depending on their energy. Its penetration in the neutron collides with the nuclei of the atoms out of their positions in the crystal lattice of steel, producing vacancies, interstitial, segregations, among other defects, capable of affecting its mechanical properties. Analyze the micro-structural damage to the vessel due to neutron irradiation, is essential for reasons of integrity of this enclosure and safety of any nuclear power plant. The objective of this thesis work is theoretical and experimentally determine the microstructural damage of a type nuclear reactor vessel steel BWR, due to neutron radiation from the reactor core, using microscopic and spectroscopic techniques as well as Monte Carlo simulation. Microscopy Optical, Scanning Electron Microscopy, Transmission Electron Microscopy, Energy Dispersion of X-rays Spectrometry and X-rays Diffractometry were the techniques used in this research. These techniques helped in the characterization of both the basis of design of pressure vessel steel and steel irradiated, after eight years of neutron irradiation on the vessel, allowing know the surface morphology and crystal structures of the previous steel and post-irradiation, analyze the change in the microstructure of the steel vessel, morphological damage to surface level in an irradiated sample, among which are cavities in the order of microns produced by Atomic displacements due to the impact of neutronic, above all in the first layers of thickness of the vessel, the effect of swelling, regions of greater damage and Atomic

  16. The law concerning indemnification of nuclear damage

    International Nuclear Information System (INIS)

    1979-01-01

    The law defines the basic system of indemnification of nuclear damage by the operation of reactors to protect sufferers and help the sound development of atomic energy business. The operation of reactors means hereunder the operation of reactors, processing, reprocessing and the uses of nuclear fuel materials as well as transport, storage and disposal of nuclear fuel materials or things contaminated by them, which accompany with those procedures. The nuclear damage signifies injuries due to functions of fission of nuclear fuel materials or radiation or poisonous functions of things contaminated by them. When nuclear damage happens by the operation of reactors, the atomic energy enterpriser concerned shall indemnify the damage. Atomic energy undertakers shall not operate reactors without taking measures for compensation. The measures shall be the conclusion of nuclear damage compensation insurance contracts and indemnification contracts or the deposit. The amount of less than yen 10 milliards specified by the order and acknowledged by the Director General of Science and Technology Agency shall be allotted to the compensation by these measures for each works, enterprise or nuclear ship. The government shall assist atomic energy enterprisers to indemnify, when such compensation surpasses the amount assigned and the support is considered necessary. (Okada, K.)

  17. Convention on supplementary compensation for nuclear damage

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-22

    The document reproduces the text of the Convention on Supplementary Compensation for Nuclear Damage which was adopted on 12 September 1997 by a Diplomatic Conference held between 8-12 September 1997 in Vienna

  18. Convention on supplementary compensation for nuclear damage

    International Nuclear Information System (INIS)

    1998-01-01

    The document reproduces the text of the Convention on Supplementary Compensation for Nuclear Damage which was adopted on 12 September 1997 by a Diplomatic Conference held between 8-12 September 1997 in Vienna

  19. Analysis of the micro-structural damages by neutronic irradiation of the steel of reactor vessels of the nuclear power plant of Laguna Verde. Characterization of the design steel; Analisis de los danos micro-estructurales por irradiacion neutronica del acero de la vasija de los reactores de la Central Nuclear de Laguna Verde. Caracterizacion del acero de diseno

    Energy Technology Data Exchange (ETDEWEB)

    Moranchel y Rodriguez, M.; Garcia B, A. [IPN, Escuela Superior de Fisica y Matematicas, Departamento de Fisica, Av. Luis Enrique Erro s/n, Unidad Profesional Adolfo Lopez Mateos, Col. Lindavista, 07738 Mexico D. F. (Mexico); Longoria G, L. C., E-mail: mmoranchel@ipn.m [ININ, Direccion de Investigacion Cientifica, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2010-09-15

    The vessel of a nuclear reactor is one of the safety barriers more important in the design, construction and operation of the reactor. If the vessel results affected to the grade of to have fracture and/or cracks it is very probable the conclusion of their useful life in order to guarantee the nuclear safety and the radiological protection of the exposure occupational personnel, of the public and the environment avoiding the exposition to radioactive sources. The materials of the vessel of a nuclear reactor are exposed continually to the neutronic irradiation that generates the same nuclear reactor. The neutrons that impact to the vessel have the sufficient energy to penetrate certain depth in function of the energy of the incident neutron until reaching the repose or to be absorbed by some nucleus. In the course of their penetration, the neutrons interact with the nuclei, atoms, molecules and with the same crystalline nets of the vessel material producing vacuums, interstitial, precipitate and segregations among other defects that can modify the mechanical properties of the steel. The steel A533-B is the material with which is manufactured the vessel of the nuclear reactors of nuclear power plant of Laguna Verde, is an alloy that, among other components, it contains atoms of Ni that if they are segregated by the neutrons impact this would favor to the cracking of the same vessel. This work is part of an investigation to analyze the micro-structural damages of the reactor vessels of the nuclear power plant of Laguna Verde due to the neutronic irradiation which is exposed in a continuous way. We will show the characterization of the design steel of the vessel, what offers a comprehension about their chemical composition, the superficial topography and the crystalline nets of the steel A533-B. It will also allow analyze the existence of precipitates, segregates, the type of crystalline net and the distances inter-plains of the design steel of the vessel. (Author)

  20. Liability for nuclear damage and compensation therefor

    International Nuclear Information System (INIS)

    Prochazkova, D.

    1996-01-01

    The basic principles are outlined of the Paris Convention on Third Party Liability in the Field of Nuclear Energy, the Brussels Convention Supplementary to the Paris Convention, the Vienna Convention on Civil Liability for Nuclear Damage, and the Joint Protocol Relating to the Application of the Paris Convention and the Vienna Convention. (P.A.)

  1. Third party liability for nuclear damage

    International Nuclear Information System (INIS)

    Crancher, D.W.

    1976-12-01

    Basic principles of nuclear liability legislation are discussed including absolute and limited liability and the role of the Sovereign State in idemnifying the operator for damage in excess of limited liability. European counrties realised the need for unifying the law of nuclear instability and efforts were made accordingly towards producing workable international conventions. The world's first legislation on nuclear liability - the USA Price-Anderson Act - is described in detail and a digest of nuclear liability claims experience is given. Observations of the present status of nuclear third party liability are outlined. (Author)

  2. Genetic damage following nuclear war

    International Nuclear Information System (INIS)

    Oftedal, P.

    1984-01-01

    Genetic damage may be caused by ionizing radiation from the exploding bomb itself, or from radioactive nuclides released or formed in the explosion. Long-wave radiation in the heat flash and physical force do not contribute. Thus only a small fraction of the energy of the explosion - fission or fusion- can cause genetic damage. Neutron irradiation is generally found to be 5-20 times more efficient than gamma irradiation for the same absorbed dose. Fetuses and children are generally more radiosensitive than adults. Exposure of gonads during the proliferative stage of gonad growth may conceivably lead to a ''fluctuation test'' effect, so that a gonad may contain a sector of cells carrying identical mutations. A corresponding development may take place if the gonad stem cell population has been severely depleted by an acute exposure and recovers

  3. Radiation damage studies of nuclear structural materials

    International Nuclear Information System (INIS)

    Barat, P.

    2012-01-01

    Maximum utilization of fuel in nuclear reactors is one of the important aspects for operating them economically. The main hindrance to achieve this higher burnups of nuclear fuel for the nuclear reactors is the possibility of the failure of the metallic core components during their operation. Thus, the study of the cause of the possibility of failure of these metallic structural materials of nuclear reactors during full power operation due to radiation damage, suffered inside the reactor core, is an important field of studies bearing the basic to industrial scientific views.The variation of the microstructure of the metallic core components of the nuclear reactors due to radiation damage causes enormous variation in the structure and mechanical properties. A firm understanding of this variation of the mechanical properties with the variation of microstructure will serve as a guide for creating new, more radiation-tolerant materials. In our centre we have irradiated structural materials of Indian nuclear reactors by charged particles from accelerator to generate radiation damage and studied the some aspects of the variation of microstructure by X-ray diffraction studies. Results achieved in this regards, will be presented. (author)

  4. Liability for nuclear damage. An international perspective

    International Nuclear Information System (INIS)

    Lopuski, J.

    1993-01-01

    The book deals with some of the complex issues of liability and compensation for nuclear damage which have been considered in the course of the work of the IAEA concerning the revision of the Vienna Convention on nuclear liability. It presents, in an orderly way, personal reflections of its author based on this experience gathered in years 1989-1992 when participating in this work. Necessarily it contains in some of its parts references to documents of the IAEA Standing Committee on Nuclear Liability; these documents because of their length could not be reproduced. Consequently these parts may be fully intelligible for those who have not participated in or closely followed in Committee's work. The IAEA work on liability for nuclear damage was initiated in the wake of the impact made on the world's public opinion by the Chernobyl incident and its transboundary effects; issues of international state liability and full compensation have been raised. But humanitarian ideas have quickly been confronted with cold calculations of the cost of financial protection for victims and an open unwillingness of some nuclear states the engage their liability; conflict of interests between nuclear and non-nuclear states has been manifested. After three years of discussion no wide consensus could be reached on some basic issues, such as: relationship between international state and civil liability regimes, structures of international legislation, concept of nuclear damage, limits of compensation, role of public funds or jurisdiction. The author presents his approach to these controversial issues, trying to provide at the same time a theoretical outline for the future international legislation on nuclear liability. (author)

  5. Liability and damages in Japanese nuclear law

    International Nuclear Information System (INIS)

    Hoshino, E.

    1981-01-01

    The Japanese legislation relating to nuclear liability is based on two laws which date back to 1961, i.e. the law concerning compensation for nuclear damage and the law concerning financial damage compensation indemnification. In Japan, the legal channelling of liability is in force, a contractual recourse is not possible unless there is intent. The financial security act in Japan consists of a (third-party) liability insurance contract concluded with a private insurer and the cover contract concluded with the state. According to the agreement on financial security concluded between government and operator, the operator has to pay the state a certain sum per year. Basically, the amount covered is DM 50 million per site. This sum will be increased to DM 90 million. The operator is fully liable. The state is not bound by law to fully cover damages but will be - de facto - prepared to do so anyway. For potential damage to personnel, the social insurance law is applicable as it is in the Federal Republic of Germany. However, this damage is intended to be subject to nuclear liability, to be effected by an amendmend. (orig./HP) [de

  6. Liability for on-site nuclear property damage

    International Nuclear Information System (INIS)

    Neems, H.J.

    2000-01-01

    Typically, liability for on-site property addressed in contracts between operator and its suppliers. Nuclear power plant operators ordinarily protect themselves against risk of nuclear damage to on-site property by insurance. Nuclear liability laws do not specifically address liability for nuclear damage to on-site property. Nuclear plant owners should address risk of damage to on-site property when developing risk management program

  7. Radiation damage in nuclear waste materials

    International Nuclear Information System (INIS)

    Jencic, I.

    2000-01-01

    Final disposal of high-level radioactive nuclear waste is usually envisioned in some sort of ceramic material. The physical and chemical properties of host materials for nuclear waste can be altered by internal radiation and consequently their structural integrity can be jeopardized. Assessment of long-term performance of these ceramic materials is therefore vital for a safe and successful disposal. This paper presents an overview of studies on several possible candidate materials for immobilization of fission products and actinides, such as spinel (MgAl 2 O 4 ), perovskite (CaTiO 3 ), zircon (ZrSiO 4 ), and pyrochlore (Gd 2 Ti 2 O 7 and Gd 2 Zr 2 O 7 ). The basic microscopic picture of radiation damage in ceramics consists of atomic displacements and ionization. In many cases these processes result in amorphization (metaminctization) of irradiated material. The evolution of microscopic structure during irradiation leads to various macroscopic radiation effects. The connection between microscopic and macroscopic picture is in most cases at least qualitatively known and studies of radiation induced microscopic changes are therefore an essential step in the design of a reliable nuclear waste host material. The relevance of these technologically important results on our general understanding of radiation damage processes and on current research efforts in Slovenia is also addressed. (author)

  8. International Co-operation in providing insurance cover for nuclear damage to third parties and for damage to nuclear installations

    International Nuclear Information System (INIS)

    Deprimoz, Jacques

    1983-01-01

    This article in three parts analyses cover for damage to third parties by fixed nuclear installations, cover for damage to third parties during transport of nuclear substances and finally, cover for damage to nuclear installations. Part I reviews the principles of nuclear third party liability and describes nuclear insurance pools, the coverage and contracts provided. Part II describes inter alia the role of pools in transport operations as well as the type of contracts available, while Part III discusses material damage, the pools' capacities and the vast sums involved in indemnifying such damage. (NEA) [fr

  9. Compensation for damages in case of a nuclear accident

    International Nuclear Information System (INIS)

    Leger, M.

    2011-01-01

    This article presents the system of compensation for damages in case of a nuclear accident. This system of civil liability for nuclear damage, as a specific regime, departs on several points from the common rules of civil liability, in order to provide an adequate and equitable compensation for the damages suffered by the victims of nuclear accidents. The French system of civil liability for nuclear damage results from two International Conventions integrated in French law (Paris convention 1960 and Brussels convention 1963) and the French law of 1968, October 30 on civil liability in the area of nuclear energy. These texts define the conditions under which a nuclear operator could be held liable in case of a nuclear accident. The protocols to amend the Paris and Brussels Conventions of 2004, not yet come into force, are also presented. They ensure that increased resources are available to compensate a greater number of victims of a nuclear accident. (author)

  10. Report of the working group for nuclear damage compensation system

    International Nuclear Information System (INIS)

    1989-01-01

    The Working Group for Nuclear Damage Compensation System was established within the Atomic Energy Commision of Japan on August 2, 1988. The Group has held five meetings to make a study on the revision of the reserve for nuclear damage compensation. The nuclear damage compensation system in Japan has been established under the Law Concerning Compensation for Nuclear Damages and the Law Concerning Contract for Compensation for Nuclear Damages. The former law requires the nuclear power plant operators to set up a reserve for damage compensation to ensure positive and quick payment of compensation in the event of an accident. The reserve is currently rely on liability insurance and a government compensation contract. The Working Group has concluded that the total reserve should be increased from the current yen10 bill. to yen30 bill. The amount of the reserve specified in the enforcement law for the Law Concerning Compensation for Nuclear Damages should also be increased accordingly. The Law Concerning compensation for Nuclear damage will also be applied to damage which occurs overseas as a result of an accident in Japan. (N.K.)

  11. SOVT analysis of the nuclear industry in Mexico; Analisis FODA de la industria nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez R, E.; Hernandez B, M. C., E-mail: edelmiraf@yahoo.com [Instituto Tecnologico de Toluca, Division de Estudios de Posgrado, Av. Instituto Tecnologico s/n, Ex-rancho La Virgen, 52140 Metepec, Estado de Mexico (Mexico)

    2011-11-15

    In this work the analysis of strengths, opportunities, vulnerabilities and threats (SOVT) of the nuclear industry in Mexico is presented. This industry presents among its strengths that Mexico is a highly electrified country and has a good established normative mark of nuclear security. Although the Secretaria de Energia in Mexico, with base to the exposed in the Programa Sectorial de Energia 2007-2012, is analyzing the convenience of the generation starting from this source, considering the strong technological dependence of the exterior and the limited federal budget dedicated to this field. As a result of the analysis of the SOVT matrix, were found a great number of strengths that threats, although the vulnerabilities list is major to the strengths, the opportunities list is the bigger. Therefore, the nuclear industry can be a sustainable industry, taking the necessary decisions and taking advantage of the detected opportunities. (Author)

  12. Analysis of archaeological pieces with nuclear techniques; Analisis de piezas arqueologicas con tecnicas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Tenorio, D [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2002-07-01

    In this work nuclear techniques such as Neutron Activation Analysis, PIXE, X-ray fluorescence analysis, Metallography, Uranium series, Rutherford Backscattering for using in analysis of archaeological specimens and materials are described. Also some published works and thesis about analysis of different Mexican and Meso american archaeological sites are referred. (Author)

  13. The 1968 Brussels convention and liability for nuclear damage

    International Nuclear Information System (INIS)

    Sands, Ph.; Galizzi, P.

    2000-01-01

    The legal regime governing civil liability for transboundary nuclear damage is expressly addressed by two instruments adopted in the 1960's: the 1960 Paris Convention on Third Party Liability in the Field of Nuclear Energy and the 1963 Vienna Convention on Civil Liability for Nuclear Damage These establish particular rules governing the jurisdiction of national courts and other matters, including channelling of liability to nuclear operators, definitions of nuclear damage, the applicable standard of care, and limitations on liability. Another instrument - the 1968 Brussels Convention on Jurisdiction and the Enforcement of Judgements in Civil and Commercial Matters (hereinafter referred to as 'the Brussels Convention') - which is not often mentioned in the nuclear context will nevertheless also be applicable in certain cases. It is premised upon different rules as to forum and applicable law, and presents an alternate vision of the appropriate arrangements governing civil liability for nuclear damage. In this paper we consider the relative merits and demerits of the Brussels Convention from the perspective of non-nuclear states which might suffer damage as a result of a nuclear accident in another state. We conclude that in the context of the applicability of the Brussels Convention the dedicated nuclear liability conventions present few attractions to non-nuclear states in Europe. We focus in particular on issues relating to jurisdiction and applicable law, and do so by reference to a hypothetical accident in the United Kingdom which has transboundary effects in Ireland. (author)

  14. Statistical analysis of the wind around a nuclear power plant; Analisis estadistico del viento alrededor de una central nucleoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Tejeda, A; Alvarez, Oscar; Contreras, A. D.; Jauregui, E. [Universidad Veracruzana, (Mexico)

    1996-12-31

    In order to show an appropriate methodology for the climatic analysis of the wind, some of the recent results in the investigation of the field flow around the Laguna Verde Nuclear Power Station, at Veracruz State (Mexico,) through the angular correlation coefficients and contingency tables among the registered wind directions by a meteorological tower at the levels of 10 and 60 meters high are presented. Finally, by applying an objective analysis of the data some conclusions are obtained in connection with the local winds with the mesoscale systems. [Espanol] Con el objeto de mostrar una metodologia apropiada en el analisis climatico del viento, se presentan algunos resultados recientes en la investigacion del campo de flujo en los alrededores de la central nucleoelectrica de Laguna Verde, Veracruz (Mexico), a traves de los coeficientes de correlacion angulares y de tablas de contingencia entre las direcciones del viento registradas por una torre meteorologica en los niveles de 10 y 60 metros de altura. Finalmente, aplicando analisis objetivo de los datos, se obtienen algunas conclusiones sobre la conexion de los vientos locales con los sistemas de mesoescala.

  15. Statistical analysis of the wind around a nuclear power plant; Analisis estadistico del viento alrededor de una central nucleoelectrica

    Energy Technology Data Exchange (ETDEWEB)

    Tejeda, A; Alvarez, Oscar; Contreras, A D; Jauregui, E [Universidad Veracruzana, (Mexico)

    1997-12-31

    In order to show an appropriate methodology for the climatic analysis of the wind, some of the recent results in the investigation of the field flow around the Laguna Verde Nuclear Power Station, at Veracruz State (Mexico,) through the angular correlation coefficients and contingency tables among the registered wind directions by a meteorological tower at the levels of 10 and 60 meters high are presented. Finally, by applying an objective analysis of the data some conclusions are obtained in connection with the local winds with the mesoscale systems. [Espanol] Con el objeto de mostrar una metodologia apropiada en el analisis climatico del viento, se presentan algunos resultados recientes en la investigacion del campo de flujo en los alrededores de la central nucleoelectrica de Laguna Verde, Veracruz (Mexico), a traves de los coeficientes de correlacion angulares y de tablas de contingencia entre las direcciones del viento registradas por una torre meteorologica en los niveles de 10 y 60 metros de altura. Finalmente, aplicando analisis objetivo de los datos, se obtienen algunas conclusiones sobre la conexion de los vientos locales con los sistemas de mesoescala.

  16. Direct reading spectrochemical analysis of nuclear graphite; Analisis espectroquimico de lectura directa de grafito nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Roca Adell, M; Becerro Ruiz, E; Alvarez Gonzalez, F

    1964-07-01

    A description is given about the application of a direct-reading spectrometer the Quantometer, to the determination of boron. calcium, iron, titanium and vanadium in nuclear grade graphite. for boron the powdered sample is mixed with 1% cupric fluoride and excited in a 10-amperes direct current arc and graphite electrodes with a crater 7 mm wide and 10 mm deep. For the other elements a smaller crater has been used and dilution with a number of matrices has been investigated; the best results are achieved by employing 25% cupric fluoride. The sensitivity limit for boron is 0,15 ppm. (Author) 21 refs.

  17. DNA damage-induced inflammation and nuclear architecture.

    Science.gov (United States)

    Stratigi, Kalliopi; Chatzidoukaki, Ourania; Garinis, George A

    2017-07-01

    Nuclear architecture and the chromatin state affect most-if not all- DNA-dependent transactions, including the ability of cells to sense DNA lesions and restore damaged DNA back to its native form. Recent evidence points to functional links between DNA damage sensors, DNA repair mechanisms and the innate immune responses. The latter raises the question of how such seemingly disparate processes operate within the intrinsically complex nuclear landscape and the chromatin environment. Here, we discuss how DNA damage-induced immune responses operate within chromatin and the distinct sub-nuclear compartments highlighting their relevance to chronic inflammation. Copyright © 2016 Elsevier Ireland Ltd. All rights reserved.

  18. Compensation for nuclear damage in the OECD member countries

    International Nuclear Information System (INIS)

    1977-01-01

    The study aims to describe briefly the main features of the system for compensation of nuclear damage in OECD Member Countries, emphasising the practical arrangements for compensating such damage, with illustrations drawn from various national legal provisions applicable to such cases. The study indicates and compares legislative provisions which are specifically nuclear, without going into the substantive and procedural rules of the general law, reference to which frequently occurs in enactments relating to nuclear third party liability. The references to national nuclear legislation illustrate the manner in which effect has been given to international Conventions. (Auth.) [fr

  19. Nuclear Liability and Insurance for Nuclear Damage in Sweden

    International Nuclear Information System (INIS)

    Thofelt, H.

    1998-01-01

    This paper contains some facts about the Swedish nuclear energy production system and about the nuclear operators liability with the important issues. The nuclear insurance of Sweden is also explained in short terms. (author)

  20. Nuclear Liability and Insurance for nuclear Damage in Switzerland

    International Nuclear Information System (INIS)

    Reitsma, S. M. S.

    1998-01-01

    With nuclear power generating 43% of its total electricity production, Switzerland is amongst the states, employing the highest percentage of nuclear electricity. Although, the country has not ratified any of the international Nuclear Liability Conventions, its Nuclear Third Party Liability Act reflects all the principles, underlying those Conventions. The statutory liability of the operator of a Swiss nuclear installation itself being unlimited, the total insurance limit of CHF 770 m. provides the highest private insurance protection worldwide. With the support of its foreign Reinsurance Pools, the capacity for this insurance guarantee has, over more than 40 years, been built up by the Swiss Nuclear Insurance Pool. Apart from Third Party Liability cover, the Pool also provides Property insurance to Swiss nuclear installation operators and reinsurance cover to other nuclear insurers worldwide. (author)

  1. The law on indemnity agreement for compensation of nuclear damage

    International Nuclear Information System (INIS)

    1979-01-01

    Basic terms are defined, such as: operation of reactors; nuclear damage; nuclear enterpriser; nuclear ship; measure for compensation; amount of compensation and liability insurance contract. The government may conclude with nuclear enterprisers indemnity agreements, in which in the case of reparation responsibilities of the enterprisers coming into being, the government agrees to make for losses of the enterprisers not possible to be compensated by liability insurance contracts, etc., and the enterprisers comply to pay indemnity charges. Losses indemnified by the government with the said agreements (indemnity agreement) shall be losses of the enterprisers (indemnity loss) which occur from reparation of nuclear damages due to earthquakes or eruptions, or regular operation of reactors or damages to be compensated by the insurance contracts, which are not demanded by the sufferers for 10 years from the day of events, and others. The term of indemnity agreements is from the time of the conclusion to the date of suspension of the operation of reactors. Indemnity charges, amount of indemnity, limit of conclusion of indemnity agreements, notice, prescription and others are prescribed respectively. The government may dissolute indemnity agreements in specified particular cases, including violation of the provisions of the law concerning indemnification of nuclear damage by the enterprisers, etc. (Okada, K.)

  2. Compensation of damage caused by diverted nuclear substances

    International Nuclear Information System (INIS)

    Deprimoz, J.

    1981-10-01

    This paper provides a comprehensive analysis of the insurance system for nuclear liability. As a rule, if nuclear fuel, radioactive products or waste are governed by nuclear energy law providing for strict and channelled liability, their legal holder will pay for damage arising from them anywhere within 20 years after theft or diversion and 10 years after the nuclear incident. In most countries, atomic liability insurers will implicitly grant their cover through policies underwritten by legal holders. If diverted substances have a low specific radioactivity, their legal holder remains liable according to common law and insurance policies cover this conventional liability. (NEA) [fr

  3. Act of 19 June 1974 on Compensation for Nuclear Damage

    International Nuclear Information System (INIS)

    1974-01-01

    This Act which came into force on 18 September 1974 replaces the nuclear third party liability provisions of the 1962 Act on nuclear installations. Its adoption enabled the Danish Government to ratify the 1960 Paris Convention and the 1963 Brussels Supplementary Convention. In accordance with the principles prescribed by these Conventions, the Act establishes an absolute and limited third party liability system (75 million Danish Krone) and compulsory insurance for the operator of a nuclear installation situated in Denmark. In certain conditions, the State may have to intervene to ensure compensation of nuclear damage exceeding the financial security provided by the operator liable. (NEA) [fr

  4. Third party liability cover for nuclear damage and related problems

    International Nuclear Information System (INIS)

    Carbone, Ferdinando; Gambardella, Elio.

    1974-06-01

    This paper analyses the financial security and cover for third party liability for nuclear damage as provided for by Act No. 1860 of 31 December 1962 on the peaceful uses of nuclear energy. The relevant Sections of the Act are quoted and explained, as are the nuclear operator's obligation to furnish financial security for his liability. Different possible types of security and cover are described, also with reference to other national legislation. Finally, the author mentions the Paris Convention which provides the basis for Italian nuclear third party liability legislation. (NEA) [fr

  5. Economic damage caused by a nuclear reactor accident

    International Nuclear Information System (INIS)

    Goemans, T.; Schwarz, J.J.

    1988-01-01

    This study is directed towards the estimation of the economic damage which arises from a severe possible accident with a newly built 1000 MWE nuclear power plant in the Netherlands. A number of cases have been considered which are specified by the weather conditions during and the severity of the accident and the location of the nuclear power plant. For each accident case the economic damage has been estimated for the following impact categories: loss of the power plant, public health, evacuation and relocation of population, export of agricultural products, working and living in contaminated regions, decontamination, costs of transportation and incoming foreign tourism. The consequences for drinking water could not be quantified adequately. The total economic damage could reach 30 billion guilders. Besides the power plant itself, loss of export and decreasing incoming foreign tourism determine an important part of the total damage. 12 figs.; 52 tabs

  6. Survey of Codes Employing Nuclear Damage Assessment

    Science.gov (United States)

    1977-10-01

    surveyed codes were com- DO 73Mu 1473 ETN OF 1NOVSSSOLETE UNCLASSIFIED 1 SECURITY CLASSIFICATION OF THIS f AGE (Wh*11 Date Efntered)S<>-~C. I UNCLASSIFIED...level and above) TALLEY/TOTEM not nuclear TARTARUS too highly aggregated (battalion level and above) UNICORN highly aggregated force allocation code...vulnerability data can bq input by the user as he receives them, and there is the abil ’ity to replay any situation using hindsight. The age of target

  7. Radiation damage in nuclear waste ceramics

    International Nuclear Information System (INIS)

    Turcotte, R.P.; Roberts, F.P.; Rusin, J.M.; Wald, J.W.

    1982-01-01

    The text contains a number of specific observations about the radiation-induced changes in glass, glass-ceramic, and supercalcine nuclear waste forms. Other, more general conclusions can be summarized: Radiation-induced property changes follow an exponential ingrowth curve to saturation. Actinide host phases in both crystalline waste forms become X-ray amorphous. The magnitudes of the waste-form density changes observed could not be directly related to observed changes in the primary actinide phases. Although large crystal-structure changes occur in the materials studied, obvious physical degradation was not observed

  8. Damage caused to houses and equipment by underground nuclear explosions

    International Nuclear Information System (INIS)

    Delort, F.; Guerrini, C.

    1969-01-01

    A description is given of the damaged caused to various structures, buildings, houses, mechanical equipment and electrical equipment by underground nuclear explosions in granite. For each type of equipment or building are given the limiting distances for a given degree of damage. These distances have been related to a parameter characterizing the movement of the medium; it is thus possible to generalize the results obtained in granite, for different media. The problem of estimating the damage caused at a greater distance from the explosion is considered. (authors) [fr

  9. Indemnification of damage in the event of a nuclear accident

    International Nuclear Information System (INIS)

    2003-01-01

    The Workshop on the Indemnification of Damage in the Event of a Nuclear Accident, organised by the OECD Nuclear Energy Agency in close co-operation with the French authorities, was held in Paris from 26 to 28 November 2001. This event was an integral part of the International Nuclear Emergency Exercise INEX 2000. It attracted wide participation from national nuclear authorities, regulators, operators of nuclear installations, nuclear insurers and international organisations. The objective was to test the capacity of the existing nuclear liability and compensation mechanisms in the 29 countries represented at the workshop to manage the consequences of a nuclear emergency. This workshop was based upon the scenario used for the INEX 2000 Exercise, i.e. an accident simulated at the Gravelines nuclear power plant in the north of France in May 2001. These proceedings contain a comparative analysis of legislative and regulatory provisions governing emergency response and nuclear third party liability, based upon country replies to a questionnaire. This publication also includes the full responses provided to that questionnaire, as well as the texts of presentations made by special guests from Germany and Japan describing the manner in which the public authorities in their respective countries responded to two nuclear accidents of a very different nature and scale. (authors)

  10. Fundamental Technology Development for Radiation Damage in Nuclear Materials

    International Nuclear Information System (INIS)

    Kwon, Sang Chul; Kwon, J. H.; Kim, E. S. and others

    2005-04-01

    This project was performed to achieve technologies for the evaluation of radiation effects at materials irradiated at HANARO and nuclear power plants, to establish measurement equipment and software for the analysis of radiation defects and to set up facilities for the measurements of radiation damage with non-destructive methods. Major targets were 1) establishment of hot laboratories and remote handling facilities/ technologies for the radioactive material tests, 2) irradiation test for the simulation of nuclear power plant environment and measurement/calculation of physical radiation damage, 3) evaluation and analysis of nano-scale radiation damage, 4) evaluation of radiation embrittlement with ultrasonic resonance spectrum measurement and electromagnetic measurement and 5) basic research of radiation embrittlement and radiation damage mechanism. Through the performance of 3 years, preliminary basics were established for the application research to evaluation of irradiated materials of present nuclear power plants and GEN-IV systems. Particularly the results of SANS, PAS and TEM analyses were the first output in Korea. And computer simulations of radiation damage were tried for the first time in Korea. The technologies will be developed for the design of GEN-IV material

  11. Nuclear data for radiation damage assessment and related safety aspects

    International Nuclear Information System (INIS)

    Kocherov, N.P.

    1989-12-01

    The IAEA Advisory Group Meeting on Nuclear Data for Radiation Damage Assessment and Related Safety Aspects was held at the IAEA Headquarters in Vienna, 19-22 September 1989. This report contains the conclusions and recommendations of this meeting. The papers which the participants prepared for and presented at the meeting will be published as an IAEA Technical Document. (author)

  12. Vienna convention on civil liability for nuclear damage

    International Nuclear Information System (INIS)

    1996-01-01

    The Vienna Convention on Civil Liability for Nuclear Damage was adopted on 21 May 1963 and was opened for signature on the same day. It entered into force on 12 November 1977, i.e. three months after the date of deposit with the Director General of the fifth instrument of ratification, in accordance with Article 23

  13. Vienna convention on civil liability for nuclear damage

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-20

    The Vienna Convention on Civil Liability for Nuclear Damage was adopted on 21 May 1963 and was opened for signature on the same day. It entered into force on 12 November 1977, i.e. three months after the date of deposit with the Director General of the fifth instrument of ratification, in accordance with Article 23.

  14. The law on indemnity agreement for compensation of nuclear damage

    International Nuclear Information System (INIS)

    1977-01-01

    The Government can conclude the contract with atomic energy entrepreneurs promising that it would indemnify the loss caused by the payment of indemnity by the latter for the nuclear damage which cannot be covered with responsibility insurance contract and other measures for indemnifying the damages upon the occurrence of responsibility of said entrepreneurs, who promises to pay the rate for indeminty. The loss to be indemnified by the Government with said contract should be limited to the loss caused by the payment of indemnity by said entrepreneurs for the damage caused by earthquakes or volcanic activities, normal operation of reactors (to be specified by the cabinet order) or the damage which can be covered with the responsibility insurance contract so long as the fact becoming its cause is concerned and the indemnification for which was not demanded by the sufferer in 10 years elapsed since the outbreak of such fact, and the damage caused by the entry of nuclear ships in foreign territorial waters, which cannot be covered with the measures for indemnifying the damage. The sum of the rate for indemnity is specified

  15. Indemnification of Damage in the Event of a Nuclear Accident

    International Nuclear Information System (INIS)

    2006-01-01

    The Second International Workshop on the Indemnification of Nuclear Damage was held in Bratislava, Slovak Republic, from 18 to 20 May 2005. The workshop was co-organised by the OECD Nuclear Energy Agency and the Nuclear Regulatory Authority of the Slovak Republic. It attracted wide participation from national nuclear authorities, regulators, operators of nuclear installations, nuclear insurers and international organisations. The purpose of the workshop was to assess the third party liability and compensation mechanisms that would be implemented by participating countries in the event of a nuclear accident taking place within or near their borders. To accommodate this objective, two fictitious accident scenarios were developed: one involving a fire in a nuclear installation located in the Slovak Republic and resulting in the release of significant amounts of radioactive materials off-site, and the other a fire on board a ship transporting enriched uranium hexafluoride along the Danube River. The first scenario was designed to involve the greatest possible number of countries, with the second being restricted to countries with a geographical proximity to the Danube. These proceedings contain the papers presented at the workshop, as well as reports on the discussion sessions held. (author)

  16. Costs for insurance of civil responsibility for nuclear damage during transportation of nuclear materials

    International Nuclear Information System (INIS)

    Amelina, M.E.; Arsent'ev, S.V.; Molchanov, A.S.

    2009-01-01

    The article considers the method of calculation of rates for insurance of civil responsibility for nuclear damage during transportation of nuclear materials, which can minimize the insurer's costs for this type of insurance in situation when there is no statistics available and it is not possible to calculate the insurance rate by the traditional means using the probability theory

  17. Study on radiation damage of electron and γ-rays and mechanism of nuclear hardening

    International Nuclear Information System (INIS)

    Jing Tao

    2001-01-01

    Radiation damage effects of electrons and γ-rays are presented. The damage defects are studied by experimental methods. On the basis of these studies the damage mechanism and nuclear hardening techniques are studied

  18. Advanced nuclear data for radiation-damage calculations

    International Nuclear Information System (INIS)

    MacFarlane, R.E.; Foster, D.G. Jr.

    1983-01-01

    Accurate calculations of atomic displacement damage in materials exposed to neutrons require detailed spectra for primary recoil nuclei. Such data are not available from direct experimental measurements. Moreover, they cannot always be computed accurately starting from evaluated nuclear data libraries such as ENDF/B-V that were developed primarily for neutron transport applications, because these libraries lack detailed energy-and-angle distributions for outgoing charged particles. Fortunately, a new generation of nuclear model codes is now available that can be used to fill in the missing spectra. One example is the preequilibrium statistical-model code GNASH. For heating and damage applications, a supplementary code called RECOIL has been developed. RECOIL uses detailed reaction data from GNASH, together with angular distributions based on Kalbach-Mann systematics to compute the energy and angle distributions of recoil nuclei. The energy-angle distributions for recoil nuclei and outgoing particles are written out in the new ENDF/B File 6 format. The result is a complete set of nuclear data that can be used to calculate displacement-energy production, heat production, gas production, transmutation, and activation. Sample results for iron are given and compared to the results of conventional damage models such as those used in NJOY

  19. Damage assessment of nuclear containment against aircraft crash

    Energy Technology Data Exchange (ETDEWEB)

    Iqbal, Mohd Ashraf, E-mail: iqbal_ashraf@rediffmail.com; Sadique, Md. Rehan, E-mail: rehan.sadique@gmail.com; Bhargava, Pradeep, E-mail: bhpdpfce@iitr.ac.in; Bhandari, N.M., E-mail: nmbcefce@iitr.ac.in

    2014-10-15

    Highlights: • Damage assessment of nuclear containment is studied against aircraft crash. • Four impact locations have been identified at the outer containment shell. • The mid of the total height has been found to be most vulnerable location. • The crown of dome has been found to be the strongest location. • Phantom F4 caused more localized and severe damage compared to other aircrafts. - Abstract: The behavior of nuclear containment structure has been studied against aircraft crash with an emphasis on the influence of strike location. The impact locations identified on the BWR Mark III type nuclear containment structure are mid-height, junction of dome and cylinder, crown of dome and arc of dome. The containment at each of the above locations has been impacted normally by Phantom F-4, Boeing 707-320 and Airbus A320 aircrafts. The loading of the aircraft has been assigned through the corresponding reaction-time response curve. ABAQUS/Explicit finite element code has been used to carry out the three-dimensional numerical simulations. The concrete damaged plasticity model was used to simulate the behavior of concrete while the behavior of steel reinforcement was incorporated using the Johnson–Cook elasto-viscoplastic material model. The mid-height of containment has been found to experience most severe deformation against each aircraft. Phantom F4 has been found to be most disastrous at each location. The results have been compared with those of the available studies with respect to the containment deformation.

  20. Automated analysis of damages for radiation in plastics surfaces; Analisis automatizado de danos por radiacion en superficies plasticas

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, C; Camacho M, E; Tavera, L; Balcazar, M [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1990-02-15

    Analysis of damages done by the radiation in a polymer characterized by optic properties of polished surfaces, of uniformity and chemical resistance that the acrylic; resistant until the 150 centigrade grades of temperature, and with an approximate weight of half of the glass. An objective of this work is the development of a method that analyze in automated form the superficial damages induced by radiation in plastic materials means an images analyst. (Author)

  1. Risk in Nuclear Industry. Liability for Nuclear Damage. Status of the Problem in the Russian Federation

    International Nuclear Information System (INIS)

    Kovalevich, Oleg M.; Gavrilov, Sergey D.; Voronov, Dmitry B.

    2001-01-01

    Russia is one of a few nuclear power states obtaining the whole number of nuclear fuel cycle (NFC) components - from mining of uranium and on-site electricity production, from NPP spent nuclear fuel processing and extracted fissile materials and radionuclides, which are available in industry, in medicine and in other relevant areas, to radioactive waste processing and disposal. For this reason it is very important to solve the problem of nuclear fuel cycle safety as it is a single system task with an adequate approach for all cycle components. The problem is that NFC facilities are technologically various and refer to different industries (mining, machinery engineering, power engineering, chemistry, etc.). Besides, the above facilities need the development of various scientific bases. The most NFC facilities is directly connected with peaceful use of nuclear energy and with military nuclear industry, as the defense orders stimulated the development of NFC. The specific attention to safety problems at the beginning of nuclear complex foundation adversely affected the state attitude towards the risk in nuclear industry, it has left the traces at present. In our paper we touch upon the problems of risk and the liability for nuclear damage for the third persons. The problems of nuclear damage compensation for nuclear facilities personnel and for the owners (operating organizations) are beyond our subject

  2. Station blackout core damage frequency in an advanced nuclear reactor

    International Nuclear Information System (INIS)

    Carvalho, Luiz Sergio de

    2004-01-01

    Even though nuclear reactors are provided with protection systems so that they can be automatically shut down in the event of a station blackout, the consequences of this event can be severe. This is because many safety systems that are needed for removing residual heat from the core and for maintaining containment integrity, in the majority of the nuclear power plants, are AC dependent. In order to minimize core damage frequency, advanced reactor concepts are being developed with safety systems that use natural forces. This work shows an improvement in the safety of a small nuclear power reactor provided by a passive core residual heat removal system. Station blackout core melt frequencies, with and without this system, are both calculated. The results are also compared with available data in the literature. (author)

  3. The Brussels I Regulation and Liability for Nuclear Damage

    International Nuclear Information System (INIS)

    Handrlica, J.

    2010-01-01

    Prior to 2004, the map of the European Union seemed to be basically identical to the map of the contracting parties to the Paris Convention on Third Party Liability in the Field of Nuclear Energy of 1960 ('the Paris Convention'). The 2004 and 2007 enlargements were mainly composed of the contracting parties to the Vienna Convention on Civil Liability for Nuclear Damage of 1963 ('the Vienna Convention'). In various discussions, the term 'nuclear liability patchwork' is used to describe this existing situation. One of the problems arising from this 'patchwork' is that, while a uniform legal framework was established for matters of jurisdiction and the enforcement of decisions under the authority given to the European Union ('EU') by the Council Regulation on jurisdiction and the recognition and enforcement of judgements in civil and commercial matters ('Brussels Regulation'), this overall framework does not apply to particular matters governed by the special conventions to which member states may be contracting parties, see Article 71 of the Brussels Regulation. This paper aims to outline the 'patchwork' of these rules that are applicable to nuclear third party liability cases in the EU and to point out the main consequences arising from this legal framework difficult to comprehend.5 Its scope, however, is limited to the legal issues arising from a nuclear incident occurring in a nuclear installation situated within the territory of the European Union

  4. Terrorism cover in France for property damage including nuclear risks

    International Nuclear Information System (INIS)

    Stanislas, A.

    2004-01-01

    The obligation to include terrorism cover in all Property Damage policies issued on the French Market is ruled by an Act of 1986 and introduced under Section R 126-2 of the French Code of Insurance. This section stipulates that Property Damage policies must provide cover for damage resulting from acts of terrorism, with the same deductible and the same limit than that of the other damage covered in the policy. Soon after the dramatic events of September 11, 2001 in the United States and although reinsurers worldwide restricted their offer of capacities, French insurers recognized that they had to maintain this global cover for the benefit of their insurers. After difficult discussions between insurers, reinsurers, brokers, risk managers and representatives of the State, the creation of a new Pool, backed with a State guarantee, was decided in less than three months. Effective January 1, 2002 and called Gestion d'Assurance et de Reassurance des Risques Attentats et Actes de Terrorisme (GAREAT), the Pool offers a multiple layers stop-loss cover for Property Damage only, i.e. excluding TPL policies. Considering that nuclear risks should be treated in the same way as other industrial risks, it was decided that they would be covered by GAREAT as well. In the meantime, by a Decree of December 28, 2001 modifying Section R 126-2, a special provision, aiming at reducing the limit and thus the price of this cover, was introduced in the Code. The purpose of this paper is to expose the present situation applying through GAREAT and, after two years of operation to discuss future developments, including other sources of capacity for the coverage of acts of terrorism in nuclear risks insurance.(author)

  5. Indemnification for nuclear damages - recent developments in the United States

    International Nuclear Information System (INIS)

    Shapar, H.K.

    1981-10-01

    Public liability for nuclear damages in the United States is dealt with by a Federal statutory system. The Price-Anderson Act provides a system of compensation for such damages with an overall limit of $560 million. This fund is composed of private insurance, a utility assessment pool, and Federal government indemnity. The 1979 accident at the Three Mile Island nuclear station resulted in a less-than-full-scale test of the system. For the most part, the system has performed as intended although certain problems have been brought to light. Legislative proposal since the accident have focused on increasing the $560 million limitation on liability, but so far none of these proposals has been acted upon by the U.S. Congress. In the next several years, the Nuclear Regulatory Commission and possibly Congress will consider application of the Price-Anderson system to high-level waste facilities. The Commission must file with the Congress within two years a comprehensive report on the Price-Anderson Act, including recommendations for its continuation and amendment. (NEA) [fr

  6. Prevention of damage and 'residual risk' in nuclear power laws

    International Nuclear Information System (INIS)

    Greipl, C.

    1992-01-01

    The concept of prevention of damage within the framework of nuclear power laws includes averting danger for the protection of third parties and preventing risks for the partial protection of third parties with the proviso that still a desire to use the concept 'residual risk' in addition, it should be limited, on the grounds of what can be reasonably expected, to those risks which cannot be reduced any further by the government, i.e. to risks which the public in general and third parties ('actually') must accept. In the future, questions regarding safety systems should be taken into account exclusively withing the context of 'what is necessary for protection against damage in keeping with the latest developments in science and technology' and not at the discretion of the law in denying permission according to Article 7 Paragraph 2 Atomic Energy Law. (orig.) [de

  7. Regional analysis of the nuclear-electricity; Analisis regional de la nucleoelectricidad

    Energy Technology Data Exchange (ETDEWEB)

    Parera, M. D., E-mail: dparera@cnea.gov.ar [CNEA, Gerencia de Planificacion, Coordinacion y Control, Subgerencia de Planificacion Estrategica, Av. Gral. Paz 1499, B1650KNA San Martin, Buenos Aires (Argentina)

    2011-11-15

    In this study was realized a regional analysis of the Argentinean electric market contemplating the effects of regional cooperation, the internal and international interconnections; and the possibilities of insert of new nuclear power stations were evaluated in different regions of the country, indicating the most appropriate areas to carry out these facilities to increase the penetration of the nuclear energy in the national energy matrix. Also was studied the interconnection of the electricity and natural gas markets, due to the existent linking among both energy forms. With this purpose the program Message (Model for energy supply strategy alternatives and their general environmental impacts) was used, promoted by the International Atomic Energy Agency. This model carries out an economic optimization level country, obtaining the minimum cost as a result for the modeling system. The division for regions realized by the Compania Administradora del Mercado Mayorista Electrico (CAMMESA) was used, which divides to the country in eight regions. They were considered the characteristics and necessities of each one of them, their respective demands and offers of electric power and natural gas, as well as their existent and projected interconnections, composed by the electric lines and gas pipes. According to the results obtained through the model, the nuclear-electricity is a competitive option. (Author)

  8. Protocol to amend the Vienna convention on civil liability for nuclear damage. Convention on supplementary compensation for nuclear damage. Final act

    International Nuclear Information System (INIS)

    1998-01-01

    The document reproduces the Final Act of the Diplomatic Conference held in Vienna between 8-12 September 1997 which adopted the Protocol to Amend the Vienna Convention on Civil Liability for Nuclear Damage, and the Convention on Supplementary Compensation for Nuclear Damage

  9. Protocol to amend the Vienna convention on civil liability for nuclear damage. Convention on supplementary compensation for nuclear damage. Final act

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-23

    The document reproduces the Final Act of the Diplomatic Conference held in Vienna between 8-12 September 1997 which adopted the Protocol to Amend the Vienna Convention on Civil Liability for Nuclear Damage, and the Convention on Supplementary Compensation for Nuclear Damage

  10. 75 FR 64717 - Convention on Supplementary Compensation for Nuclear Damage Contingent Cost Allocation

    Science.gov (United States)

    2010-10-20

    ... DEPARTMENT OF ENERGY Convention on Supplementary Compensation for Nuclear Damage Contingent Cost... Supplementary Compensation for Nuclear Damage (``CSC'') including its obligation to contribute to an international supplementary fund in the event of certain nuclear incidents. The NOI provided a September 27...

  11. Legislative Study on China’s Compensation for Nuclear Damage Liability

    Directory of Open Access Journals (Sweden)

    Jiu Liu

    2018-06-01

    Full Text Available The civil nuclear industry plays an important role in improving environmental quality and safeguarding energy security in China. Nevertheless, the industry is facing a huge risk of nuclear accident damage. The legal system of nuclear damage compensation is of vital importance for the industry to address potential risks. The Nuclear Safety Law, which has recently been published in China, stipulates two articles about nuclear damage compensation in principle. However, in general, the current nuclear damage compensation legal system in China has not yet been made systematic and there are still problems, such as a lack of maneuverability and details. This paper adopts qualitative and quantitative methodologies to summarize and analyze the current legislation and regulation pertaining to civil nuclear damage compensation liability in China and analyzes the shortages and deficiencies of these rules in detail by using legal analysis methods. Suggestions to establish and perfect China’s legal system of nuclear damage compensation are proposed to safeguard the healthy development of the civil nuclear industry and remedy damages brought about by nuclear accidents. Such a legal system should contain the elements of clear legislative goals and objectives, a specific definition and scope of nuclear damage, strict and sole responsibility principles for operators, an appropriate liability amount, a stable financial guarantee for operators, and national supplementary liability.

  12. Nuclear oxidative damage correlates with poor survival in colorectal cancer.

    LENUS (Irish Health Repository)

    Sheridan, J

    2012-02-01

    Oxidative DNA damage results from DNA adducts such as 8-oxo-7, 8 dihydro-2\\'-deoxyguanosine (8-oxo-dG), which is a pro-mutagenic lesion. No known association between 8-oxo-dG, disease progression and survival exists in colorectal cancer (CRC). We examined levels of 8-oxo-dG in sporadic CRC to determine its relationship with pathological stage and outcome. A total of 143 CRC patients and 105 non-cancer patients were studied. Nuclear and cytoplasmic 8-oxo-dG was assessed using immunohistochemistry. Double immunofluorescence using 8-oxo-dG and manganese superoxide dismutase (MnSOD) antibodies localised cytoplasmic 8-oxo-dG. Apoptosis was detected using TUNEL. Nuclear staining levels were similar in tumour tissue and matched normal mucosa in both epithelial (P=0.22) and stromal (P=0.85) cells. Epithelial cytoplasmic staining was greater in tumour tissue (P<0.001). Double immunofluorescence localised cytoplasmic 8-oxo-dG to mitochondria. Epithelial and stromal nuclear 8-oxo-dG decreased with local disease spread, but highest levels were found in distant disease (P<0.01). Survival was related to epithelial nuclear and stromal staining in normal mucosa (P<0.001) and tumour (P<0.01) but was unrelated to cytoplasmic staining. Normal control cells in tissue from cancer patients with high levels of 8-oxo-dG failed to undergo cell death. 8-oxo-dG may be an important biomarker of disease risk, progression and survival for CRC patients.

  13. Research on spatial Model and analysis algorithm for nuclear weapons' damage effects

    International Nuclear Information System (INIS)

    Liu Xiaohong; Meng Tao; Du Maohua; Wang Weili; Ji Wanfeng

    2011-01-01

    In order to realize the three dimension visualization of nuclear weapons' damage effects. Aiming at the characteristics of the damage effects data, a new model-MRPCT model is proposed, and this model can carry out the modeling of the three dimension spatial data of the nuclear weapons' damage effects. For the sake of saving on the memory, linear coding method is used to store the MRPCT model. On the basis of Morton code, spatial analysis of the damage effects is completed. (authors)

  14. Ukraine. Law on civil liability for nuclear damage and its financial security (13 december 2001)

    International Nuclear Information System (INIS)

    Anon.

    2002-01-01

    The objective of this law is to regulate civil liability for the compensation of damage resulting from activities involving the utilisation of nuclear energy for peaceful purposes. It governs relations in respect of civil liability for nuclear damage, establishes the rules and procedures for compensation for damage caused by a nuclear incident, defines the methods of ensuring financial security of civil liability and establishes its limits. (N.C.)

  15. The amendment of the law on compensation for nuclear damage in Japan

    International Nuclear Information System (INIS)

    Tanikawa, H.

    2000-01-01

    The legal regime relating to the compensation for nuclear damage in Japan is governed by 'the Law on Compensation for Nuclear Damage' and the 'Law on indemnity Agreement for Compensation of Nuclear Damage'. The basic liability scheme on compensation for nuclear damage in the Compensation law is constituted on the basis of strict and unlimited liability, and such liability is channeled to a nuclear undertaker who is engaged on the operation of the reactor, etc.Furthermore, in order to operate a reactor a nuclear undertaker has to have provided financial security for compensation of nuclear damage by means of contracts, for liability insurance in respect of potential nuclear damage and an indemnity agreement for compensation of nuclear damage or the deposit. In addition to this financial security, in the event that nuclear damage occurs, and if necessary, the Government shall give to a nuclear undertaker such aid as required for him to compensate the nuclear damage. The financial security amount specified in the compensation Law has been increased to JPY (Japan yen) 60 billion. The necessity for special requirements in relation to financial security and/or the level of its amount in case of decommissioning of reactors, storage of nuclear spent fuel outside the power plant, radioisotopes other than nuclear fuel materials, or high level waste of nuclear fuel material, or the operation of experimental reactors for nuclear fusion, etc. shall be examined in the near future according to developments made in this field and the corresponding necessity for financial security for each case. (N.C.)

  16. Neutron analysis of the fuel of high temperature nuclear reactors; Analisis neutronico del combustible de reactores nucleares de alta temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Bastida O, G. E.; Francois L, J. L., E-mail: gbo729@yahoo.com.mx [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2014-10-15

    In this work a neutron analysis of the fuel of some high temperature nuclear reactors is presented, studying its main features, besides some alternatives of compound fuel by uranium and plutonium, and of coolant: sodium and helium. For this study was necessary the use of a code able to carry out a reliable calculation of the main parameters of the fuel. The use of the Monte Carlo method was convenient to simulate the neutrons transport in the reactor core, which is the base of the Serpent code, with which the calculations will be made for the analysis. (Author)

  17. Present status and prospects of the compensation system for nuclear damage in China

    International Nuclear Information System (INIS)

    Zhou, Z.; Liu, C.

    1993-01-01

    In handling liability for nuclear damage matters, China currently adheres to the rules stipulated in the administrative legal document regarding liability to third parties for nuclear damage enacted by the State Council, in which it is defined that the principles of absolute liability, limitation of liability and single competent court are applicable in China. The Chinese government shall enact state laws on liability for nuclear damage on the basis of the above-mentioned legal document and with active consideration of the function of the state in the compensation for nuclear damage

  18. Analisi matematica

    CERN Document Server

    Canuto, Claudio

    2014-01-01

    Il presente testo intende essere di supporto ad un secondo insegnamento di Analisi Matematica in quei corsi di studio (quali ad esempio Ingegneria, Informatica, Fisica) in cui lo strumento matematico parte significativa della formazione dell'allievo. I concetti e i metodi fondamentali del calcolo differenziale ed integrale in più variabili, le serie di funzioni e le equazioni differenziali ordinarie sono presentati con l'obiettivo primario di addestrare lo studente ad un loro uso operativo, ma critico. L'impostazione didattica dell'opera ricalca quella usata nel testo parallelo di Analisi Matematica I. La modalità di presentazione degli argomenti ne permette un uso flessibile e modulare. Lo stile adottato privilegia la chiarezza e la linearità dell'esposizione. Il testo organizzato su due livelli di lettura. Uno, più essenziale, permette allo studente di cogliere i concetti indispensabili della materia, di familiarizzarsi con le relative tecniche di calcolo e di trovare le giustificazioni dei principali r...

  19. Statistical analysis about corrosion in nuclear power plants; Analisis estadistico de la corrosion en centrales nucleares de potencia

    Energy Technology Data Exchange (ETDEWEB)

    Naquid G, C.; Medina F, A.; Zamora R, L. [Instituto Nacional de Investigaciones Nucleares, Gerencia de Ciencia de Materiales, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2000-07-01

    Nowadays, it has been carried out the investigations related with the structure degradation mechanisms, systems or and components in the nuclear power plants, since a lot of the involved processes are the responsible of the reliability of these ones, of the integrity of their components, of the safety aspects and others. This work presents the statistics of the studies related with materials corrosion in its wide variety and specific mechanisms. These exist at world level in the PWR, BWR, and WWER reactors, analysing the AIRS (Advanced Incident Reporting System) during the period between 1993-1998 in the two first plants in during the period between 1982-1995 for the WWER. The factors identification allows characterize them as those which apply, they are what have happen by the presence of some corrosion mechanism. Those which not apply, these are due to incidental by natural factors, mechanical failures and human errors. Finally, the total number of cases analysed, they correspond to the total cases which apply and not apply. (Author)

  20. Legal analysis at the Law for Civil liabilities by nuclear damage

    International Nuclear Information System (INIS)

    Gonzalez G, A.

    2000-01-01

    The present work has the objective to analyse in specific terms the legal regime of the Civil liability by nuclear damage. It has been the intention of that this compilation is the initiation of a large way which awake the interests of jurists and specialists dedicated to study the aspects as the liability by nuclear damage, compensation guarantee, risk and nuclear damage among others. The peaceful applications of the nuclear energy require the necessity of a legal ordinance that it is updated according to the nuclear technology development that the regulations of the common law do not cover. This work is initiated mentioning some antecedents of the nuclear energy law in Mexico. Also is realized the study of the elemental concepts and definitions about the subject as the evolution of the legal figure in the National law frame where the jurist must do an incursion in the nuclear field and make use of scientific and technical terminology. It was analysed and it was made the reflection of the legal figure of liability, its exoneration cases, about the concepts of risk and nuclear damage overcoming the conceptual error among them. It is talked about the study of nuclear damage and its repairing as financial guarantee to compensate to the people injured by a nuclear accident. Finally, it was treated about the legal analysis and proposals of additions and reforms for updating the Nuclear damage liability Law, concluding with general contributions to the Law resulting products of this work. (Author)

  1. Fatigue damage of nuclear facilities; Endommagement par fatigue des installations nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    The conference on the fatigue damage of nuclear facilities, organized by the SFEN (french society of nuclear energy), took place at Paris the 23. of november 2000. Eleven papers were presented, showing the state of the art and the research programs in the domain of the sizing rules, safety, installations damage, examination and maintenance. (A.L.B.)

  2. Just and reasonable distribution of funds for limited damages in the event of nuclear disasters

    International Nuclear Information System (INIS)

    Schattke, H.

    1985-01-01

    A suggestion is made to make legal dispositions for the distribution of funds before a nuclear event. The concept incorporates the following material-legal elements: Proportionate reduction of damages compensation claims in case the funds for liability and coverage are insufficient; creation of reserve funds for late damage; legal preference of personal damage and only subsequent satisfaction of demand for compensation of nuclear industries. (orig.) [de

  3. Nuclear energy: liability for damage to the environment according to the National Environmental Law

    International Nuclear Information System (INIS)

    Eiras, Sergio Alves; Couto, Roberto Toscano

    1995-01-01

    Liability for damage of the environment is the kind of subject which arouses heated debates in the nuclear energy field among the jurists. Brazil lacks a specific environmental law upon which settlement on questions of nuclear damage could be based. In spite of such lackness, considerable progress has been achieved with the obligatory elaboration of the Environmental Impact Assessment (EIA), the constitutional rules establishing competence and responsibilities on this matter, and some scattered laws. The objective of this work is to focus the responsibility of the Union that exercised the monopoly of nuclear activities, its agents and the team of experts which elaborate the EIA as well as the damage to the environment from a nuclear accident. This study is based on the legal definitions of nuclear reactor, radioactive waste and product, radioisotope, among others. It also focuses some proposed amendments of the law regulating both the civil and criminal liabilities for nuclear damage. (author). 7 refs

  4. Safety technical investigation activities for shipment of damaged spent fuels from Fukushima Daiichi Nuclear Power Station

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Japan Nuclear Energy Safety Organization(JNES) carries out the investigation for damaged fuel transportation from Fukushima Daiichi Nuclear Power Station(1F) under safety condition to support Nuclear Regulation Authority (NRA). In 2012 fiscal year, JNES carried out the investigation of spent fuel condition in unit 4 of 1F and actual result of leak fuel transport in domestic /other countries. From this result, Package containing damaged fuel from unit 4 in 1F were considered. (author)

  5. New tendencies in the legal mark give the civil liability for nuclear damages

    International Nuclear Information System (INIS)

    Gil Portela, Rosario; Alonso Gonzalez, Ivonne

    1998-01-01

    The development gives an indispensable legal mark for the execution a nuclear program it includes relative special dispositions to the civil liability for nuclear damages. The existence gives an international regime in this matter and its current improvement, give the one that Cuba is State it leaves, it conditions the inclusion additional requirements in the national legislative system on civil liability relatives to the possible damages that it could cause to the personal one and environment in general a nuclear accident

  6. Radiation damage studies related to nuclear waste forms

    International Nuclear Information System (INIS)

    Gray, W.J.; Wald, J.W.; Turcotte, R.P.

    1981-12-01

    Much of the previously reported work on alpha radiation effects on crystalline phases of importance to nuclear waste forms has been derived from radiation effects studies of composite waste forms. In the present work, two single-phase crystalline materials, Gd 2 Ti 2 O 7 (pyrochlore) and CaZrTi 2 O 7 (zirconolite), of relative importance to current waste forms were studied independently by doping with 244 Cm at the 3 wt % level. Changes in the crystalline structure measured by x-ray diffraction as a function of dose show that damage ingrowth follows an expected exponential relationship of the form ΔV/V 0 = A[1-exp(-BD)]. In both cases, the materials became x-ray amorphous before the estimated saturation value was reached. The predicted magnitudes of the unit cell volume changes at saturation are 5.4% and 3.5%, respectively, for Gd 2 Ti 2 O 7 and CaZrTi 2 O 7 . The later material exhibited anisotropic behavior in which the expansion of the monoclinic cell in the c 0 direction was over five times that of the a 0 direction. The effects of transmutations on the properties of high-level waste solids have not been studied until now because of the long half-lives of the important fission products. This problem was circumvented in the present study by preparing materials containing natural cesium and then irradiating them with neutrons to produce 134 Cs, which has only a 2y half-life. The properties monitored at about one year intervals following irradiation have been density, leach rate and microstructure. A small amount of x-ray diffraction work has also been done. Small changes in density and leach rate have been observed for some of the materials, but they were not large enough to be of any consequence for the final disposal of high level wastes

  7. The new definition of nuclear damage in the 1997 protocol to amend the 1963 vienna convention on civil liability for nuclear damage

    International Nuclear Information System (INIS)

    Soljan, V.

    2000-01-01

    This communication analyzes the content and the impact of the new definition of nuclear damage contented in the amendment protocol of the Vienna Convention relative to the civil liability in the 1963 Convention. Having in mind the experience of the Three Mile Island and Chernobyl accidents, it is demonstrated that the costs of preventive measures, damage to the environment and economic loss may constitute substantial portions of the total damage following a nuclear accident. Then, the new definition is studied in detail, on insisting on the notion of economic loss. A development is devoted to the question of damage to the environment. The preventive measures are studied and their conditions of the compensation receivability evoked with the criteria of reasonable measures. (N.C.)

  8. Aging and oxidatively damaged nuclear DNA in animal organs

    DEFF Research Database (Denmark)

    Møller, Peter; Løhr, Mille; Folkmann, Janne K

    2010-01-01

    Oxidative stress is considered to contribute to aging and is associated with the generation of oxidatively damaged DNA, including 8-oxo-7,8-dihydroguanine. We have identified 69 studies that have measured the level of oxidatively damaged DNA in organs of animals at various ages. In general, organs...... with limited cell proliferation, i.e., liver, kidney, brain, heart, pancreas, and muscle, tended to show accumulation of DNA damage with age, whereas organs with highly proliferating cells, such as intestine, spleen, and testis, showed more equivocal or no effect of age. A restricted analysis of studies...... evidence for aging-associated accumulation of oxidatively damaged DNA in organs with limited cell proliferation....

  9. Need for a probabilistic fire analysis at nuclear power plants; Necesidad de un analisis probabilista de incendios en una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Calabuig Beneyto, J L [Empresarios Agrupados, A.I.E., Madrid (Spain); Ibanez Aparicio, J [Asociacion Nuclear ASCO, Barcelona (Spain)

    1993-12-15

    Although fire protection standards for nuclear power plants cover a wide scope and are constantly being updated, the existence of certain constraints makes it difficult to precisely evaluate plant response to different postulatable fires. These constraints involve limitations such as: - Physical obstacles which impede the implementation of standards in certain cases; - Absence of general standards which cover all the situations which could arise in practice; - Possible temporary noncompliance of safety measures owing to unforeseen circumstances; - The fact that a fire protection standard cannot possibly take into account additional damages occurring simultaneously with the fire; Based on the experience of the ASCO NPP PSA developed within the framework of the joint venture, INITEC-INYPSA-EMPRESARIOS AGRUPADOS, this paper seeks to justify the need for a probabilistic analysis to overcome the limitations detected in general application of prevailing standards. (author)

  10. Nuclear damage under the 1997 protocol: conventional thinking?

    International Nuclear Information System (INIS)

    Warren, G.

    2000-01-01

    This communication expresses the critical point of view of nuclear insurers about the international civil liability system and tackles questions about the current revision of this system. After having examined the nuclear risk nature in the insurance point of view and remind the objective of nuclear conventions in this context, the author expresses the opinion that compensation means, planned by these conventions, can be suitable to limited nuclear accident but would be insufficient to face the consequences of a serious nuclear accident. (N.C.)

  11. Ecological impacts and damage - comparison of selected components for nuclear and conventional power plants (example of Mochovce nuclear power plant)

    International Nuclear Information System (INIS)

    Bucek, M.

    1984-01-01

    A comparison is given of ecological damage for the nuclear power plant in Mochovce and a conventional power plant with the same power. Ecological effects and damage are divided into three groups: comparable damage, ecological damage caused only by conventional power plants and ecological damage caused only by nuclear power plants. In the first group the factors compared are land requisition, consumption of utility water and air consumption. In the second group are enumerated losses of crops (cereals, sugar beet, potatoes, oleaginous plants) and losses caused by increased disease rate owing to polluted environment by conventional power plants. In the third group health hazards are assessed linked with ionizing radiation. Also considered are vent stack escapes. (E.S.)

  12. Nur77 forms novel nuclear structures upon DNA damage that cause transcriptional arrest

    International Nuclear Information System (INIS)

    Leseleuc, Louis de; Denis, Francois

    2006-01-01

    The orphan nuclear receptor Nur77 has been implicated in both growth and apoptosis, and its function and activity can be modulated by cellular redistribution. Green fluorescent protein-tagged Nur77 was used to evaluate the role of Nur77 intracellular redistribution in response to genotoxic stress. Selected DNA damaging agents and transcription inhibition lead to rapid redistribution of Nur77 into nuclear structures distinct from conventional nuclear bodies. These nuclear bodies formed transiently were tightly bound to the nuclear matrix and conditions that lead to their appearance were associated with Nur77 transcriptional inhibition. The formation of Nur77 nuclear bodies might be involved in programmed cell death modulation upon exposure to DNA damaging agents that inhibit transcription by sequestrating this proapoptotic factor in dense nuclear structures

  13. Legal responsibility for damage caused by nuclear accidents

    International Nuclear Information System (INIS)

    Brink, J.J. van den.

    1986-04-01

    In this essay a treatment is given of the legal third-party risks of licencees of nuclear power plants. It is regarded to what extent the actual responsibility arrangements provide an adequate protection to the citizen against potential risks of a nuclear power plant. (Auth.)

  14. New national legislation on compensation of nuclear damage

    International Nuclear Information System (INIS)

    Guerra Machado de Faria, N.

    1981-10-01

    This paper describes the nuclear third party liability system within the Brazilian legal framework. Following some considerations regarding the development of nuclear energy it then focuses on the relationship between accident prevention and third party liability and on the political administrative framework related to the nuclar industry in Brazil. (NEA) [fr

  15. Through the looking glass: placing India's new civil liability regime for nuclear damage in context

    International Nuclear Information System (INIS)

    Gruendel, Robert J.; Kini, Els Reynaers

    2012-01-01

    Until India adopted the Civil Liability for Nuclear Damage Act, 2010 (Liability Act) and the Civil Liability for Nuclear Damage Rules, 2011 (Liability Rules or Rules), no specific legislation was in place to govern nuclear liability or to compensate victims for damages due to a nuclear incident in India. Before delving into a more legal-technical analysis of the Liability Act and Rules (Part B), it is worth first briefly touching upon India's general energy situation, which necessarily influences India's policies, laws and negotiating strategies while also driving the significant business opportunities in the nuclear energy sector (Part A). Taking a look at India's energy sector today also underscores the sheer size of India's plans to build new nuclear power plants, which stands in dramatic contrast to the goals of many other countries. In this article, we will address the relationship of the Liability Act with the Convention on Supplementary Compensation for Nuclear Damage (CSC) (Part C), while also touching upon the current status of an Indian nuclear insurance pool (Part D) and discussing some recent domestic developments, including the filing of public interest litigations and amendments to the Liability Rules (Part E), before presenting some concluding thoughts (Part F)

  16. Analisis Statistika dengan SPSS

    OpenAIRE

    Mustari, Kahar

    2012-01-01

    Buku ini membahas tentang berbagai model analisis statistika yang dapat digunakan dalam berbagai bidang penelitian. Pembahasan buku ini dilengkapi pula dengan penerapan analisis statistika yang menggunakan program SPSS versi 20 sehingga memudahkan pembaca untuk menerapkannya. Oleh karena itu, buku ini penting dibaca oleh mahasiswa atau peneliti yang melakukan pengolahan data penelitian.

  17. Concrete alkali-silica reaction and nuclear radiation damage

    International Nuclear Information System (INIS)

    Ichikawa, Tsuneki

    2008-01-01

    The deterioration of concrete by alkali-silica reaction of aggregates (ASR) and the effect of nuclear radiations on the ASR have been reviewed based on our studies on the mechanism of ASR and the effect of nuclear radiations on the resistivity of minerals to alkaline solution. It has been found that the ASR is initiated by the attack of alkaline solution in concrete to silicious aggregates to convert them into hydrated alkali silicate. The consumption of alkali hydroxide by the aggregates induces the dissolution of Ca 2+ ions into the solution. The alkali silicate surrounding the aggregates then reacts with Ca 2+ ions to convert to insoluble tight and rigid reaction rims. The reaction rim allows the penetration of alkaline solution but prevents the leakage of viscous alkali silicate, so that alkali silicate generated afterward is accumulated in the aggregate to give an expansive pressure enough for cracking the aggregate and the surrounding concrete. The effect of nuclear radiation on the reactivity of quartz and plagioclase, a part of major minerals composing volcanic rocks as popular aggregates, to alkaline solution has been examined for clarifying whether nuclear radiations accelerates the ASR. It has been found that the irradiation of these minerals converts them into alkali-reactive amorphous ones. The radiation dose for plagioclase is as low as 10 8 Gy, which suggests that the ASR of concrete surrounding nuclear reactors is possible to be accelerated by nuclear radiation. (author)

  18. Nuclear Reaction Data and Uncertainties for Radiation Damage. Summary Report of the Technical Meeting

    International Nuclear Information System (INIS)

    Griffin, P.J.; Sjöstrand, H.; Simakov, S.P.

    2016-08-01

    This Meeting was organized to implement the recommendation of the second Research Coordinated Meeting (RCM) of the International Atomic Energy Agency (IAEA) Coordinated Research Project (CRP) “Primary Radiation Damage Cross Sections” to analyse the accuracy and consistency of the radiation damage-relevant nuclear data in the major nuclear data evaluations with the eventual goal of identifying the most reliable data and providing quantitative uncertainty estimates. Participants have considered the status of the primary nuclear data, such as reaction recoils spectra in the latest releases of ENDF, JEFF, JENDL, FENDL, ROSFOND and TENDL nuclear data libraries, and the ways of deriving the damage quantities KERMA, NRT- or arc-dpa and gas production cross sections as well as the recipes for an assessment of their uncertainties. This report contains the contemporary view of the Meeting participants on these issues in the form of a consolidated set of statements, recommendations and individual summaries. (author)

  19. Tornado damage at the Grand Gulf, Mississippi nuclear power plant site: aerial and ground surveys

    International Nuclear Information System (INIS)

    Fujita, T.T.; McDonald, J.R.

    1978-05-01

    A tornado struck the Grand Gulf nuclear power generating station, Port Gibson, Mississippi, about 11:30 p.m. on April 17, 1978. Storm damage investigators from the University of Chicago and Texas Tech University were dispatched to survey the damage. The meteorological situation that spawned the Grand Gulf tornado and seven others in the area is discussed. Aerial surveys of the entire damage path and detailed surveys of the plant site are presented. An engineering evaluation of the damage is also presented based primarily on information gained from detailed ground surveys

  20. The Indian civil liability for nuclear damage act, 2010. Legislation with flaws?

    International Nuclear Information System (INIS)

    Pelzer, Norbert

    2011-01-01

    1. India has had no special legislation so far about liability under civil law for nuclear damage. Instead, the general law about damages outside of contractual provisions applied. 2. The ambitious Indian civil nuclear program requires intensified international cooperation. The potential partners in that cooperation demand that liability regulations be adopted on the basis of the principles of the international nuclear liability conventions so as to grant legal assurance to their export industries. 3. In May 2010, draft liability legislation was introduced into the Indian parliament. Final deliberations were held on August 30, 2010. On September 21, 2010, the President confirmed the draft legislation, thereby making it law. The draft legislation had been a matter of dispute in India from the outset. 4. The law applies to nuclear facilities owned or controlled by the Indian central government. Only the government or government institutions or state-owned companies can be owners of a nuclear facility. The owner is liable without fault having to be proven. The details of liability follow the provisions of the liability conventions. 5. The law provides for legal channelling of liability to the owner of a nuclear facility. 6. Regular courts of law have no competence to rule about claims for damages under the law. Instead, a 'Claims Commissioner' appointed ad hoc by the government, or a 'Nuclear Claims Commission,' are competent. 7. The 2010 Indian nuclear liability law is a piece of legislation with deficiencies. Key elements are incompatible with the principles of international nuclear liability regimes. (orig.)

  1. The order for enforcing the law on indemnity agreement for compensation of nuclear damage

    International Nuclear Information System (INIS)

    1977-01-01

    The states to be specified by the cabinet order stipulated in Item 2, Article 3 to the Law on Indemmity Agreement for Compensation of Nuclear Damage (hereinafter referred to as the Law) are the states meeting the following requirements. There are no violation of the stipulations according to the specified articles of the Law for the Regulation of Nuclear Source Materials, Nuclear Fuel Materials and Reactors, no damage of the facilities provided for the operation of reactors and others, and no natural calamity or no action of third parties which become the causes for the occurrence of nuclear damage. The nuclear damage to be specified according to the cabinet order stipulated in No. 5, Article 3 of the Law is the one caused by tidal waves. The indemnification rate stipulated in Article 6 of the Law to be decided by the cabinet order is 5/10000 (and 2.5/10000 regarding the indemnification contract with universities or colleges). Atomic energy entrepreneurs should notify the specified items to the Government with reference to the indemnification contracts concerning the operation of reactors, fabrication, reprocessing, use and transportation of nuclear fuel materials or matters contaminated by nuclear fuel materials

  2. Deliberations on Compensation and Remediation of Nuclear Damage to the Environment

    International Nuclear Information System (INIS)

    Pelzer, N.

    2010-01-01

    At its meeting held on 17 and 18 November 2009, the OECD NEA's Nuclear Law Committee (NLC) discussed the issue of obtaining financial security to cover liability for environmental damage. The experts from the insurance industry observed that the liability for environmental damage under the '2004 Paris Convention on Third Party Liability in the Field of Nuclear Energy' (2004 Paris Convention)2 may differ from the liability established under the 'Directive 2004/35/EC of the European Parliament and of the Council of 21 April 2004 on environmental liability with regard to the prevention and remedying of environmental damage' (referred to as 'directive'). This discussion put into focus the question whether the term 'liability' of the operator under the 2004 Paris Convention and under the directive covers identical concepts of 'compensation'. It is true that the directive, according to its Article 4, excludes nuclear risks or environmental damage or the imminent threat of such damage originating from defined nuclear activities from its scope of application. However, it reserves the right to amend that exclusion by 2014 [Article 18(2) and (3)]. Irrespective of this legal situation, there exists an understandable interest of the insurance industry and of other stakeholders as well to get clarification on which type of obligation the operator has to meet under both instruments, or in other words: which liability and coverage consequences does damage to the environment entail for the operator?

  3. Risk analysis by flooding in the PSA of Asco Nuclear Power Plant. Analisis de riesgo por inundaciones en el APS de C. N. Asco

    Energy Technology Data Exchange (ETDEWEB)

    Faig, J.

    1993-06-01

    The scope of the Probabilistic Safety Analysis of the ASCO Nuclear Power Plant included the analysis and evaluation of the probability of situations with core damage because of flood originated by internal sources of the installation. A short description of the systematic and methodology used for the analysis and the results obtained are given. The impact of some improvements introduced on the core damage frequency within the PSA are described as well. Our methodology followed basically the guidelines of NUREG/CR-2815. Analysis procedure was developed according two major steps: Selective Analysis and Detailed Analysis.

  4. Possible genetic damage in the Czech nuclear powe plant werkers

    Czech Academy of Sciences Publication Activity Database

    Šrám, Radim; Rössner st., Pavel; Rubeš, J.; Beskid, Olena; Dušek, Zdík; Chvátalová, Irena; Schmuczerová, J.; Milcová, Alena; Solanský, I.; Bavorová, H.; Očadlíková, D.; Kopečná, O.; Musilová, P.

    2006-01-01

    Roč. 593, 1-2 (2006), s. 50-63 ISSN 0027-5107 R&D Projects: GA MŽP SL/5/160/05 Institutional research plan: CEZ:AV0Z50390512 Keywords : nuclear power plant * chromosomal aberrations * occupational risk Subject RIV: DN - Health Impact of the Environment Quality Impact factor: 4.111, year: 2006

  5. Risks and benefits of the interventions aimed at minimizing nuclear damage in the Chernobyl accident

    International Nuclear Information System (INIS)

    Rossiello, L.A.; Failla, L.

    1997-01-01

    The damages that the absorption of ionizing radiation (i.r.) can cause to humans may be classified as 1) nonstochastic (somatic or deterministic) or 2) stochastic (probabilistic) , which result, for example, from high doses of i.r. absorbed after a serious nuclear accident. Though the Chernobyl case involved both kinds of damage, this paper deals only with stochastic damage risk, and confine our considerations to individuals who were directly Affected and received high i.r. doses. The purpose of this paper is to provide elements on which to base future decisions on the evacuation and return of populations affected by serious nuclear accidents. Unlike the abundant literature on the subject, and as a necessary complement thereto within the bounds of a strict synthesis, to identify the most significant parameters applicable to single individuals rather than to the population at large, and referring solely to risks of stochastic damage

  6. Assessment of seismic damages in nuclear power plant buildings

    International Nuclear Information System (INIS)

    Corsanego, A.; DelGrosso, A.; Ferro, G.

    1987-01-01

    Performance of nuclear power plant sites, buildings and components is in today's practice continuously evaluated by means of monitoring systems composed by a variety of instruments, allowing records of the most significant behavioral parameters to be gathered by electronic data acquisition equipment. A great emphasis has been devoted in recent years to the development of ''intelligent'' monitoring systems able to perform interpretation of the response of structures and components automatically, only requiring human intervention and sophisticated data processing techniques when degradation of the safety margins is likely to have been produced. Such computerized procedures can be formulated through logic or algorithmic processes and normally are consistently based upon simplified, heuristic behavioral models and probabilistic reasoning schemes. This paper is devoted to discuss the development of an algorithmic procedure intended for automatic, real-time interpretation of the recorded response of nuclear power plant buildings and foundations during seismic events

  7. International conventions on civil liability for nuclear damage. Revised 1976 ed.

    International Nuclear Information System (INIS)

    1976-01-01

    This revised edition contains the texts of the following multilateral conventions and instruments concerning civil liability for nuclear damage: The Vienna Convention of 21 May 1963 on Civil Liability for Nuclear Damage; The Paris Convention of 29 July 1960 on Third Party Liability in the Field of Nuclear Energy (incorporating the provisions of the Additional Protocol of 28 January 1964); The Brussels Convention of 31 January 1963; Supplementary to the Paris Convention of 29 July 1960 (and incorporating the provisions of the Additional Protocol signed in Paris on 28 January 1964); and the Brussels Convention of 25 May 1962 on the Liability of Operators of Nuclear Ships. Final Act and Resolutions of the International Conference on Civil Liability for Nuclear Damage, held in Vienna from 29 April to 19 May 1963; Final Act of the International Legal Conference on Maritime Carriage of Nuclear Substances, held in Brussels from 29 November to 2 December 1971; and Convention Relating to Civil Liability in the Field of Maritime Carriage of Nuclear Material, adopted at Brussels on 17 December 1971

  8. Liability for nuclear damage: an international perspective. Reflections on the revision of the Vienna Convention

    International Nuclear Information System (INIS)

    Lopuski, J.

    1993-01-01

    This book deals with deals of the complex issues of liability and compensation for nuclear damage which have been considered in the course of the work of the IAEA concerning the revision of the Vienna Convention on nuclear liability. It presents, in an orderly way, personal reflections of its author based on his experience gathered in years 1989-1992 when participating in this work. Necessarily it contains in some of its parts references to documents of the IAEA Standing Committee on Nuclear Liability; these documents because of their length could not be reproduced. Consequently these parts may not be fully intelligible for those who have not participated in or closely followed the Committee's work. The IAEA work on liability for nuclear damage was initiated in the wake of the impact made on the world's public opinion by the Chernobyl incident and its transboundary effects; issues of international state liability and full compensation have been raised. But humanitarian ideas have quickly been confronted with cold calculations of the cost of financial protection for victims and an open unwillingness of some nuclear states has been manifested. After three years of discussions no wide consensus could be reached on some basic issues, such as: relationship between international state and civil liability regimes, structure of international legislation, concept of nuclear damage, limits of compensation, role of public funds or jurisdiction. The author presents his approach to these controversial issue, trying to provide at the same time a theoretical outline for the future international legislation on nuclear liability. (author)

  9. Management of severely damaged nuclear fuel and related waste

    International Nuclear Information System (INIS)

    1991-01-01

    This report is concerned primarily with severe fuel damage accidents in large electric power producing reactors such as those in the TMI and Chernobyl plants. It does include, as appropriate, knowledge gained from accidents in other power, research and military reactors. It is believed that the conclusions and recommendations apply to a large extent to severe fuel damage accidents in all types of reactors. The period considered in this publication begins after the initial crisis of an accident has been brought under control. (This initial crisis could be from one day to several weeks after the event, depending on the specific conditions). Accordingly, it is assumed that the plant is shut down, the reactor is under control and decay heat removal is in progress in a stable manner so that attention must be given to cleanup. This report addresses the principles involved in planning, engineering, construction, operation and other activities to characterize, clean up and dispose of the fuel and related waste. The end of the period under consideration is when the fuel and abnormal wastes are packaged either for interim storage or final disposal and activities are started either to restore the plant to service or to establish a safe state from which decommissioning planning can start. 36 refs, 3 figs, 4 tabs.

  10. Data analysis on reducing damage on equipment's available in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Hasif Mohamad; Saipo Bahari Abdul Ratan; Ahmad Firdaus Che Hassan; Mazlipah Mohamed Ramlan; Mohd Hazri Mohd Salleh; Ghazali Bachok

    2010-01-01

    Technical Support Division (BST) in the underlying unit of Instrumentation and Automation Center (PIA), has been entrusted to carry out repair work on the equipment's available at Nuclear Malaysia as well as help rehabilitate and provide advisory services to foreign companies in need of our services. These data taken to determine the cause of damage to seek a solution to reduce damage in future. Tools do get involved are autoclave, Water Distiller, Barometer, Vaccum Pump and Chiller and Freezer. (author)

  11. Draft Federal Act of the Russian Federation 'The Civil Liability for Nuclear Damage and its Financial Security'

    International Nuclear Information System (INIS)

    Lebedeva, Yulia

    2014-01-01

    The use of nuclear power by states in the modern world requires supplements to international law through the development of national legislation on civil liability for nuclear damage and compensation. The situation in the Russian Federation is no exception. Russian law on civil liability for nuclear damage has not fully evolved, and currently, there is no specific law covering liability for nuclear damage, nor is there a law regarding the financial and insurance mechanisms for compensation. Instead, the current laws establish a state system of benefits and compensation for damage to health and property of citizens. Since 1996, Russia has been actively working to develop a draft federal act to cover liability for nuclear damage. A bill was first introduced in the State Duma of the Federal Assembly of the Russian Federation on 16 July 1996, and was originally called 'The Compensation for Nuclear Damage and Nuclear Insurance'. In 1997, the official representative of the Government of the Russian Federation, Head of Russian Federal Inspectorate for Nuclear and Radiation Safety, Yuri Vishnevsky, was appointed to present this bill for discussion in the chambers of the Federal Assembly of the Russian Federation. In September 1998, the State Duma rejected the draft federal act and instead adopted in the first reading a different draft federal act: No. 96700118-2, 'The Civil Liability for Nuclear Damage and its Financial Security' ('the bill'). In this case, the State Duma Committee on Ecology was charged with incorporating the incoming amendments into a final bill and submitting it to the State Duma for a second reading. In 2005, Russia ratified the Vienna Convention on Civil Liability for Nuclear Damage. This ratification required significant amendments to 'The Civil Liability for Nuclear Damage and its Financial Security' bill. But, even though the Russian Federation had not yet ratified the Vienna Convention, the drafters were still careful to take into account the

  12. Ubiquitination of HTLV-I Tax in response to DNA damage regulates nuclear complex formation and nuclear export

    Directory of Open Access Journals (Sweden)

    Marriott Susan J

    2007-12-01

    Full Text Available Abstract Background The HTLV-I oncoprotein, Tax, is a pleiotropic protein whose activity is partially regulated by its ability to interact with, and perturb the functions of, numerous cellular proteins. Tax is predominantly a nuclear protein that localizes to nuclear foci known as Tax Speckled Structures (TSS. We recently reported that the localization of Tax and its interactions with cellular proteins are altered in response to various forms of genotoxic and cellular stress. The level of cytoplasmic Tax increases in response to stress and this relocalization depends upon the interaction of Tax with CRM1. Cellular pathways and signals that regulate the subcellular localization of Tax remain to be determined. However, post-translational modifications including sumoylation and ubiquitination are known to influence the subcellular localization of Tax and its interactions with cellular proteins. The sumoylated form of Tax exists predominantly in the nucleus while ubiquitinated Tax exists predominantly in the cytoplasm. Therefore, we hypothesized that post-translational modifications of Tax that occur in response to DNA damage regulate the localization of Tax and its interactions with cellular proteins. Results We found a significant increase in mono-ubiquitination of Tax in response to UV irradiation. Mutation of specific lysine residues (K280 and K284 within Tax inhibited DNA damage-induced ubiquitination. In contrast to wild-type Tax, which undergoes transient nucleocytoplasmic shuttling in response to DNA damage, the K280 and K284 mutants were retained in nuclear foci following UV irradiation and remained co-localized with the cellular TSS protein, sc35. Conclusion This study demonstrates that the localization of Tax, and its interactions with cellular proteins, are dynamic following DNA damage and depend on the post-translational modification status of Tax. Specifically, DNA damage induces the ubiquitination of Tax at K280 and K284

  13. Economic damage caused by a nuclear reactor accident

    International Nuclear Information System (INIS)

    Baan, P.J.A.

    1988-01-01

    The impacts of a nuclear reactor accident have been estimated for: the public water supply; the use of surface water for sprinkling in agriculture, for industry water supply, recreation, etc.; and fisheries. Contamination of water sources may affect the public water supply severely. In such a situation demand of water cannot always be met. Agriculture faces production losses, if demand for uncontaminated surface water cannot be met. The impacts on recreation can also be significant. The losses to other water users are less substantial. Fisheries may lose (export) markets, as people become reluctant to buy fish and fish products. 33 refs.; 3 figs.; 35 tabs

  14. Fatigue damage in nuclear power plants: cases study

    International Nuclear Information System (INIS)

    Goltrant, O.; Thebault, Y.

    2001-01-01

    Some fatigue cracks have been detected on nuclear power plants components. Generally they appears under local solicitations not correctly predicted. Two cases are presented in this paper to illustrate the problem: the pitting during mechanical fatigue where the stresses are induced by the pumps vibrations or by fluid flow; the mixing zones of RRA circuit (N4 bearing) where the stresses are induced by the flow of different temperature fluids. The examination allowed the identification of the cracking origin and the development of corrective solutions. (A.L.B.)

  15. Yugoslavia-Act on Liability for Nuclear Damage of 19 April 1978

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    This Act, which came into force eight days after its publication, is based to a great extent on the provisions of the 1963 Vienna Convention on Civil Liability for Nuclear Damage, ratified by Yugoslavia on 12 August 1977. Under the Act, a nuclear operator is held absolutely liable for any nuclear damage caused by a nuclear indicent occurring in his installation. This liability is limited to 450 million dinars (approximately 22 million US$). To cover his liability, an operator must take out insurance or other financial security, whose amount will be determinated by the competent authority according to the characteristics of the installation involved but in no event should it be below 150 million dinars. Within the meaning of the Act, the operator may be an organisation of associated labour which has obtained site approval, licences for test runs and entry into operation of the installation, or any person recognised as such by the State. (NEA) [fr

  16. Vibration analysis and vibration damage assessment in nuclear and process equipment

    International Nuclear Information System (INIS)

    Pettigrew, M.J.; Taylor, C.E.; Fisher, N.J.; Yetisir, M.; Smith, B.A.W.

    1997-01-01

    Component failures due to excessive flow-induced vibration are still affecting the performance and reliability of process and nuclear components. The purpose of this paper is to discuss flow-induced vibration analysis and vibration damage prediction. Vibration excitation mechanisms are described with particular emphasis on fluid elastic instability. The dynamic characteristics of process and power equipment are explained. The statistical nature of some parameters, in particular support conditions, is discussed. The prediction of fretting-wear damage is approached from several points-of-view. An energy approach to formulate fretting-wear damage is proposed. (author)

  17. Investigation of potential fire-related damage to safety-related equipment in nuclear power plants

    International Nuclear Information System (INIS)

    Wanless, J.

    1985-11-01

    Based on a review of vendor information, fire damage reports, equipment qualification and hydrogen burn test results, and material properties, thirty-three types of equipment found in nuclear power plants were ranked in terms of their potential sensitivity to fire environments. The ranking considered both the functional requirements and damage proneness of each component. A further review of the seven top-ranked components was performed, considering the relative prevalence and potential safety significance of each. From this, relays and hand switches dominate as first choices for fire damage testing with logic equipment, power supplies, transmitters, and motor control centers as future candidates

  18. Liability for damage resulting from acts of the nuclear and radiological terrorism

    International Nuclear Information System (INIS)

    Handrlica, J.

    2008-01-01

    Nuclear terrorism is defined as an attack on a nuclear installation serving peaceful uses (such as a nuclear power plant) or non-peaceful uses. Radiological terrorism, which may be more likely, is defined as an action which doesn't trigger a nuclear reaction but gives rise to the release of radioactivity. The aim of this paper is to analyze the existing legal framework covering such situations. The relevant provisions of the Vienna and Paris Conventions on civil liability for nuclear damage, which represent a legal framework for nuclear liability at the international level, are discussed. The focus is on the identification of the the liable subject, including definition of the scope and nature of its liability. (author)

  19. Entry into force of the Convention on Supplementary Compensation for Nuclear Damage: Opening the umbrella

    International Nuclear Information System (INIS)

    McRae, Ben

    2015-01-01

    There are 431 commercial nuclear power plants around the world. On 14 April 2015, 193 of these power plants were covered by a nuclear liability instrument (118 power plants by the Paris Convention and 75 by the Vienna Convention). With the entry into force of the Convention on Supplementary Compensation for Nuclear Damage (CSC)4 on 15 April 2015, the number of power plants covered by a nuclear liability instrument increased to 340. Thus, the entry into force of the CSC marked a major milestone towards the establishment of a global nuclear liability regime. This article discusses several events that have promoted progress towards a global nuclear liability regime and then addresses several questions that may arise as countries consider actions necessary to achieve such a regime. (author)

  20. The inadequate liability and compensation regime for damage caused by nuclear activities

    International Nuclear Information System (INIS)

    Dyke, Jon M. Van

    2010-09-01

    The specific obligation to provide restitution and compensation when nuclear activities cause injuries has been recognized repeatedly and is now certainly part of customary international law. But problems remain regarding how to measure damages, how to implement the duty to repair the injuries, and what specific obligations exist to protect neighboring states from transboundary pollution. Although some treaties exist governing liability for harm resulting from nuclear accidents, they are not adequate to protect victims and have not been widely ratified. The failure to require nuclear operators to prepare for damage that may result from accidents constitutes a subsidy to the nuclear industry and makes it difficult to compare the real costs of nuclear energy with the costs of other energy sources. This survey of settled norms and unresolved issues demonstrates that further work is needed to develop a comprehensive and authoritative regime to govern harm from nuclear activities. Although it is clear that both the operators of nuclear facilities and the states that have jurisdiction over them would be responsible to provide restitution and compensation for such harm under a strict liability regime, the types of injuries that must be compensated and the range of damages that must be covered remain subjects of controversy. Although the underlying customary international law principles (the no-harm principle and the polluter-pays principle) are clear, the actual treaties that have been drafted are inadequate and they have not been widely ratified. Victims of damage from nuclear activities would have difficulty finding a neutral tribunal in which to bring their claims and would face procedural obstacles including caps on liabilities and inappropriately short statutes of limitations as well as difficulties regarding proof of damages. The failure to develop a proper regime that would ensure full restitution and compensation for harm resulting from nuclear facilities

  1. The convention on supplementary compensation for nuclear damage (CSC). A cornerstone of a global nuclear liability regime?

    International Nuclear Information System (INIS)

    Pelzer, Norbert

    2015-01-01

    International discussions on compensation of nuclear damage seem to be governed by the magic word ''global nuclear liability regime''. It is said that only such regime promises to guarantee full and timely compensation at conditions acceptable and favourable for both the victims and the operator liable and at the same time promotes nuclear industry. Surely, nuclear incidents may have worldwide implications, and a globally unified legal framework appears to be desirable or is even necessitated. But until today we have not yet achieved a global regime. There are international nuclear liability conventions some of which may be qualified to form such regime. But which of them is best qualified and which one could be accepted by all States? Mainly the USA opt for, and strongly support, the 1997 ''Convention on Supplementary Compensation for Nuclear Damage'' (CSC) to be the only international instrument which is apt to form a global regime. This paper will deal with the question whether this assertion is convincing. It will also be asked whether we need a global regime.

  2. The convention on supplementary compensation for nuclear damage (CSC). A cornerstone of a global nuclear liability regime?

    Energy Technology Data Exchange (ETDEWEB)

    Pelzer, Norbert

    2015-06-15

    International discussions on compensation of nuclear damage seem to be governed by the magic word ''global nuclear liability regime''. It is said that only such regime promises to guarantee full and timely compensation at conditions acceptable and favourable for both the victims and the operator liable and at the same time promotes nuclear industry. Surely, nuclear incidents may have worldwide implications, and a globally unified legal framework appears to be desirable or is even necessitated. But until today we have not yet achieved a global regime. There are international nuclear liability conventions some of which may be qualified to form such regime. But which of them is best qualified and which one could be accepted by all States? Mainly the USA opt for, and strongly support, the 1997 ''Convention on Supplementary Compensation for Nuclear Damage'' (CSC) to be the only international instrument which is apt to form a global regime. This paper will deal with the question whether this assertion is convincing. It will also be asked whether we need a global regime.

  3. Nuclear data for analysis of radiation damage processes

    International Nuclear Information System (INIS)

    Aruga, Takeo

    1999-01-01

    Parameters needed to analyze radiation damages for neutron irradiations are presented, taking iron samples irradiated with JMTR neutrons for an example. Special interests have been put on a comparison between results obtained by irradiations for one case with a full neutron spectrum and the other with a Cd-shielded neutron spectrum. A possibility is described that although atomic displacement rates for the two case differ only less than 2%, production rates of freely migrating defects can differ appreciably, due to recoiled atoms by (n, γ) reactions. More over, it is also suggested that although the median energy of PKA, defined as a PKA energy above (or below) which one half of the total atomic displacements are to be produced, may differ only slightly between the two cases, final radiation effects can be significantly different. The effects of charged particles emitted with high energies due to nucleon irradiations are stressed in relation to the significance of defects produced by PKAs with lower energies than several keV, especially for the case of irradiations with highly energetic nucleons as anticipated in GeV proton irradiations. (author)

  4. Nuclear data for analysis of radiation damage processes

    Energy Technology Data Exchange (ETDEWEB)

    Aruga, Takeo [Department of Materials Science Research, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan)

    1999-03-01

    Parameters needed to analyze radiation damages for neutron irradiations are presented, taking iron samples irradiated with JMTR neutrons for an example. Special interests have been put on a comparison between results obtained by irradiations for one case with a full neutron spectrum and the other with a Cd-shielded neutron spectrum. A possibility is described that although atomic displacement rates for the two case differ only less than 2%, production rates of freely migrating defects can differ appreciably, due to recoiled atoms by (n, {gamma}) reactions. More over, it is also suggested that although the median energy of PKA, defined as a PKA energy above (or below) which one half of the total atomic displacements are to be produced, may differ only slightly between the two cases, final radiation effects can be significantly different. The effects of charged particles emitted with high energies due to nucleon irradiations are stressed in relation to the significance of defects produced by PKAs with lower energies than several keV, especially for the case of irradiations with highly energetic nucleons as anticipated in GeV proton irradiations. (author)

  5. Aspects of the Brazilian law on civil liability for nuclear damage

    International Nuclear Information System (INIS)

    Rocha, L.M.G. da

    1980-06-01

    The civil liability for nuclear damage in the Brazilian law is analysed. The innovations introduced by the 6.453 act of October 17 th, 1977 are emphasized. The influence of international conventions on the Brazilian law are also mentioned. (A.L.) [pt

  6. Compensation for nuclear damage: a comparison among the international regime, Japan and China

    NARCIS (Netherlands)

    Liu, J.; Faure, Michael

    2016-01-01

    Following the Fukushima disaster in Japan in 2011, how the compensation system for nuclear damage should be improved has obtained broad attention. The compensation system, including liability rules, insurance and government involvement, does not only concern to what extent the victims can be

  7. Protocol to amend the Vienna convention on civil liability for nuclear damage

    International Nuclear Information System (INIS)

    1998-01-01

    The document reproduces the text of the Protocol to Amend the Vienna Convention on Civil Liability for Nuclear Damage which was adopted by a Diplomatic Conference, 8-12 September 1997, and the consolidated text of the 1963 Vienna Convention as amended by the Protocol

  8. Protocol to amend the Vienna convention on civil liability for nuclear damage

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-22

    The document reproduces the text of the Protocol to Amend the Vienna Convention on Civil Liability for Nuclear Damage which was adopted by a Diplomatic Conference, 8-12 September 1997, and the consolidated text of the 1963 Vienna Convention as amended by the Protocol

  9. Development of seismic damage assessment system for nuclear power plant structures in Korea

    International Nuclear Information System (INIS)

    Hyun, Chang-Hun; Lee, Sung-Kyu; Choi, Kang-Ryoung; Koh, Hyun-Moo; Cho, HoHyun

    2003-01-01

    A seismic damage assessment system that analyses in real-time the actual seismic resistance capacity and the damage level of power plant structures has been developed. The system consists of three parts: a 3-D inelastic seismic analysis, a damage assessment using a damage index based on the previous 3-D analysis, and a 3-D graphic representation. PSC containment structures are modelled by finite shell elements using layered method and analysis is performed by means of time history inelastic seismic analysis method, which takes into account material nonlinearities. HHT-α, one kind of direct integration method, is adopted for the seismic analysis. Two damage indices at finite element and structural levels are applied for the seismic damage assessment. 3-D graphical representation of dynamic responses and damage index expedites procedure for evaluating the damage level. The developed system is now being installed at the Earthquake Monitoring Center of KINS (Korea Institute of Nuclear Safety) to support site inspections after an earthquake occurrence, and decisions about effective emergency measures, repair and operations of the plant. (author)

  10. Quantitative analysis of water heavy by NMR spectroscopy; aplicacion de la resonancia magnetica nuclear al analisis cuantitativo de agua pesada

    Energy Technology Data Exchange (ETDEWEB)

    Gomez Gil, V

    1975-07-01

    Nuclear Magnetic Resonance has been applied to a wide variety of quantitative problems. A typical example has been the determination of isotopic composition. In this paper two different analytical methods for the determination of water in deuterium oxide are described. The first one, employs acetonitril as an internal standard compound and in the second one calibration curve of signal integral curve versus amount of D{sub 2}O is constructed. Both methods give results comparable to those of mass spectrometry of IR spectroscopy. (Author) 5 refs.

  11. Organizing irresponsibility? The (inter)national management of a nuclear accident damages as discursive regime

    International Nuclear Information System (INIS)

    Topcu, Sezin

    2014-01-01

    This article analyzes the historical process related to the international organization of responsibilities and the management of the damages in case of a nuclear disaster. The author shows that the political and legal settings on which the discourse of an 'international regime of civil responsibility' (that emerged in the 1960's) relies, have globally aimed at maintaining a 'historical and spectacular gap' between the damages the nuclear operators are taking responsibility for, and the real and extensive damages engendered by a major accident. She argues that the existence of such a 'gap' is inherent to the nuclear sector, that it is a form of government (both of economic affairs and of the public space) which was historically constructed, and that the existence of such a gap is crucial for the survival of the nuclear industry itself. Thus the notion of 'responsibility' in the nuclear sector appears to serve mainly as a discursive regime, as a means to organize not only responsibilities but also irresponsibilities, whatever the geographic scale (national or international) at which they should be managed

  12. Efficient prevention and compensation of catastrophic risks. The example of damage by nuclear accidents

    International Nuclear Information System (INIS)

    Vanden Borre, T.

    2001-01-01

    This book deals with the liability for damage due to catastrophic risks. The nuclear liability law serves as an example of such a catastrophic risk. The question that we tried to answer is what an efficient compensation scheme for catastrophic risks should look like. This question is dealt with both from a law and an economic point of view and from a comparative point of view. The main element in comparing the laws in different countries is the comparison between Belgian and Dutch civil (nuclear) liability law. But also American nuclear liability law is part of the analysis (the Price-Anderson Act). The book consists of four parts: (nuclear) civil liability law, legal and economic approach, analysis of other compensation systems and conclusions. The big themes in this book are therefore civil (nuclear) liability law, insurance law and environmental liability law [nl

  13. Mitochondrial and Nuclear DNA Damage and Repair in Age-Related Macular Degeneration

    Directory of Open Access Journals (Sweden)

    Janusz Blasiak

    2013-01-01

    Full Text Available Aging and oxidative stress seem to be the most important factors in the pathogenesis of age-related macular degeneration (AMD, a condition affecting many elderly people in the developed world. However, aging is associated with the accumulation of oxidative damage in many biomolecules, including DNA. Furthermore, mitochondria may be especially important in this process because the reactive oxygen species produced in their electron transport chain can damage cellular components. Therefore, the cellular response to DNA damage, expressed mainly through DNA repair, may play an important role in AMD etiology. In several studies the increase in mitochondrial DNA (mtDNA damage and mutations, and the decrease in the efficacy of DNA repair have been correlated with the occurrence and the stage of AMD. It has also been shown that mitochondrial DNA accumulates more DNA lesions than nuclear DNA in AMD. However, the DNA damage response in mitochondria is executed by nucleus-encoded proteins, and thus mutagenesis in nuclear DNA (nDNA may affect the ability to respond to mutagenesis in its mitochondrial counterpart. We reported that lymphocytes from AMD patients displayed a higher amount of total endogenous basal and oxidative DNA damage, exhibited a higher sensitivity to hydrogen peroxide and UV radiation, and repaired the lesions induced by these factors less effectively than did cells from control individuals. We postulate that poor efficacy of DNA repair (i.e., is impaired above average for a particular age when combined with the enhanced sensitivity of retinal pigment epithelium cells to environmental stress factors, contributes to the pathogenesis of AMD. Collectively, these data suggest that the cellular response to both mitochondrial and nuclear DNA damage may play an important role in AMD pathogenesis.

  14. The protection against nuclear risks under the international nuclear liability law: the geographical and technical scope of the international conventions on third party liability for nuclear damage

    International Nuclear Information System (INIS)

    Kissich, S.J.

    2001-10-01

    This Ph.D.-research deals with the International Conventions on Third Party Liability for Nuclear Damage. In 1960, the Paris Convention was established with the aim of providing a special uniform nuclear third party liability regime for Western Europe. This Convention was supplemented in 1963 by the Brussels Supplementary Convention. Also in 1963, the Vienna Convention, which aimed to establish a world-wide system based on the same principles as the Paris Convention, was adopted. A further Convention was adopted in 1971 to ensure that nuclear third party liability law and not maritime law would apply to carriage of nuclear materials by sea. In 1988, the Paris and Vienna Conventions have been linked by the adoption of a Joint Protocol. In 1997, the process of amending the 1963 Vienna Convention was successfully concluded and a Convention on Supplementary Compensation was adopted. This Ph.D.-research consists of seven chapters: following an introduction, the second chapter gives a general view of the existing international legal sources. The third chapter describes the international civil nuclear liability law concept and its leading principles. The main element of this work is the question of the technical and geographical scope of the international nuclear liability conventions (chapter IV and V). The conventions are only applicable to nuclear incidents, which occur in a nuclear installation or incidental to the carriage or storage of nuclear material. The nuclear damage must arise out of the radioactive properties of nuclear substances which are also defined by legal terms. In addition, the scope of the conventions is limited by the nature of the installations. The geographical scope of application is established by the provisions on geographical coverage. Only the 1963 Vienna Convention does not contain any specific provision dealing with the territorial scope of its application. The geographical scope determines where the nuclear incident or the nuclear damage

  15. Issues and decisions for nuclear power plant management after fuel damage events

    International Nuclear Information System (INIS)

    1997-04-01

    Experience has shown that the on-site activities following an incident that results in severely damaged fuel at a nuclear power plant required extraordinary effort. Even in cases that are not extreme but in which fuel damage is greater than mentioned in the specifications for operation, the recovery will require extensive work. This publication includes information from several projects at the IAEA since 1989 that have resulted in a Technical Report, a TECDOC and a Workshop. While the initial purpose of the projects was focused on providing technical information transfer to the experts engaged in recovery work at the damaged unit of Chernobyl NPP, the results have led to a general approach to managing events in which there is substantial fuel damage. This TECDOC summarizes the work to focus on management issues that may be encountered in any such event whether small or large. 11 refs, 2 figs, 5 tabs

  16. Analysis of the evolution of the collective dose in nuclear power plants in Spain; Analisis de la evolucion de la dosis colectiva en las centrales nucleares de Espana

    Energy Technology Data Exchange (ETDEWEB)

    Ponjuan Reyes, G.; Ruibia Rodiz, M. A. de la; Rosales Calvo, M.; Labarta Mancho, T.; Calavia Gimenez, I.

    2011-07-01

    This article presents an analysis of the evolution of occupational collective dose of the Spanish nuclear power plants during the period 2000 - 2008 within the international context, by the Nuclear Safety Council (CSN) in order to have information contrasted to assessing the extent of application of the ALARA criteria in the Spanish plants and identify areas of priority attention.

  17. Nuclear magnetic resonance-based metabolomics for prediction of gastric damage induced by indomethacin in rats

    International Nuclear Information System (INIS)

    Um, So Young; Park, Jung Hyun; Chung, Myeon Woo; Kim, Kyu-Bong; Kim, Seon Hwa; Choi, Ki Hwan; Lee, Hwa Jeong

    2012-01-01

    Highlights: ► NMR based metabolomics – gastric damage by indomethacin. ► Pattern recognition analysis was performed to biomarkers of gastric damage. ► 2-Oxoglutarate, acetate, taurine and hippurate were selected as putative biomarkers. ► The gastric damage induced by NSAIDs can be screened in the preclinical step of drug. - Abstract: Non-steroidal anti-inflammatory drugs (NSAIDs) have side effects including gastric erosions, ulceration and bleeding. In this study, pattern recognition analysis of the 1 H-nuclear magnetic resonance (NMR) spectra of urine was performed to develop surrogate biomarkers related to the gastrointestinal (GI) damage induced by indomethacin in rats. Urine was collected for 5 h after oral administration of indomethacin (25 mg kg −1 ) or co-administration with cimetidine (100 mg kg −1 ), which protects against GI damage. The 1 H-NMR urine spectra were divided into spectral bins (0.04 ppm) for global profiling, and 36 endogenous metabolites were assigned for targeted profiling. The level of gastric damage in each animal was also determined. Indomethacin caused severe gastric damage; however, indomethacin administered with cimetidine did not. Simultaneously, the patterns of changes in their endogenous metabolites were different. Multivariate data analyses were carried out to recognize the spectral pattern of endogenous metabolites related to indomethacin using partial least square-discrimination analysis. In targeted profiling, a few endogenous metabolites, 2-oxoglutarate, acetate, taurine and hippurate, were selected as putative biomarkers for the gastric damage induced by indomethacin. These metabolites changed depending on the degree of GI damage, although the same dose of indomethacin (10 mg kg −1 ) was administered to rats. The results of global and targeted profiling suggest that the gastric damage induced by NSAIDs can be screened in the preclinical stage of drug development using a NMR based metabolomics approach.

  18. Nuclear magnetic resonance-based metabolomics for prediction of gastric damage induced by indomethacin in rats

    Energy Technology Data Exchange (ETDEWEB)

    Um, So Young [Department of Pharmacology, National Institute of Toxicological Research, Korea Food and Drug Administration, 643 Yeonje-ri, Gangoe-myeon, Cheongwon-gun, Chungbuk (Korea, Republic of); Division of Life and Pharmaceutical Science and College of Pharmacy, Ewha Womans University, 52 Ewahyeodae-gil, Seodaemun-gu, Seoul (Korea, Republic of); Park, Jung Hyun [Division of Life and Pharmaceutical Science and College of Pharmacy, Ewha Womans University, 52 Ewahyeodae-gil, Seodaemun-gu, Seoul (Korea, Republic of); Chung, Myeon Woo [Department of Pharmacology, National Institute of Toxicological Research, Korea Food and Drug Administration, 643 Yeonje-ri, Gangoe-myeon, Cheongwon-gun, Chungbuk (Korea, Republic of); Kim, Kyu-Bong [College of Pharmacy, Dankook University, Dandae-ro, Cheonan, Chungnam (Korea, Republic of); Kim, Seon Hwa [Department of Pharmacology, National Institute of Toxicological Research, Korea Food and Drug Administration, 643 Yeonje-ri, Gangoe-myeon, Cheongwon-gun, Chungbuk (Korea, Republic of); Division of Life and Pharmaceutical Science and College of Pharmacy, Ewha Womans University, 52 Ewahyeodae-gil, Seodaemun-gu, Seoul (Korea, Republic of); College of Pharmacy, Dankook University, Dandae-ro, Cheonan, Chungnam (Korea, Republic of); Choi, Ki Hwan, E-mail: hyokwa11@korea.kr [Department of Pharmacology, National Institute of Toxicological Research, Korea Food and Drug Administration, 643 Yeonje-ri, Gangoe-myeon, Cheongwon-gun, Chungbuk (Korea, Republic of); Lee, Hwa Jeong, E-mail: hwalee@ewha.ac.kr [Division of Life and Pharmaceutical Science and College of Pharmacy, Ewha Womans University, 52 Ewahyeodae-gil, Seodaemun-gu, Seoul (Korea, Republic of)

    2012-04-13

    Highlights: Black-Right-Pointing-Pointer NMR based metabolomics - gastric damage by indomethacin. Black-Right-Pointing-Pointer Pattern recognition analysis was performed to biomarkers of gastric damage. Black-Right-Pointing-Pointer 2-Oxoglutarate, acetate, taurine and hippurate were selected as putative biomarkers. Black-Right-Pointing-Pointer The gastric damage induced by NSAIDs can be screened in the preclinical step of drug. - Abstract: Non-steroidal anti-inflammatory drugs (NSAIDs) have side effects including gastric erosions, ulceration and bleeding. In this study, pattern recognition analysis of the {sup 1}H-nuclear magnetic resonance (NMR) spectra of urine was performed to develop surrogate biomarkers related to the gastrointestinal (GI) damage induced by indomethacin in rats. Urine was collected for 5 h after oral administration of indomethacin (25 mg kg{sup -1}) or co-administration with cimetidine (100 mg kg{sup -1}), which protects against GI damage. The {sup 1}H-NMR urine spectra were divided into spectral bins (0.04 ppm) for global profiling, and 36 endogenous metabolites were assigned for targeted profiling. The level of gastric damage in each animal was also determined. Indomethacin caused severe gastric damage; however, indomethacin administered with cimetidine did not. Simultaneously, the patterns of changes in their endogenous metabolites were different. Multivariate data analyses were carried out to recognize the spectral pattern of endogenous metabolites related to indomethacin using partial least square-discrimination analysis. In targeted profiling, a few endogenous metabolites, 2-oxoglutarate, acetate, taurine and hippurate, were selected as putative biomarkers for the gastric damage induced by indomethacin. These metabolites changed depending on the degree of GI damage, although the same dose of indomethacin (10 mg kg{sup -1}) was administered to rats. The results of global and targeted profiling suggest that the gastric damage induced by

  19. Main features of the convention on supplementary compensation for nuclear damage - an over view

    International Nuclear Information System (INIS)

    Boulanenkov, V.

    2000-01-01

    The Chernobyl accident prompted widespread awareness of the need for improved protection of the public from the consequences of nuclear accidents. It was generally recognised that urgent efforts should be undertaken to strengthen the international nuclear liability regime based on two civil law conventions, namely the 1963 Vienna Convention on Civil Liability for Nuclear Damage and the 1960 Paris Convention on Third Party Liability in the Field of Nuclear Energy. The work initiated by the Agency - it was assigned to the Standing Committee established in 1990 - followed a two-track approach: to improve the existing civil liability regime, including revision of the Vienna Convention for which the IAEA is depositary; and, to develop a comprehensive international liability regime. The issue of compensation additional to that available under the two basic conventions received full attention in the negotiations. In the latter context, this work resulted in the adoption by a diplomatic conference convened by the IAEA in September 1997 of a new instrument, i.e. the Convention on Supplementary Compensation for Nuclear Damage (the CSC). The CSC is a product of many years of multilateral negotiations and represents a balance of various legal, economic and political considerations. While not all concerns may have been fully met, it represents a significant improvement in the protection of the public from the consequences of nuclear accidents. (author)

  20. Development for analysis system of rods enrichment of nuclear fuels; Desarrollo de un sistema de analisis de enriquecimiento de barras de combustible nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Rojas C, E.L

    1998-11-01

    Nuclear industry is strongly regulated all over the world and quality assurance is important in every nuclear installation or process related with it. Nuclear fuel manufacture is not the exception. ININ was committed to manufacture four nuclear fuel bundles for the CFE nucleo electric station at Laguna Verde, Veracruz, under General Electric specifications and fulfilling all the requirements of this industry. One of the quality control requisites in nuclear fuel manufacture deals with the enrichment of the pellets inside the fuel bundle rods. To achieve the quality demanded in this aspect, the system described in this work was developed. With this system, developed at ININ it is possible to detect enrichment spikes since 0.4 % in a column of pellets with a 95 % confidence interval and to identify enrichment differences greater than 0.2 % e between homogeneous segments, also with a 95 % confidence interval. ININ delivered the four nuclear fuel bundles to CFE and these were introduced in the core of the nuclear reactor of Unit 1 in the fifth cycle. Nowadays they are producing energy and have shown a correct mechanical performance and neutronic behavior. (Author)

  1. Analysis and application of a simulator of a nuclear reactor AP-600; Analisis y aplicacion de un simulador de un reactor nuclear AP-600

    Energy Technology Data Exchange (ETDEWEB)

    Medina S, V. S. [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico); Salazar S, E., E-mail: medina_victor@comunidad.unam.mx [UNAM, Facultad de Ingenieria, Division de Ingenieria Electrica, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, 62250 Jiutepec, Morelos (MX)

    2011-11-15

    In front of the resurgence of interest in the nuclear power production, several national organizations have considered convenient to have highly specialized human resources in the technologies of nuclear reactors of III + and IV generation. For this task, the intensive and extensive applications of the computation should been considered, as the virtual instrumentation. The present work analyzes the possible applications of a nuclear simulator provided by the IAEA with base in the design of the reactor AP-600, using a focusing of modular model developed in FORTRAN. One part of the work that was made with the simulator includes the evaluation of 21 transitory events of operation, including the recreation of the accident happened in the nuclear power plant of Three Mile Island in 1979, comparing the actions flow and the answer of the systems under the intrinsic security of a III + generation reactor. The impact that had the mentioned accident was analyzed in the growing of the nuclear energy sector and in the public image with regard to the nuclear power plants. An application for this simulator was proposed, its use as tool for the instruction in the nuclear engineering courses using it to observe the operation of the different security systems and its interrelation inside the power plant as well as a theoretical/practical approach for the student. (Author)

  2. Liability for nuclear damage: an international perspective. Reflections on the revision of the Vienna Convention

    Energy Technology Data Exchange (ETDEWEB)

    Lopuski, J

    1994-12-31

    This book deals with deals of the complex issues of liability and compensation for nuclear damage which have been considered in the course of the work of the IAEA concerning the revision of the Vienna Convention on nuclear liability. It presents, in an orderly way, personal reflections of its author based on his experience gathered in years 1989-1992 when participating in this work. Necessarily it contains in some of its parts references to documents of the IAEA Standing Committee on Nuclear Liability; these documents because of their length could not be reproduced. Consequently these parts may not be fully intelligible for those who have not participated in or closely followed the Committee`s work. The IAEA work on liability for nuclear damage was initiated in the wake of the impact made on the world`s public opinion by the Chernobyl incident and its transboundary effects; issues of international state liability and full compensation have been raised. But humanitarian ideas have quickly been confronted with cold calculations of the cost of financial protection for victims and an open unwillingness of some nuclear states has been manifested. After three years of discussions no wide consensus could be reached on some basic issues, such as: relationship between international state and civil liability regimes, structure of international legislation, concept of nuclear damage, limits of compensation, role of public funds or jurisdiction. The author presents his approach to these controversial issue, trying to provide at the same time a theoretical outline for the future international legislation on nuclear liability. (author).

  3. Liability for nuclear damage: an international perspective. Reflections on the revision of the Vienna Convention

    Energy Technology Data Exchange (ETDEWEB)

    Lopuski, J.

    1993-12-31

    This book deals with deals of the complex issues of liability and compensation for nuclear damage which have been considered in the course of the work of the IAEA concerning the revision of the Vienna Convention on nuclear liability. It presents, in an orderly way, personal reflections of its author based on his experience gathered in years 1989-1992 when participating in this work. Necessarily it contains in some of its parts references to documents of the IAEA Standing Committee on Nuclear Liability; these documents because of their length could not be reproduced. Consequently these parts may not be fully intelligible for those who have not participated in or closely followed the Committee`s work. The IAEA work on liability for nuclear damage was initiated in the wake of the impact made on the world`s public opinion by the Chernobyl incident and its transboundary effects; issues of international state liability and full compensation have been raised. But humanitarian ideas have quickly been confronted with cold calculations of the cost of financial protection for victims and an open unwillingness of some nuclear states has been manifested. After three years of discussions no wide consensus could be reached on some basic issues, such as: relationship between international state and civil liability regimes, structure of international legislation, concept of nuclear damage, limits of compensation, role of public funds or jurisdiction. The author presents his approach to these controversial issue, trying to provide at the same time a theoretical outline for the future international legislation on nuclear liability. (author).

  4. Development of a seismic damage assessment program for nuclear power plant structures

    Energy Technology Data Exchange (ETDEWEB)

    Koh, Hyun Moo; Cho, Yang Heui; Shin, Hyun Mok [Seoul National Univ., Seoul (Korea, Republic of)] (and others)

    2001-12-15

    The most part of the nuclear power plants operating currently in Korea are more than 20 years old and obviously we cannot pretend that their original performance is actually maintained. In addition, earthquake occurrences show an increasing trend all over the world, and Korea can no more be considered as a zone safe from earthquake. Therefore, need is to guarantee the safety of these power plant structures against seismic accident, to decide to maintain them operational and to obtain data relative to maintenance/repair. Such objectives can be reached by damage assessment using inelastic seismic analysis considering aging degradation. It appears to be more important particularly for the structure enclosing the nuclear reactor that must absolutely protect against any radioactive leakage. Actually, the tendency of the technical world, led by the OECD/NEA, BNL in the United States, CEA in France and IAEA, is to develop researches or programs to assess the seismic safety considering aging degradation of operating nuclear power plants. Regard to the above-mentioned international technical trend, a technology to establish inelastic seismic analysis considering aging degradation so as to assess damage level and seismic safety margin appears to be necessary. Damage assessment and prediction system to grasp in real-time the actual seismic resistance capacity and damage level by 3-dimensional graphic representations are also required.

  5. Development of a seismic damage assessment program for nuclear power plant structures

    Energy Technology Data Exchange (ETDEWEB)

    Koh, Hyun Moo; Cho, Ho Hyun; Cho, Yang Hui [Seoul National Univ., Seoul (Korea, Republic of)] (and others)

    2000-12-15

    Some of nuclear power plants operating currently in Korea have been passed about 20 years after construction. Moreover, in the case of KORI I the service year is over 20 years, so their abilities are different from initial abilities. Also, earthquake outbreak increase, our country is not safe area for earthquake. Therefore, need is to guarantee the safety of these power plant structures against seismic accident, to decide to maintain them operational and to obtain data relative to maintenance/repair. Such objectives can be reached by damage assessment using inelastic seismic analysis considering aging degradation. It appears to be more important particularly for the structure enclosing the nuclear reactor that must absolutely protect against any radioactive leakage. Actually, the tendency of the technical world, led by the OECD/NEA, BNL in the United States, CEA in France and IAEA, is to develop researches or programs to assess the seismic safety considering aging degradation of operating nuclear power plants. Regard to the above-mentioned international technical trend, a technology to establish inelastic seismic analysis considering aging degradation so as to assess damage level and seismic safety margin appears to be necessary. Damage assessment and prediction system to grasp in real-time the actual seismic resistance capacity and damage level by 3-dimensional graphic representations are also required.

  6. The order for enforcing the law on indemnity agreement for compensation of nuclear damage

    International Nuclear Information System (INIS)

    1980-01-01

    The cabinet ordinance is established under the provisions of the law concerning atomic energy damage indemnification contract. The damage indemnifications in this law cover the occasions when there is not the cause for atomic energy damages due to the violation of the specified provisions of the law concerning the regulation of nuclear raw materials, nuclear fuel materials and reactors, the failures of operation facilities for reactors and natural calamity or the deed of a third party. The rate of indemnification fees is stipulated at 5/10,000. An enterpriser of atomic energy business shall inform the following matters to the government concerning the indemnification contracts. The objects of operation of reactors; the types, thermal output and number of reactors; the names and addresses of works or places of business where reactors are set up; the locations, structures and equipments of reactor facilities; beginning dates and expected ending dates of the operation on reactors; the kinds and estimated quantities of use in a year of nuclear fuel materials employed for reactors; the methods of disposal of spent fuels and the matters concerning liability insurance contracts. The matters to be reported to the government are specified respectively for the indemnification contracts for the processing, reprocessing, use, transport and disposal of nuclear fuel materials. The payment of indemnification fees and indemnities, the cancellation of indemnification contracts and the fines for default are particularly defined. (Okada, K.)

  7. Changes in nuclear protein acetylation in u.v.-damaged human cells

    International Nuclear Information System (INIS)

    Ramanathan, B.; Smerdon, M.J.

    1986-01-01

    The levels of nuclear protein acetylation in u.v.-irradiated human fibroblasts have been investigated. Initially, we measured the levels of acetylation in total acid-soluble nuclear proteins and observed two distinct differences between the irradiated and unirradiated (control) cells. Immediately after irradiation, there is a 'wave' of protein hyperacetylation that lasts for 2-6 h, followed by a hypoacetylation phase, lasting for many hours, and the total level of acetylation does not return to that of control cells until 24-72 h after u.v. damage. Both the magnitude and duration of each phase is dependent on the dose of u.v. light used. The wave of hyperacetylation is more pronounced at low u.v. doses, while the wave of hypoacetylation is more pronounced at higher u.v. doses. Furthermore, the duration of each phase is prolonged when cells are exposed to 2 mM hydroxyurea, an agent which retards the rate of excision repair at u.v.-damaged sites. Examinations of the acetylation levels of the individual nuclear proteins indicated that acetylation of the core histones follows the same pattern observed for the total acid-soluble protein fractions. Furthermore, these were the only major proteins in the total acid-soluble fraction observed to undergo the early, rapid hyperacetylation immediately following u.v. damage. These results raise the possibility that a causal relationship exists between nuclear protein acetylation and nucleotide excision repair of DNA in human cells. (author)

  8. Nuclear accumulation and activation of p53 in embryonic stem cells after DNA damage

    Directory of Open Access Journals (Sweden)

    Rolletschek Alexandra

    2009-06-01

    Full Text Available Abstract Background P53 is a key tumor suppressor protein. In response to DNA damage, p53 accumulates to high levels in differentiated cells and activates target genes that initiate cell cycle arrest and apoptosis. Since stem cells provide the proliferative cell pool within organisms, an efficient DNA damage response is crucial. Results In proliferating embryonic stem cells, p53 is localized predominantly in the cytoplasm. DNA damage-induced nuclear accumulation of p53 in embryonic stem cells activates transcription of the target genes mdm2, p21, puma and noxa. We observed bi-phasic kinetics for nuclear accumulation of p53 after ionizing radiation. During the first wave of nuclear accumulation, p53 levels were increased and the p53 target genes mdm2, p21 and puma were transcribed. Transcription of noxa correlated with the second wave of nuclear accumulation. Transcriptional activation of p53 target genes resulted in an increased amount of proteins with the exception of p21. While p21 transcripts were efficiently translated in 3T3 cells, we failed to see an increase in p21 protein levels after IR in embryonal stem cells. Conclusion In embryonic stem cells where (anti-proliferative p53 activity is not necessary, or even unfavorable, p53 is retained in the cytoplasm and prevented from activating its target genes. However, if its activity is beneficial or required, p53 is allowed to accumulate in the nucleus and activates its target genes, even in embryonic stem cells.

  9. Nuclear accumulation and activation of p53 in embryonic stem cells after DNA damage.

    Science.gov (United States)

    Solozobova, Valeriya; Rolletschek, Alexandra; Blattner, Christine

    2009-06-17

    P53 is a key tumor suppressor protein. In response to DNA damage, p53 accumulates to high levels in differentiated cells and activates target genes that initiate cell cycle arrest and apoptosis. Since stem cells provide the proliferative cell pool within organisms, an efficient DNA damage response is crucial. In proliferating embryonic stem cells, p53 is localized predominantly in the cytoplasm. DNA damage-induced nuclear accumulation of p53 in embryonic stem cells activates transcription of the target genes mdm2, p21, puma and noxa. We observed bi-phasic kinetics for nuclear accumulation of p53 after ionizing radiation. During the first wave of nuclear accumulation, p53 levels were increased and the p53 target genes mdm2, p21 and puma were transcribed. Transcription of noxa correlated with the second wave of nuclear accumulation. Transcriptional activation of p53 target genes resulted in an increased amount of proteins with the exception of p21. While p21 transcripts were efficiently translated in 3T3 cells, we failed to see an increase in p21 protein levels after IR in embryonal stem cells. In embryonic stem cells where (anti-proliferative) p53 activity is not necessary, or even unfavorable, p53 is retained in the cytoplasm and prevented from activating its target genes. However, if its activity is beneficial or required, p53 is allowed to accumulate in the nucleus and activates its target genes, even in embryonic stem cells.

  10. Analysis of opinion about nuclear energy and sustainability in a graduate level population; Analisis de opinion sobre la energia nuclear y sustentabilidad en una poblacion de nivel superior

    Energy Technology Data Exchange (ETDEWEB)

    Meza L, C.D.; Arredondo S, C. [IPN, ESFM, 07738 Mexico D.F. (Mexico)]. e-mail: angie2esa@hotmail.com

    2007-07-01

    The Mexican society has a modest knowledge of the nuclear energy, even at the participant students of superior education level in this survey is finds a scarce compression with regard to their obtaining, use and manage. As a result of the lack of interest of the same society and at the problems that know each other like they are: the pollutants that it produces those nuclear waste and the possible use or warlike end, a fear is believed about this energy type. In the Superior School of Physics and Mathematics there is the possibility to make studies so much at master degree level in the one fear of the nuclear energy and the applications of the same one in peaceful uses. However, particularly the studies at master level seem to be immersed in a crisis that requires of different supports to be resolved. For all it previous was thought in carrying out a survey inside a student population with superior level to know the opinion and the knowledge on the nuclear energy in Mexico. In this work the results of the survey are analyzed with the purpose of to determine which is the knowledge of the community mentioned regarding the other energy types, the impact that they have these in the environment, the sustenance of the same ones and in particular on knowledge about the nuclear energy considering the aspects before mentioned. With base had said analysis settles down that the interviewed community knows very little about the nuclear energy but they show interest to study and to obtain bigger information about the same one, for what is very important to diffuse but and better information on the nuclear energy to the population's strata, because it is of supposing that the rest of the population has erroneous information on the nuclear energy. In particular for the community of the Superior School of Physics and Mathematics the diffusion of all the benefits of the peaceful applications of the nuclear energy, including the capacity to generate enormous quantities and

  11. Japan's compensation system for nuclear damage - As related to the TEPCO Fukushima Daiichi nuclear accidents

    International Nuclear Information System (INIS)

    Nomura, Toyohiro; Matsuura, Shigekazu; Takahashi, Yasufumi; Takenaka, Chihiro; Hokugo, Taro; Kamada, Toshihiko; Kamai, Hiroyuki

    2012-01-01

    Following the TEPCO Fukushima Daiichi nuclear power plant accident, extraordinary efforts were undertaken in Japan to implement a compensation scheme for the proper and efficient indemnification of the affected victims. This publication provides English translations of key Japanese legislative and administrative texts and other implementing guidance, as well as several commentaries by Japanese experts in the field of third party nuclear liability. The OECD Nuclear Energy Agency (NEA) has prepared this publication in co-operation with the government of Japan to share Japan's recent experience in implementing its nuclear liability and compensation regime. The material presented in the publication should provide valuable insights for those wishing to better understand the regime applied to compensate the victims of the accident and for those working on potential improvements in national regimes and the international framework for third party nuclear liability

  12. Nuclear Liability and Insurance of Nuclear Damage in the Czech republic

    International Nuclear Information System (INIS)

    Zaruba, P.

    1998-01-01

    The paper gives a short introduction to the past and present situation of operation and construction of nuclear power plants in the Czech Republic, including some basic technical data and background information. It then continues in providing up to date information on the Czech nuclear legislation and consideration of various questions and problems in the light of the respective legal clauses (e.g. minimum insurance requirements, treatment of small reactors and small quantities of nuclear material, state guarantees etc.). The paper gives more detailed information about practical application of the insurance clauses of the Atomic Act, including some time related questions. A considerable part of the paper is dedicated to the past history and present functions and activities of the Czech Nuclear Insurance Pool which was officially founded in 1995 and is without doubt one of the most active and successful national nuclear insurance pools of the former East European countries. (author)

  13. Psychological health damage as an environmental effect: Metropolitan Edison Co. v. People Against Nuclear Energy

    International Nuclear Information System (INIS)

    Hoff, E.H.

    1984-01-01

    The Supreme court took a narrow view of the term environmental in Metropolitan Edison Co. v. People Against Nuclear Energy when it stated that the purpose of the National Environmental Policy Act (NEPA) is to protect the physical environment. Psychological health damage caused by the perception of the risk of a nuclear accident is not an environmental effect cognizable under NEPA unless their is a demonstrable relationship. Litigants seeking the protection of NEPA must carefully examine the origin and nature of alleged psychological harms and frame their complains to establish a close relationship between a change in the physical environment and the alleged psychological harm

  14. Liability according to civil law regarding border-crossing nuclear damage

    International Nuclear Information System (INIS)

    Baer, Caroline

    1987-12-01

    The problem of the liability in border-crossing damage caused by a nuclear-reactor accident is divided into two different areas: the liability according to international law of the state, and liability according to civil right of the licensee of a nuclear power plant. In this study attention is paid to the question of the liability according to civil right: is it possible that an aggrieved obtains compensation for damage? This is investigated on the basis of three standard questions of international private law: which judge is qualified, which law is to be applied, and is acknowledgement and execution of foreign sentences possible? First a historical survey is given of international agreements and national legislations regarding third-party liability. (author). 112 refs

  15. Serpent: an alternative for the nuclear fuel cells analysis of a BWR; SERPENT: una alternativa para el analisis de celdas de combustible nuclear de un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Silva A, L.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. Instituto Politecnico Nacional s/n, U.P. Adolfo Lopez Mateos, Edificio 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Gomez T, A. M., E-mail: lidi.s.albarran@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    In the last ten years the diverse research groups in nuclear engineering of the Universidad Nacional Autonoma de Mexico and Instituto Politecnico Nacional (UNAM, IPN), as of research (Instituto Nacional de Investigaciones Nucleares, ININ) as well as the personnel of the Nuclear Plant Management of the Comision Federal de Electricidad have been using the codes Helios and /or CASMO-4 in the generation of cross sections (X S) of nuclear fuel cells of the cores corresponding to the Units 1 and 2 of the nuclear power plant of Laguna Verde. Both codes belong to the Studsvik-Scandpower Company who receives the payment for the use and their respective maintenance. In recent years, the code Serpent appears among the nuclear community distributed by the OECD/Nea which does not has cost neither in its use neither in its maintenance. The code is based on the Monte Carlo method and makes use of the processing in parallel. In the Escuela Superior de Fisica y Matematicas of the IPN, the personnel has accumulated certain experience in the use of Serpent under the direction of personal of the ININ; of this experience have been obtained for diverse fuel burned, the infinite multiplication factor for three cells of nuclear fuel, without control bar and with control bar for a known thermodynamic state fixed by: a) the fuel temperature (T{sub f}), b) the moderator temperature (T{sub m}) and c) the vacuums fraction (α). Although was not realized any comparison with the X S that the codes Helios and CASMO-4 generate, the results obtained for the infinite multiplication factor show the prospective tendencies with regard to the fuel burned so much in the case in that is not present the control bar like when it is. The results are encouraging and motivate to the study group to continue with the X S generation of a core in order to build the respective library of nuclear data as a following step and this can be used for the codes PARCS, of USA NRC, DYN3D of HZDR, or others developed locally

  16. Changes in nuclear protein acetylation in u. v. -damaged human cells

    Energy Technology Data Exchange (ETDEWEB)

    Ramanathan, B.; Smerdon, M.J.

    1986-07-01

    We have investigated the levels of nuclear protein acetylation in u.v.-irradiated human fibroblasts. We measured the levels of acetylation in total acid-soluble nuclear proteins and observed two distinct differences between the irradiated and unirradiated (control) cells. Immediately after irradiation, there is a wave of protein hyperacetylation (i.e. a total acetylation level greater than that of unirradiated cells) that lasts for 2-6 h depending on the experimental conditions. This hyperacetylation phase is then followed by a hypoacetylation phase, lasting for many hours, and the total level of acetylation does not return to that of control cells until 24-72 h after u.v. damage. Both the magnitude and duration of each phase is dependent on the dose of u.v. light used. The wave of hyperacetylation is more pronounced at low u.v. doses (i.e. less than 5 J/m2), while the wave of hypoacetylation is more pronounced at higher u.v. doses (greater than or equal to 8 J/m2). Furthermore, the duration of each phase is prolonged when cells are exposed to 2 mM hydroxyurea. Examination of the acetylation levels of the individual nuclear proteins indicated that acetylation of the core histones follows the same pattern observed for the total acid-soluble protein fractions. Furthermore, these were the only major proteins in the total acid-soluble fraction observed to undergo the early, rapid hyperacetylation immediately following u.v. damage. Acetylation of histone H1 was negligible in both damaged and control cells, while three prominent non-histone proteins were acetylated only after long labeling times (greater than 4 h) in each case, gradually becoming hyperacetylated in the u.v.-damaged cells. These results raise the possibility that a causal relationship exists between nuclear protein acetylation and nucleotide excision repair of DNA in human cells.

  17. Effect of radiation damage on operating safety of steel pressure vessels of nuclear reactors

    International Nuclear Information System (INIS)

    Vacek, M.; Havel, S.; Stoces, B.; Brumovsky, M.

    1980-01-01

    The effects are assessed of the environment upon mechanical properties of steel used generally for pressure vessels of light water nuclear reactors. Changes caused by radiation affect the reliability of vessels. Deterioration of steel properties is mainly due to neutron radiation. The article deals with factors bearing upon damage and with methods allowing to evaluate the reliability of vessels and predict their service life. Operating reliability of vessels is very unfavourably affected by planned and accidental reactor transients. (author)

  18. Specific defences to the liability of a nuclear operator for damages resulting from a nuclear incident

    International Nuclear Information System (INIS)

    Schwartz, J.A.; Cunningham, G.H.

    1988-01-01

    This paper reviews the cases in which the nuclear operator may be partly or totally exonerated from his liability for a nuclear accident (insurrection, civil war, exceptional natural disasters, intentional act of the victim, etc.) under the Paris and Vienna Conventions and national laws. The laws of the countries reviewed are the following: United States, Japan, Canada, United Kingdom, Brazil, Belgium, the Federal Republic of Germany, France (NEA) [fr

  19. An overview of the international regime governing liability for nuclear damage

    International Nuclear Information System (INIS)

    Sturms, W.; Reye, S.

    1995-01-01

    Since 1986, the IAEA has been seized with considerations of all aspects of international nuclear liability, with a view to establishing a comprehensive international regime that would obtain widest adherence. The practical work is currently being done in the IAEA Standing Committee on Liability for Nuclear Damage. The efforts, which were first concentrated on the improvement of the existing civil liability regime, resulted in adoption, in 1988, of the Joint Protocol to the Vienna Convention and the Paris Convention, combining them into one expanded regime. At present, the work is focused on the following questions: (a) Revision of the Vienna Convention: In this context, specific draft amendments are considered relating to some key issues where need for improvement has been recognized, such as geographical scope, application to military installations, expansion of the definition of damage to cover environmental damage, preventative measures and consequential losses, increase of liability limits, provision of funds by the Installation State, extension of time limits for submission of claims, restriction of exonerations, etc. (b) International State liability and its relationship with the civil liability regime: Emphasis is placed on proposals for Installation State involvement in the provision of public funds in addition to compensation paid by the operator. (c) Elaboration of a supplementary funding system to cover damage exceeding compensation available under the Vienna and Paris Conventions

  20. Evaluation of cytogenetic damage in nuclear medicine personnel occupationally exposed to low-level ionising radiation

    International Nuclear Information System (INIS)

    Garaj-Vrhovac, V.; Kopjar, N.; Poropat, M.

    2005-01-01

    Despite intensive research over the last few decades, there still remains considerable uncertainty as to the genetic impact of ionising radiation on human populations, particularly at low levels. The aim of this study was to provide data on genetic hazards associated with occupational exposure to low doses of ionising radiation in nuclear medicine departments. The assessment of DNA damage in peripheral blood lymphocytes of medical staff was performed using the chromosome aberration (CA) test. Exposed subjects showed significantly higher frequencies of CA than controls. There were significant inter-individual differences in DNA damage within the exposed population, indicating differences in genome sensitivity. Age and gender were not confounding factors, while smoking enhanced the levels of DNA damage only in control subjects. The present study suggests that chronic exposure to low doses of ionising radiation in nuclear medicine departments causes genotoxic damage. Therefore, to avoid potential genotoxic effects, the exposed medical personnel should minimise radiation exposure wherever possible. Our results also point to the significance of biological indicators providing information about the actual risk to the radiation exposed individuals.(author)

  1. Summary Report of the Technical Meeting on Primary Radiation Damage: From Nuclear Reaction to Point Defects

    International Nuclear Information System (INIS)

    Stoller, R. E.; Nordlund, K.; Simakov, S.P.

    2012-11-01

    The Meeting was convened to bring together the experts from both the nuclear data and materials research communities because of their common objective of accurately characterizing irradiation environments and resulting material damage. The meeting demonstrated that significant uncertainties remain regarding both the status of nuclear data and the use of these data by the materials modeling community to determine the primary damage state obtained in irradiated materials. At the conclusion of the meeting, the participants agreed that there is clear motivation to initiate a CRP that engages participants from the nuclear data and materials research communities. The overall objective of this CRP would be to determine the best possible parameter (or a few parameters) for correlating damage from irradiation facilities with very different particle types and energy spectra, including fission and fusion reactors, charged particle accelerators, and spallation irradiation facilities. Regarding progress achieved during the last decade in the atomistic simulation of primary defects in crystalline materials, one of the essential and quantitative outcomes from the CRP is expected to be cross sections for point defects left after recoil cascade quenching. (author)

  2. Transportation of failed or damaged foreign research reactor spent nuclear fuel

    International Nuclear Information System (INIS)

    Messick, C.E.; Mustin, T.P.; Massey, C.D.

    1998-01-01

    Since resuming the Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance Program in 1996, the Program has had to deal with difficult issues associated with the transportation of failed or damaged spent fuel. In several instances, problems with failed or damaged fuel have prevented the acceptance of the fuel at considerable cost to both the Department of Energy (DOE) and research reactor operators. In response to the problems faced by the Acceptance Program, DOE has undertaken significant steps to better define the spent fuel acceptance criteria. DOE has worked closely with the U.S. Nuclear Regulatory Commission to address failed or damaged research reactor spent fuel and to identify cask certificate issues which must be resolved by cask owners and foreign regulatory authorities. The specific issues associated with the transport of Materials Testing Reactor (MTR)-type FRR SNF will be discussed. The information presented will include U.S. Nuclear Regulatory Commission regulatory issues, cask certificate issues, technical constraints, and lessons learned. Specific information will also be provided on the latest efforts to revise DOE's Appendix B, Transport Package (Cask) Acceptance Criteria. The information presented in this paper will be important to foreign research reactor operators, shippers, and cask vendors, so that appropriate amendments to the Certificate of Compliance for spent fuel casks can be submitted in a timely manner to facilitate the safe and scheduled transport of FRR SNF

  3. Transportation of failed or damaged foreign research reactor spent nuclear fuel

    International Nuclear Information System (INIS)

    Messick, Charles E.; Mustin, Tracy P.; Massey, Charles D.

    1999-01-01

    Since initiating the Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Acceptance Program in 1996, the Program has had to deal with difficult issues associated with the transportation of failed or damaged spent fuel. In several instances, problems with failed or damaged fuel have prevented the acceptance of the fuel at considerable cost to both the Department of Energy and research reactor operators. In response to the problems faced by the Acceptance Program, DOE has undertaken significant steps to better define the spent fuel acceptance criteria. DOE has worked closely with the U.S. Nuclear Regulatory Commission to address failed or damaged research reactor spent fuel causing a degradation of the fuel assembly exposing fuel meat and to identify cask certificate issues which must be resolved by cask owners and foreign regulatory authorities. The specific issues and implementation challenges associated with the transport of MTR type FRR SNF will be discussed. The information presented will include U.S. Nuclear Regulatory Commission regulatory issues, cask certificate issues, technical constraints, implementation status, and lessons learned. Specific information will also be provided on the latest efforts to revise DOE's Appendix B, Transport Package (Cask) Acceptance Criteria. The information presented in this paper will be of interest to foreign research reactor operators, shippers, and cask vendors in evaluating the condition of their fuel to ensure it can be transported in accordance with appropriate cask certificate requirements. (author)

  4. AZTLAN platform: Mexican platform for analysis and design of nuclear reactors; AZTLAN platform: plataforma mexicana para el analisis y diseno de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Gomez T, A. M.; Puente E, F. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Edif. 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Francois L, J. L.; Martin del Campo M, C. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico); Espinosa P, G., E-mail: armando.gomez@inin.gob.mx [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco No. 186, Col. Vicentina, 09340 Mexico D. F. (Mexico)

    2014-10-15

    The Aztlan platform Project is a national initiative led by the Instituto Nacional de Investigaciones Nucleares (ININ) which brings together the main public houses of higher studies in Mexico, such as: Instituto Politecnico Nacional, Universidad Nacional Autonoma de Mexico and Universidad Autonoma Metropolitana in an effort to take a significant step toward the calculation autonomy and analysis that seeks to place Mexico in the medium term in a competitive international level on software issues for analysis of nuclear reactors. This project aims to modernize, improve and integrate the neutron, thermal-hydraulic and thermo-mechanical codes, developed in Mexican institutions, within an integrated platform, developed and maintained by Mexican experts to benefit from the same institutions. This project is financed by the mixed fund SENER-CONACYT of Energy Sustain ability, and aims to strengthen substantially to research institutions, such as educational institutions contributing to the formation of highly qualified human resources in the area of analysis and design of nuclear reactors. As innovative part the project includes the creation of a user group, made up of members of the project institutions as well as the Comision Nacional de Seguridad Nuclear y Salvaguardias, Central Nucleoelectrica de Laguna Verde (CNLV), Secretaria de Energia (Mexico) and Karlsruhe Institute of Technology (Germany) among others. This user group will be responsible for using the software and provide feedback to the development equipment in order that progress meets the needs of the regulator and industry; in this case the CNLV. Finally, in order to bridge the gap between similar developments globally, they will make use of the latest super computing technology to speed up calculation times. This work intends to present to national nuclear community the project, so a description of the proposed methodology is given, as well as the goals and objectives to be pursued for the development of the

  5. The OECD/NEA workshop on the indemnification of nuclear damage in the event of a nuclear accident

    International Nuclear Information System (INIS)

    Wagstaff, F.

    2002-01-01

    Since 1993, the OECD Nuclear Energy Agency (OECD/NEA) has run the International Nuclear Emergency Exercise (INEX) Program. The program serves to discuss an effective accident management approach on the basis of a simulated nuclear accident situation together with the states involved and their institutions, and also elaborate measures for its further improvement. At the present time, the INEX Program has reached Phase 3 in which, for the first time, also aspects of liability for the consequences of accidents were included. These aspects were made the subject of a workshop held after an emergency exercise. The scenario covered was based on an INES level-4 accident in the French Gravelines Nuclear Power Station situated close to the French-Belgian border. The workshop dealt with these topics, among others: the application of the Paris Convention on Third Party Liability, the Brussels Supplementary Convention, and the Vienna Convention on Civil Liability for Nuclear Damage as well as the Supplementary Compensation Convention of 1997. It was seen that there was a clear need for further discussion, especially to shed more light on the interrelationship of these treaties. (orig.) [de

  6. Vienna Convention and Its Revision and convention on Supplementary Compensation for Nuclear Damage on September 12, 1997

    International Nuclear Information System (INIS)

    Soljan, V.

    1998-01-01

    After Chernobyl, the perception of common interest in modernization of the international regime that regulate various aspects of nuclear energy, has been evident among states with nuclear power plants as well as those likely to be involved in or affected by a nuclear incident. The adoption of the protocol Amending the Vienna Convention on Civil liability for Nuclear Damage, 1963 and the Convention on Supplementary Compensation for nuclear damage in September 1997, represents important part of the entire result that has been achieved from the 1986. This article gives a brief survey on the background of the process of modernization of the international regime of liability for nuclear damage and examines solutions contained in the provisions of the conventions. (author)

  7. Quantitative PCR analysis of diepoxybutane and epihalohydrin damage to nuclear versus mitochondrial DNA

    Energy Technology Data Exchange (ETDEWEB)

    LaRiviere, Frederick J. [Department of Chemistry, Washington and Lee University, Lexington, VA 24450 (United States); Newman, Adam G.; Watts, Megan L.; Bradley, Sharonda Q.; Juskewitch, Justin E. [Department of Chemistry, Colby College, 5757 Mayflower Hill Drive, Waterville, ME 04901 (United States); Greenwood, Paul G. [Department of Biology, Colby College, Waterville, ME 04901 (United States); Millard, Julie T., E-mail: jtmillar@colby.edu [Department of Chemistry, Colby College, 5757 Mayflower Hill Drive, Waterville, ME 04901 (United States)

    2009-05-12

    The bifunctional alkylating agents diepoxybutane (DEB) and epichlorohydrin (ECH) are linked to the elevated incidence of certain cancers among workers in the synthetic polymer industry. Both compounds form interstrand cross-links within duplex DNA, an activity suggested to contribute to their cytotoxicity. To assess the DNA targeting of these compounds in vivo, we assayed for damage within chicken erythro-progenitor cells at three different sites: one within mitochondrial DNA, one within expressed nuclear DNA, and one within unexpressed nuclear DNA. We determined the degree of damage at each site via a quantitative polymerase chain reaction, which compares amplification of control, untreated DNA to that from cells exposed to the agent in question. We found that ECH and the related compound epibromohydrin preferentially target nuclear DNA relative to mitochondrial DNA, whereas DEB reacts similarly with the two genomes. Decreased reactivity of the mitochondrial genome could contribute to the reduced apoptotic potential of ECH relative to DEB. Additionally, formation of lesions by all agents occurred at comparable levels for unexpressed and expressed nuclear loci, suggesting that alkylation is unaffected by the degree of chromatin condensation.

  8. Quantitative PCR analysis of diepoxybutane and epihalohydrin damage to nuclear versus mitochondrial DNA

    International Nuclear Information System (INIS)

    LaRiviere, Frederick J.; Newman, Adam G.; Watts, Megan L.; Bradley, Sharonda Q.; Juskewitch, Justin E.; Greenwood, Paul G.; Millard, Julie T.

    2009-01-01

    The bifunctional alkylating agents diepoxybutane (DEB) and epichlorohydrin (ECH) are linked to the elevated incidence of certain cancers among workers in the synthetic polymer industry. Both compounds form interstrand cross-links within duplex DNA, an activity suggested to contribute to their cytotoxicity. To assess the DNA targeting of these compounds in vivo, we assayed for damage within chicken erythro-progenitor cells at three different sites: one within mitochondrial DNA, one within expressed nuclear DNA, and one within unexpressed nuclear DNA. We determined the degree of damage at each site via a quantitative polymerase chain reaction, which compares amplification of control, untreated DNA to that from cells exposed to the agent in question. We found that ECH and the related compound epibromohydrin preferentially target nuclear DNA relative to mitochondrial DNA, whereas DEB reacts similarly with the two genomes. Decreased reactivity of the mitochondrial genome could contribute to the reduced apoptotic potential of ECH relative to DEB. Additionally, formation of lesions by all agents occurred at comparable levels for unexpressed and expressed nuclear loci, suggesting that alkylation is unaffected by the degree of chromatin condensation.

  9. Analysis of the participation of nuclear energy in electricity planning in Mexico; Analisis de la participacion de la energia nuclear en la planeacion electrica en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez H, U. A.; Martin del C, C., E-mail: uahh_123@hotmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, Circuito Exterior s/n, 04510 Ciudad de Mexico (Mexico)

    2017-09-15

    In recent years there has been an effort in Mexico and the world to reduce greenhouse gas emissions (GGE) and at the same time supply the increase in energy consumption worldwide. In this context, the electricity sector in Mexico is fundamental in the fulfillment of GGE reduction commitments and goals by contributing more than 20% of these. Nuclear energy must have a fundamental role in the expansion of the National Electric System, since it allows generating large amounts of electricity for long periods of time without emissions of polluting gases. With this background, was determined to investigate the main characteristics that nuclear technology must have in order to be considered as a real solution in guaranteeing the supply of electricity in a continuous, safe and economic manner with the least amount of GGE possible. However, combined cycle power plants are the main option to cover these needs in accordance with the current national policy, so in this work an extensive technical, economic and safety comparison between the combined cycle and nuclear technologies was carried out. In order to know the technology that should have a greater participation in the planning of the National Electric System in the coming decades. Thus, five price scenarios were elaborated for natural gas and liquefied natural gas imports, in order to know the cost that would generate to continue with the current policy of use of combined cycle power plants as a base for electricity generation and if that cost justified in the first instance the increase of nuclear capacity in the country. The results showed that is necessary to change the main source of power generation in Mexico in order to have a reliable, safe, economical and clean electrical system. (Author)

  10. Analysis considerations in the future of the nuclear energy in Mexico; Consideraciones de analisis en el futuro de la energia nuclear en Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Alonso V, G., E-mail: gustavo.alonso@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    Mexico requires for legal command reducing the participation of fossil energy for the electric power production to not more than 65% for 2024, the other 35% will be covered by sources of clean energy, among which are the renewable sources and the nuclear energy. Inside the National Strategy of Energy 2012-2016 3 possible scenarios are outlined to give execution to this command, in this work is made an analysis of these scenarios and its implications in energy safety. (Author)

  11. Nuclear Containment Inspection Using AN Array of Guided Wave Sensors for Damage Localization

    Science.gov (United States)

    Cobb, A. C.; Fisher, J. L.

    2010-02-01

    Nuclear power plant containments are typically both the last line of defense against the release of radioactivity to the environment and the first line of defense to protect against intrusion from external objects. As such, it is important to be able to locate any damage that would limit the integrity of the containment itself. Typically, a portion of the containment consists of a metallic pressure boundary that encloses the reactor primary circuit. It is made of thick steel plates welded together, lined with concrete and partially buried, limiting areas that can be visually inspected for corrosion damage. This study presents a strategy using low frequency (<50 kHz) guided waves to find corrosion-like damage several meters from the probe in a mock-up of the containment vessel. A magnetostrictive sensor (MsS) is scanned across the width of the vessel, acquiring waveforms at a fixed interval. A beam forming strategy is used to localize the defects. Experimental results are presented for a variety of damage configurations, demonstrating the efficacy of this technique for detecting damage smaller than the ultrasonic wavelength.

  12. Novel Concepts for Damage-Resistant Alloys in Next Generation Nuclear Power Systems

    Energy Technology Data Exchange (ETDEWEB)

    Stephen M. Bruemmer; Peter L. Andersen; Gary Was

    2002-12-27

    The discovery of a damage-resistant alloy based on Hf solute additions to a low-carbon 316SS is the highlight of the Phase II research. This damage resistance is supported by characterization of radiation-induced microstructures and microchemistries along with measurements of environmental cracking. The addition of Hf to a low-carbon 316SS reduced the detrimental impact of radiation by changing the distribution of Hf. Pt additions reduced the impact of radiation on grain boundary segregation but did not alter its effect on microstructural damage development or cracking. Because cracking susceptibility is associated with several material characteristics, separate effect experiments exploring strength effects using non-irradiated stainless steels were conducted. These crack growth tests suggest that irradiation strength by itself can promote environmental cracking. The second concept for developing damage resistant alloys is the use of metastable precipitates to stabilize the microstructure during irradiation. Three alloys have been tailored for evaluation of precipitate stability influences on damage evolution. The first alloy is a Ni-base alloy (alloy 718) that has been characterized at low neutron irradiation doses but has not been characterized at high irradiation doses. The other two alloys are Fe-base alloys (PH 17-7 and PH 17-4) that have similar precipitate structures as alloy 718 but is more practical in nuclear structures because of the lower Ni content and hence lesser transmutation to He.

  13. Damaged Spent Nuclear Fuel at U.S. DOE Facilities Experience and Lessons Learned

    International Nuclear Information System (INIS)

    Brett W. Carlsen; Eric Woolstenhulme; Roger McCormack

    2005-01-01

    From a handling perspective, any spent nuclear fuel (SNF) that has lost its original technical and functional design capabilities with regard to handling and confinement can be considered as damaged. Some SNF was damaged as a result of experimental activities and destructive examinations; incidents during packaging, handling, and transportation; or degradation that has occurred during storage. Some SNF was mechanically destroyed to protect proprietary SNF designs. Examples of damage to the SNF include failed cladding, failed fuel meat, sectioned test specimens, partially reprocessed SNFs, over-heated elements, dismantled assemblies, and assemblies with lifting fixtures removed. In spite of the challenges involved with handling and storage of damaged SNF, the SNF has been safely handled and stored for many years at DOE storage facilities. This report summarizes a variety of challenges encountered at DOE facilities during interim storage and handling operations along with strategies and solutions that are planned or were implemented to ameliorate those challenges. A discussion of proposed paths forward for moving damaged and nondamaged SNF from interim storage to final disposition in the geologic repository is also presented

  14. The order for enforcing the law concerning indemnification of nuclear damage

    International Nuclear Information System (INIS)

    1980-01-01

    The cabinet ordinance is established under the law concerning the indemnification for atomic energy damages. The matters stipulated by the ordinance in the law include the following matters: the operation of reactors; the processing of nuclear fuel materials, such as uranium 235, specified uranium and its compounds, plutonium and its compounds, etc.; reprocessing; the employment of such nuclear fuel materials; the transportation, storage and disposal of such materials, particular spent fuels and the things contaminated by nuclear fuel materials, which occur according to the operation of reactors and other practices above mentioned. The amounts of indemnification are respectively 10 billion yen for the operation of reactors whose thermal outputs are more than 10,000 kilowatts and reprocessing, 2 billion yen for the operation of reactors whose thermal outputs are more than 100 kilowatts and less than 10,000 kilowatts and the transportation of spent fuel accompanying the operation of reactors or reprocessing, 200 million yen for the operation of reactors whose thermal outputs are less than 100 kilowatts, and the processing and employment of nuclear fuel materials, the transportation of nuclear fuel materials accompanying the operation of reactors, and the processing, reprocessing and employment of nuclear fuel materials. The payment of casualty indemnification includes that according to the provisions of the government official casualty indemnification law and that due to official causes under the provisions of the seamen insurance law. (Okada, K.)

  15. Deterministic Safety Analysis for Nuclear Power Plants. Specific Safety Guide (Spanish Edition); Analisis determinista de seguridad para centrales nucleares. Guia de Seguridad Especifica

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-12-15

    The IAEA's Statute authorizes the Agency to establish safety standards to protect health and minimize danger to life and property - standards which the IAEA must use in its own operations, and which a State can apply by means of its regulatory provisions for nuclear and radiation safety. A comprehensive body of safety standards under regular review, together with the IAEA's assistance in their application, has become a key element in a global safety regime. In the mid-1990s, a major overhaul of the IAEA's safety standards programme was initiated, with a revised oversight committee structure and a systematic approach to updating the entire corpus of standards. The new standards that have resulted are of a high calibre and reflect best practices in Member States. With the assistance of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its safety standards. Safety standards are only effective, however, if they are properly applied in practice. The IAEA's safety services - which range in scope from engineering safety, operational safety, and radiation, transport and waste safety to regulatory matters and safety culture in organizations - assist Member States in applying the standards and appraise their effectiveness. These safety services enable valuable insights to be shared and I continue to urge all Member States to make use of them. Regulating nuclear and radiation safety is a national responsibility, and many Member States have decided to adopt the IAEA's safety standards for use in their national regulations. For the contracting parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions. The standards are also applied by designers, manufacturers and operators around the world to enhance nuclear and radiation safety in power generation, medicine, industry, agriculture, research and education

  16. Energy analysis of a desalination process of sea water with nuclear energy; Analisis energetico de un proceso de desalinizacion de agua de mar con energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Martinez L, G.; Valle H, J., E-mail: julfi_jg@yahoo.com.mx [Universidad Politecnica Metropolitana de Hidalgo, Boulevard acceso a Tolcayuca No. 1009, Ex-hacienda San Javier, 43860 Tolcayuca, Hidalgo (Mexico)

    2016-09-15

    In the present work, is theoretically proven that the residual heat, removed by the chillers in the stage prior to the compression of the recuperative Brayton cycle with which nuclear power plants operate with high temperature gas reactors (HTGR), can be used to produce stem and desalinate seawater. The desalination process selected for the analysis, based on its operating characteristics, is the Multi-Stage Distillation (Med). The Med process will use as energy source, for the flash evaporation process in the flash trap, the residual heat that the reactor coolant dissipates to the environment in order to increase the compression efficiency of the same; the energy dissipated depends on the operating conditions of the reactor. The Med distillation process requires saturated steam at low pressure which can be obtained by means of a heat exchanger, taking advantage of the residual heat, where the relative low temperatures with which the process operates make the nuclear plants with HTGR reactors ideal for desalination of sea water, because they do not require major modifications to their design of their operation. In this work the energy analysis of a six-stage Med module coupled to the chillers of an HTGR reactor of the Pebble Bed Modular Reactor type is presented. Mathematical modeling was obtained by differential equations of mass and energy balances in the system. The results of the analysis are presented in a table for each distillation stage, estimating the pure water obtained as a function of the heat supplied. (Author)

  17. An image analyzer system for the analysis of nuclear traces; Un sistema analizador de imagenes para el analisis de trazas nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Cuapio O, A

    1990-10-15

    Inside the project of nuclear traces and its application techniques to be applied in the detection of nuclear reactions of low section (non detectable by conventional methods), in the study of accidental and personal neutron dosemeters, and other but, are developed. All these studies are based on the fact that the charged particles leave latent traces of dielectric that if its are engraved with appropriate chemical solutions its are revealed until becoming visible to the optical microscope. From the analysis of the different trace forms, it is possible to obtain information of the characteristic parameters of the incident particles (charge, mass and energy). Of the density of traces it is possible to obtain information of the flow of the incident radiation and consequently of the received dose. For carry out this analysis has been designed and coupled different systems, that it has allowed the solution of diverse outlined problems. Notwithstanding it has been detected that to make but versatile this activity is necessary to have an Image Analyzer System that allow us to digitize, to process and to display the images with more rapidity. The present document, presents the proposal to carry out the acquisition of the necessary components for to assembling an Image Analyzing System, like support to the mentioned project. (Author)

  18. A quantitative 14-3-3 interaction screen connects the nuclear exosome targeting complex to the DNA damage response

    DEFF Research Database (Denmark)

    Blasius, Melanie; Wagner, Sebastian A; Choudhary, Chuna Ram

    2014-01-01

    RNA metabolism is altered following DNA damage, but the underlying mechanisms are not well understood. Through a 14-3-3 interaction screen for DNA damage-induced protein interactions in human cells, we identified protein complexes connected to RNA biology. These include the nuclear exosome...

  19. Nondestructive Evaluation of Functionally Graded Subsurface Damage on Cylinders in Nuclear Installations Based on Circumferential SH Waves

    Directory of Open Access Journals (Sweden)

    Zhen Qu

    2016-01-01

    Full Text Available Subsurface damage could affect the service life of structures. In nuclear engineering, nondestructive evaluation and detection of the evaluation of the subsurface damage region are of great importance to ensure the safety of nuclear installations. In this paper, we propose the use of circumferential horizontal shear (SH waves to detect mechanical properties of subsurface regions of damage on cylindrical structures. The regions of surface damage are considered to be functionally graded material (FGM and the cylinder is considered to be a layered structure. The Bessel functions and the power series technique are employed to solve the governing equations. By analyzing the SH waves in the 12Cr-ODS ferritic steel cylinder, which is frequently applied in the nuclear installations, we discuss the relationship between the phase velocities of SH waves in the cylinder with subsurface layers of damage and the mechanical properties of the subsurface damaged regions. The results show that the subsurface damage could lead to decrease of the SH waves’ phase velocity. The gradient parameters, which represent the degree of subsurface damage, can be evaluated by the variation of the SH waves’ phase velocity. Research results of this study can provide theoretical guidance in nondestructive evaluation for use in the analysis of the reliability and durability of nuclear installations.

  20. High dose radiation damage in nuclear energy structural materials investigated by heavy ion irradiation simulation

    International Nuclear Information System (INIS)

    Zheng Yongnan; Xu Yongjun; Yuan Daqing

    2014-01-01

    Structural materials in ITER, ADS and fast reactor suffer high dose irradiations of neutrons and/or protons, that leads to severe displacement damage up to lOO dpa per year. Investigation of radiation damage induced by such a high dose irradiation has attracted great attention along with the development of nuclear energy facilities of new generation. However, it is deeply hampered for the lacking of high dose neutron and proton sources. Irradiation simulation of heavy ions produced by accelerators opens up an effective way for laboratory investigation of high dose irradiation induced radiation damage encountered in the ITER, ADS, etc. Radiation damage is caused mainly by atomic displacement in materials. The displacement rate of heavy ions is about lO 3 ∼10 7 orders higher than those of neutrons and protons. High displacement rate of heavy ions significantly reduces the irradiation time. The heavy ion irradiation simulation technique (HIIS) technique has been developed at China Institute of Atomic Energy and a series of the HIIS experiments have been performed to investigate radiation damage in stainless steels, tungsten and tantalum at irradiation temperatures from room temperature to 800 ℃ and in the irradiation dose region up to 100 dpa. The experimental results show that he radiation swelling peak for the modified stainless steel appears in the temperature region around 580 ℃ and the radiation damage is more sensitive to the temperature, the size of the radiation induced vacancy cluster or void increase with the increasing of the irradiation dose, and among the three materials the home-made modified stainless steel has the best radiation resistant property. (authors)

  1. Radiation damage studies in nuclear waste storage matrices: a few remarks

    International Nuclear Information System (INIS)

    Limoge, Y.

    1997-01-01

    For safe management of high level nuclear waste (HLNW) we have to predict the behaviour of the storage matrix that will have to sustain irradiation over a long period of 10 4 to 10 5 years. 2 approaches are possible and in fact complementary. The first approach is an experimental one: the selected material is submitted to an acceleration of the damage by using various forms of external or internal radiations delivering a higher flux than the stored wastes themselves. The second approach is a cognitive one that requires the modelling of the radiation damage. The second approach seems to have been less developed than the first one. The second approach is a multi-step one. The first step is to review and model all possible phenomena occurring in irradiated material. The second step is to review the different kinds of defects produced by irradiation, their possible mutual interaction and their elimination modes that are followed by the material to go back to equilibrium. There have been a lot of detailed studies of defect formation under ionizing conditions in silica and simple silica based glass, mainly for electronic industry purposes. Fewer studies have been done on nuclear glasses. This article makes a point about the necessity and need for reliable simulation of long-term irradiation effects on nuclear glasses

  2. Review of the Shoreham Nuclear Power Station Probabilistic Risk Assessment: internal events and core damage frequency

    International Nuclear Information System (INIS)

    Ilberg, D.; Shiu, K.; Hanan, N.; Anavim, E.

    1985-11-01

    A review of the Probabilistic Risk Assessment of the Shoreham Nuclear Power Station was conducted with the broad objective of evaluating its risks in relation to those identified in the Reactor Safety Study (WASH-1400). The scope of the review was limited to the ''front end'' part, i.e., to the evaluation of the frequencies of states in which core damage may occur. Furthermore, the review considered only internally generated accidents, consistent with the scope of the PRA. The review included an assessment of the assumptions and methods used in the Shoreham study. It also encompassed a reevaluation of the main results within the scope and general methodological framework of the Shoreham PRA, including both qualitative and quantitative analyses of accident initiators, data bases, and accident sequences which result in initiation of core damage. Specific comparisons are given between the Shoreham study, the results of the present review, and the WASH-1400 BWR, for the core damage frequency. The effect of modeling uncertainties was considered by a limited sensitivity study so as to show how the results would change if other assumptions were made. This review provides an independently assessed point value estimate of core damage frequency and describes the major contributors, by frontline systems and by accident sequences. 17 figs., 81 tabs

  3. Damage-plasticity model of the host rock in a nuclear waste repository

    Energy Technology Data Exchange (ETDEWEB)

    Koudelka, Tomáš; Kruis, Jaroslav, E-mail: kruis@fsv.cvut.cz [Department of Mechanics, Faculty of Civil Engineering, Czech Technical University in Prague, Thákurova 7, 166 29 Prague (Czech Republic)

    2016-06-08

    The paper describes damage-plasticity model for the modelling of the host rock environment of a nuclear waste repository. Radioactive Waste Repository Authority in Czech Republic assumes the repository to be in a granite rock mass which exhibit anisotropic behaviour where the strength in tension is lower than in compression. In order to describe this phenomenon, the damage-plasticity model is formulated with the help of the Drucker-Prager yield criterion which can be set to capture the compression behaviour while the tensile stress states is described with the help of scalar isotropic damage model. The concept of damage-plasticity model was implemented in the SIFEL finite element code and consequently, the code was used for the simulation of the Äspö Pillar Stability Experiment (APSE) which was performed in order to determine yielding strength under various conditions in similar granite rocks as in Czech Republic. The results from the performed analysis are presented and discussed in the paper.

  4. The principle of proportionateness in the nuclear law to provide against damage

    International Nuclear Information System (INIS)

    Marburger, P.

    1983-01-01

    The author explains the principle of proportionateness as applied in licensing procedures for nuclear installations to provide against damage, as required by section 7, sub-section (2), no. 3 of the Atomic Energy Act. He stated that in his opinion, the appropriateness as an important element of the principle of proportionateness in the law pertaining to technical safety calls for a balanced evaluation so that in principle, additional safety requirements ought to be set only if they undoubtedly bring about additional improvements, improvements that clearly outweigh any disadvantages. This, he said, is also the opinion of the Federal Constitutional Court, as expressed in the indicial declaration of law. Appropriate consideration is also to be given to economic aspects (risk/cost evaluations) when deciding upon appropriate measures to provide against damage. (WB) [de

  5. Probabilistic analysis of safety of a production plant of hydrogen using nuclear energy; Analisis probabilistico de seguridad de una planta de produccion de hidrogeno utilizando energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Flores F, A. [Facultad de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico); Nelson E, P.F.; Francois L, J.L. [Facultad de Ingenieria, UNAM, Paseo Cuauhnahuac 8532, Jiutepec, Morelos (Mexico)]. e-mail: alain_fyf@yahoo.com

    2005-07-01

    The present work makes use of the Probabilistic Safety analysis to evaluate and to quantify the safety in a plant producer of hydrogen coupled to a nuclear reactor of high temperature, the one which is building in Japan. It is had the description of systems and devices of the HTTR, the pipe diagrams and instrumentation of the plant, as well as the rates of generic faults for the components of the plant. The first step was to carry out a HAZOP study (Hazard and Operability Study) with the purpose of obtaining the initiator events; once obtained these, it was developed a tree of events by each initiator event and for each system it was developed a fault tree; the data used for the quantification of the failure probability of the systems were obtained starting from several generic sources of information. In each tree of events different final states were obtained and it stops each one, their occurrence frequency. The construction and evaluation of the tree of events and of failures one carries out with the SAPHIRE program. The results show the safety of the shutdown system of the HTTR and they allow to suggest modifications to the auxiliary system of refrigeration and to the heat exchanger helium/water pressurized. (Author)

  6. The effect of uncertainties in nuclear reactor plant-specific failure data on core damage frequency

    International Nuclear Information System (INIS)

    Martz, H.F.

    1995-05-01

    It is sometimes the case in PRA applications that reported plant-specific failure data are, in fact, only estimates which are uncertain. Even for detailed plant-specific data, the reported exposure time or number of demands is often only an estimate of the actual exposure time or number of demands. Likewise the reported number of failure events or incidents is sometimes also uncertain because incident or malfunction reports may be ambiguous. In this report we determine the corresponding uncertainty in core damage frequency which can b attributed to such uncertainties in plant-specific data using a simple but typical nuclear power reactor example

  7. Study of DNA damage with a new system for irradiation of samples in a nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Gual, Maritza R., E-mail: mrgual@instec.c [Instituto Superior de Tecnologias y Ciencias Aplicadas, InSTEC, Avenida Salvador Allende y Luaces, Quinta de Los Molinos, Plaza de la Revolucion, Havana, AP 6163 (Cuba); Milian, Felix M. [Universidade Estadual de Santa Cruz, UESC (Brazil); Deppman, Airton [Instituto de Fisica, Universidad de Sao Paulo, IF-USP, Rua do Matao, Travessa R, no. 187, Ciudade Universitaria, Butanta, CEP 05508-900, Sao Paulo (Brazil); Coelho, Paulo R.P. [Instituto de Pesquisas Energeticas e Nucleares, IPEN-CNEN/SP (Brazil)

    2011-02-15

    In this paper, we report results of a quantitative analysis of the effects of neutrons on DNA, and, specifically, the production of simple and double breaks of plasmid DNA in aqueous solutions with different concentrations of free-radical scavengers. The radiation damage to DNA was evaluated by electrophoresis through agarose gels. The neutron and gamma doses were measured separately with thermoluminescent detectors. In this work, we have also demonstrated usefulness of a new system for positioning and removing samples in channel BH3 of the IEA-R1 reactor at the Instituto de Pesquisas Energeticas e Nucleares (Brazil) without necessity of interrupting the reactor operation.

  8. Equipment for testing a group of nuclear reactor fuel elements for damage to the cans

    International Nuclear Information System (INIS)

    Mohm, F.

    1977-01-01

    Equipment is described for use in sodium cooled nuclear reactors, with which the fuel elements consisting of bundles of fuel and fertile rods can be examined for damage to the cans. Fission poducts occurring in the liquid coolant act as indicators. The coolant is sucked via pipelines which penetrate into the elements into a collecting container, and a special pipeline is available for every element of a group, where the highest points of individual pipelines at different hydrostatic heads are taken to the collecting container. This permits the checking of one line at a time due to pressure changes. (UWI) [de

  9. Accident prevention and security measures to prevent intentional harm and damage through nuclear energy

    International Nuclear Information System (INIS)

    Rauschning, D.

    1984-01-01

    The author explains the authorities' duty to provide for protection against intentional damage or physical harm through the use of nuclear energy. It belongs to the competence of the various authorities to define ways and means to afford protection, and to establish an appropriate network of provisions. There are provisions belonging to criminal law, those concerning liability and indemnity, and security regulations incorporated in the law on licensing and supervision. The author presents a detailed account of the law applicable and discusses the conflict of interests between governmental duties and intentions and the civil rights of the individual affected by the provisions. (HSCH) [de

  10. Analysis of simulation results of damaged nuclear fuel accidents at NPPs with shell-type nuclear reactors

    Directory of Open Access Journals (Sweden)

    Igor L. Kozlov

    2015-03-01

    Full Text Available Lessons from the accident at the Fukushima Daiichi NPP made it necessary to reevaluate and intensificate the work on modeling and analyzing various scenarios of severe accidents with damage to the nuclear fuel in the reactor, containment and spent nuclear fuel storage pool with the expansion of the primary initiating event causes group listing. Further development of computational tools for modeling the explosion prevention criteria as to steam and gas mixtures, considering the specific thermal-hydrodynamic conditions and mechanisms of explosive situations arrival at different stages of a severe accident development, is substantiated. Based on the analysis of the known shell-type nuclear reactors accidents results the explosion safety thermodynamic criteria are presented, the parameters defining the steam and gas explosions conditions are found, the need to perform the further verification and validation of deterministic codes serving to simulate general accident processes behavior as well as phase-to-phase interaction calculated dependencies is established. The main parameters controlling and defining the criteria explosion safety effective regulation areas and their optimization conditions are found.

  11. Notes on third party liability for nuclear damage in connection with the construction of the first nuclear power plant in Brazil

    International Nuclear Information System (INIS)

    Simoes, A.C.

    1975-01-01

    Responsibilities for the construction and operation of the first nuclear power plant have been transferred from the National Nuclear Energy Commission to Electrobras, a public undertaking set up for this purpose. In view of such transfer of responsibilities and the implementation of further nuclear power projects, liability for nuclear damage has to be regulated in a way consistent with international conventions. A working group associating representatives of national authorities and public utilities was entrusted with the task of drafting rules for co-ordinating their respective activities in relation to the execution of the first nuclear power project; these rules were issued by Ministerial order in 1970. The working group also prepared a draft law on civil liability for nuclear damage, based on the Vienna Convention. This draft law has reached its final stage and, after promulgation, will enable Brazil to ratify the Vienna Convention. (author)

  12. Oxidative damage of mitochondrial and nuclear DNA induced by ionizing radiation in human hepatoblastoma cells

    International Nuclear Information System (INIS)

    Morales, Albert; Miranda, Merce; Sanchez-Reyes, Alberto; Biete, Alberto; Fernandez-Checa, Jose C.

    1998-01-01

    Purpose: Since reactive oxygen species (ROS) act as mediators of radiation-induced cellular damage, the aim of our studies was to determine the effects of ionizing radiation on the regulation of hepatocellular reduced glutathione (GSH), survival and integrity of nuclear and mitochondrial DNA (mtDNA) in human hepatoblastoma cells (Hep G2) depleted of GSH prior to radiation. Methods and Materials: GSH, oxidized glutathione (GSSG), and generation of ROS were determined in irradiated (50-500 cGy) Hep G2 cells. Clonogenic survival, nuclear DNA fragmentation, and integrity of mtDNA were assessed in cells depleted of GSH prior to radiation. Results: Radiation of Hep G2 cells (50-400 cGy) resulted in a dose-dependent generation of ROS, an effect accompanied by a decrease of reduced GSH, ranging from a 15% decrease for 50 cGy to a 25% decrease for 400 cGy and decreased GSH/GSSG from a ratio of 17 to a ratio of 7 for controls and from 16 to 6 for diethyl maleate (DEM)-treated cells. Depletion of GSH prior to radiation accentuated the increase of ROS by 40-50%. The depletion of GSH by radiation was apparent in different subcellular sites, being particularly significant in mitochondria. Furthermore, depletion of nuclear GSH to 50-60% of initial values prior to irradiation (400 cGy) resulted in DNA fragmentation and apoptosis. Consequently, the survival of Hep G2 to radiation was reduced from 25% of cells not depleted of GSH to 10% of GSH-depleted cells. Fitting the survival rate of cells as a function of GSH using a theoretical model confirmed cellular GSH as a key factor in determining intrinsic sensitivity of Hep G2 cells to radiation. mtDNA displayed an increased susceptibility to the radiation-induced loss of integrity compared to nuclear DNA, an effect that was potentiated by GSH depletion in mitochondria (10-15% intact mtDNA in GSH-depleted cells vs. 25-30% of repleted cells). Conclusion: GSH plays a critical protective role in maintaining nuclear and mtDNA functional

  13. The regulation for enforcing the law concerning indemnification of nuclear damage

    International Nuclear Information System (INIS)

    1978-01-01

    These provisions are established on the basis of and to enforce the ''Law concerning the indemnification of nuclear damage''. Atomic energy enterprises who want to get the approval in connection with the Law shall file the applications to the Director General of Science and Technology Agency, in which the name and the address of the applicant, kinds of the operation of nuclear reactors, the name and the address of the factory or the establishment concerning the operation of nuclear reactors, the thermal output of the reactors, the kinds and quantities of nuclear fuel materials or the things contaminated by such materials to be transported, and the time of starting and the expected time of ending the operation of the reactors, etc. To such applications, shall be attached actually surveyed maps indicating the area of the factory or the establishment concerning the operation of the reactors and the documents certifying the conclusion of obligatory insurances and indemnification contracts, etc. The securities which can be deposited and recovering of such securities are prescribed. (Okada, K.)

  14. Act No 6453 of 17th October, 1977 on civil liability for nuclear damage and criminal responsibility for acts relating to nuclear activities, and other provisions

    International Nuclear Information System (INIS)

    1978-01-01

    This Act was published on 17 October 1977. It is based to a great extent on the provisions of the Vienna Convention on Civil Liability for Nucler Damage of 21 May 1963. Under the Act the operator of a nuclear installation is exclusively liable regardless of fault for compensation of nuclear damage due to a nuclear incident. This exclusive liability is limited to an amount equal to 1,500,000 Treasury Bonds and the operator must take out and maintain insurance or other financial security to cover his liability. The Federative Government will guarantee, up to the prescribed limit, payment of compensation for nuclear damage where it is acknowledged that the operator's liability is involved. As regards apportionment of compensation, persons are granted priority over property. This Act is original in that it contains provisions on criminal liability with penalties ranging from two to ten years imprisonment. (NEA) [fr

  15. Questions raised by the concept of nuclear damage in the ambit of the nuclear Conventions with particular regard to the German viewpoint

    International Nuclear Information System (INIS)

    Steinkemper, H.

    1985-01-01

    An important consequence of the amendment of the Paris Convention and the Brussels Supplementary Convention by the Protocols of 16 November 1982 is the replacement of the European Monetary Agreement unit of account by the International Monetary Fund's Special Drawing Right. The increase by a factor of 2.5 of the maximum amounts under the Brussels Convention is also an essential aspect of the revision. The question of damage covered by the nuclear third party liability regime was not affected by the 1982 amendments. This is why the author considers it appropriate to examine in further detail a number of important questions in this field. The paper deals with the following aspects: the scope and limits of the concept of nuclear damage; the right to be indemnified for disamenities and costs arising from evacuation and prevention measures; and the problem of the nuclear link of causality for damage likely to be attributed also to non-nuclear causes. (NEA) [fr

  16. Probabilistic analysis of turbine missile damage to nuclear power plant structures

    International Nuclear Information System (INIS)

    Twisdale, L.A.; Dunn, W.L.; Frank, R.A.

    1983-01-01

    This paper summarizes the results of the EPRI project that focused on the development of the overall probabilistic methodology to assess the risks of turbine missile induced damage to nuclear power plant structures and components. The project was structured to use the results of other EPRI projects that provided information on turbine failure and missile generation frequencies, models to predict the characteristics and exit conditions of the missiles, and experimental data for use in updating empirical impact formulas for reinforced concrete barriers. The research effort included: (1) adaptation and implementation of the missile generation probability and turbine casing impact models developed in Ref. [2]; (2) development of a methodology for the prediction of the motion of the postulated missile fragments that perforate the turbine casing; (3) development of a model using the experimental impact data to predict the effects of fragment impact on nuclear power plant barriers and components; (4) construction of a probabilistic damage assessment methodology using Monte Carlo simulation methodology; and (5) implementation of the methodology into an independent computer program (TURMIS), demonstration of its application to an example case study problem, and assessment of prediction sensitivity. (orig./RW)

  17. The usefulness of the nuclear cardiology in the cellular implant in patients with severe myocardial damage

    International Nuclear Information System (INIS)

    Omelas A, M.; Arguero S, R.; Garrido G, M.H.; Rodriguez C, A.; Careaga, G.; Castano G, R.; Nambo, M.J.; Pascual P, J.; Ortega R, A.; Gaxiola A, A.; Magana S, J.A.; Estrada A, H.; Equipo de Tecnicos en Medicina Nuclear

    2005-01-01

    The recent therapeutic advances as the cellular implant as well as those different protocols of image acquisition in the field of the Nuclear Cardiology its have allowed that the patient with severe myocardial damage and without some possibility of revascularization is benefited with these advances. Doubtless the Tl-201 par excellence has an important paper for standardize the more appropriate therapeutic behavior for the heart attack patient; reason by this investigation protocol was developed. The objective of the study was to identify the heart attack regions without viable tissue with SPECT in patient with important myocardial damage without some possibility of traditional revascularization; for the 'Stem cell' cellular implantation therapy. The methodology it was carried out by a study of myocardial perfusion in 10 patients with important myocardial damage previous cellular implants, with PICANUC/ SPECT methodology and using a software (Emory Tool Box) for the image processing validated by the University of Emory Atlanta GA; and using as tracer the Tl - 201 to identify the heart attack regions without presence of viable tissue with an analysis model of 17 segments standardized for the left ventricle; qualifying this way the myocardial perfusion in: 0 (normal), 1 (light), 2 (moderate), 3 (severe), 4 (absent) and x (bad technique). The conclusions were that the SPECT study with PICANUC methodology with Tl-201 is safe and effective for the precise localization for the cellular implantation via direct intra myocardial. (Author)

  18. Displacement damage effects on CMOS APS image sensors induced by neutron irradiation from a nuclear reactor

    International Nuclear Information System (INIS)

    Wang, Zujun; Huang, Shaoyan; Liu, Minbo; Xiao, Zhigang; He, Baoping; Yao, Zhibin; Sheng, Jiangkun

    2014-01-01

    The experiments of displacement damage effects on CMOS APS image sensors induced by neutron irradiation from a nuclear reactor are presented. The CMOS APS image sensors are manufactured in the standard 0.35 μm CMOS technology. The flux of neutron beams was about 1.33 × 10 8 n/cm 2 s. The three samples were exposed by 1 MeV neutron equivalent-fluence of 1 × 10 11 , 5 × 10 11 , and 1 × 10 12 n/cm 2 , respectively. The mean dark signal (K D ), dark signal spike, dark signal non-uniformity (DSNU), noise (V N ), saturation output signal voltage (V S ), and dynamic range (DR) versus neutron fluence are investigated. The degradation mechanisms of CMOS APS image sensors are analyzed. The mean dark signal increase due to neutron displacement damage appears to be proportional to displacement damage dose. The dark images from CMOS APS image sensors irradiated by neutrons are presented to investigate the generation of dark signal spike

  19. Fatigue damage evaluation of stainless steel pipes in nuclear power plants using positron annihilation lineshape analysis

    Energy Technology Data Exchange (ETDEWEB)

    Kawaguchi, Yasuhiro [Institute of Nuclear Safety System, Inc., Mihama, Fukui (Japan); Nakamura, Noriko; Yusa, Satoru [Ishikawajima-Harima Heavy Industries Co., Tokyo (Japan)

    2002-09-01

    Since positron annihilation lineshape analysis can evaluate the degree of fatigue damage by detecting defects such as dislocations in metals, we applied this method to evaluate that in a type 316 stainless steel pipe which was used in the primary system of a nuclear power plant. Using {sup 68}Ge as a positron source, an energy spread of annihilation gamma ray peak from the material was measured and expressed as the S-parameter. Actual plant material cut from a surge line pipe of a pressurizer in a pressurized water reactor type nuclear power plant was measured by positron annihilation lineshape analysis and the S-parameter was obtained. Comparing the S-parameter with a relationship between the S-parameter and fatigue life ratio of the type 316 stainless steel, we evaluated the degree of fatigue damage of the actual material. Furthermore, to verify the evaluation, microstructures of the actual material were investigated with TEM (transmission electron microscope) to observe dislocation densities. As a result, a change in the S-parameter of the actual material from standard as-received material (type 316 stainless steel) was in the range from -0.0013 to 0.0014, while variations in the S-parameter of the standard as-received material were about {+-}0.002, and hence the differences between the actual material and the as-received material were negligible. Moreover, the dislocation density of the actual plant material observed with TEM was almost the same as that of the as-received one. In conclusion, we could confirm the applicability of the positron annihilation lineshape analysis to fatigue damage evaluation of stainless steel. (author)

  20. Glutathione-deficient Plasmodium berghei parasites exhibit growth delay and nuclear DNA damage.

    Science.gov (United States)

    Padín-Irizarry, Vivian; Colón-Lorenzo, Emilee E; Vega-Rodríguez, Joel; Castro, María Del R; González-Méndez, Ricardo; Ayala-Peña, Sylvette; Serrano, Adelfa E

    2016-06-01

    Plasmodium parasites are exposed to endogenous and exogenous oxidative stress during their complex life cycle. To minimize oxidative damage, the parasites use glutathione (GSH) and thioredoxin (Trx) as primary antioxidants. We previously showed that disruption of the Plasmodium berghei gamma-glutamylcysteine synthetase (pbggcs-ko) or the glutathione reductase (pbgr-ko) genes resulted in a significant reduction of GSH in intraerythrocytic stages, and a defect in growth in the pbggcs-ko parasites. In this report, time course experiments of parasite intraerythrocytic development and morphological studies showed a growth delay during the ring to schizont progression. Morphological analysis shows a significant reduction in size (diameter) of trophozoites and schizonts with increased number of cytoplasmic vacuoles in the pbggcs-ko parasites in comparison to the wild type (WT). Furthermore, the pbggcs-ko mutants exhibited an impaired response to oxidative stress and increased levels of nuclear DNA (nDNA) damage. Reduced GSH levels did not result in mitochondrial DNA (mtDNA) damage or protein carbonylations in neither pbggcs-ko nor pbgr-ko parasites. In addition, the pbggcs-ko mutant parasites showed an increase in mRNA expression of genes involved in oxidative stress detoxification and DNA synthesis, suggesting a potential compensatory mechanism to allow for parasite proliferation. These results reveal that low GSH levels affect parasite development through the impairment of oxidative stress reduction systems and damage to the nDNA. Our studies provide new insights into the role of the GSH antioxidant system in the intraerythrocytic development of Plasmodium parasites, with potential translation into novel pharmacological interventions. Copyright © 2016 The Authors. Published by Elsevier Inc. All rights reserved.

  1. MAP kinase-signaling controls nuclear translocation of tripeptidyl-peptidase II in response to DNA damage and oxidative stress

    Energy Technology Data Exchange (ETDEWEB)

    Preta, Giulio; Klark, Rainier de; Chakraborti, Shankhamala [Center for Molecular Medicine (CMM), Department of Medicine, Karolinska Institutet, Karolinska University Hospital, 171 76 Stockholm (Sweden); Glas, Rickard, E-mail: rickard.glas@ki.se [Center for Molecular Medicine (CMM), Department of Medicine, Karolinska Institutet, Karolinska University Hospital, 171 76 Stockholm (Sweden)

    2010-08-27

    Research highlights: {yields} Nuclear translocation of TPPII occurs in response to different DNA damage inducers. {yields} Nuclear accumulation of TPPII is linked to ROS and anti-oxidant enzyme levels. {yields} MAPKs control nuclear accumulation of TPPII. {yields} Inhibited nuclear accumulation of TPPII decreases DNA damage-induced {gamma}-H2AX expression. -- Abstract: Reactive oxygen species (ROS) are a continuous hazard in eukaroytic cells by their ability to cause damage to biomolecules, in particular to DNA. Previous data indicated that the cytosolic serine peptidase tripeptidyl-peptidase II (TPPII) translocates into the nucleus of most tumor cell lines in response to {gamma}-irradiation and ROS production; an event that promoted p53 expression as well as caspase-activation. We here observed that nuclear translocation of TPPII was dependent on signaling by MAP kinases, including p38MAPK. Further, this was caused by several types of DNA-damaging drugs, a DNA cross-linker (cisplatinum), an inhibitor of topoisomerase II (etoposide), and to some extent also by nucleoside-analogues (5-fluorouracil, hydroxyurea). In the minority of tumor cell lines where TPPII was not translocated into the nucleus in response to DNA damage we observed reduced intracellular ROS levels, and the expression levels of redox defense systems were increased. Further, treatment with the ROS-inducer {gamma}-hexa-chloro-cyclohexane ({gamma}-HCH, lindane), an inhibitor of GAP junctions, restored nuclear translocation of TPPII in these cell lines upon {gamma}-irradiation. Moreover, blocking nuclear translocation of TPPII in etoposide-treated cells, by using a peptide-derived inhibitor (Z-Gly-Leu-Ala-OH), attenuated expression of {gamma}-H2AX in {gamma}-irradiated melanoma cells. Our results indicated a role for TPPII in MAPK-dependent DNA damage signaling.

  2. The regulation for enforcing the law concerning indemnification of nuclear damage

    International Nuclear Information System (INIS)

    1980-01-01

    The regulation is set up under the provisions of the law concerning the indemnification for atomic energy damages, to enforce them. An atomic energy business enterpriser who intends to get the approval of indemnification measures specified under the law shall file an application to the General Director of the Science Technology Agency, attaching particular documents and writing the following matters: his name and address; the kinds of operation of reactors; the names and addresses of works or places of business where reactors are operated; the thermal output of reactors; the kinds and quantities of nuclear fuel materials processed or employed; the kinds and quantities of nuclear fuel materials or contaminated materials to be transported; the kinds and quantities of nuclear fuel materials or contaminated materials to be disposed; beginning dates and expected ending dates of the operation of reactors; and other items stipulated concerning liability insurance and indemnification contracts. The negotiable securities qualified to be trusted include government bonds; municipal bonds; bonds issued by particular legal persons; bonds issued by banks, Central Cooperative Bank for Agriculture and Forestry, or Bank for Commerce and Industrial Cooperatives, and secured debentures under the secured debenture trust law. The recovering of trusted securities and identification cards are defined, respectively. (Okada, K.)

  3. Internal event analysis of Laguna Verde Unit 1 Nuclear Power Plant. System Analysis; Analisis de Eventos Internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Analisis de sistemas

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A; Aguilar T, O; Nunez C, A; Lopez M, R [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1993-07-01

    The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the {sup I}nternal Event Analysis of Laguna Verde Unit 1 Nuclear Power Plant{sup ,} CNSNS-TR-004, in five volumes. The reports are organized as follows: CNSNS-TR-004 Volume 1: Introduction and Methodology. CNSNS-TR-004 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR-004 Volume 3: System Analysis. CNSNS-TR-004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR-004 Volume 5: Appendices A, B and C. This volume presents the results of the system analysis for the Laguna Verde Unit 1 Nuclear Power Plant. The system analysis involved the development of logical models for all the systems included in the accident sequence event tree headings, and for all the support systems required to operate the front line systems. For the Internal Event analysis for Laguna Verde, 16 front line systems and 5 support systems were included. Detailed fault trees were developed for most of the important systems. Simplified fault trees focusing on major faults were constructed for those systems that can be adequately represent,ed using this kind of modeling. For those systems where fault tree models were not constructed, actual data were used to represent the dominant failures of the systems. The main failures included in the fault trees are hardware failures, test and maintenance unavailabilities, common cause failures, and human errors. The SETS and TEMAC codes were used to perform the qualitative and quantitative fault tree analyses. (Author)

  4. Act No. 225 of 17 March 1979 containing regulations on third party liability for damage caused by nuclear incidents; Nuclear Incidents (Third Party Liability) Act

    International Nuclear Information System (INIS)

    1979-01-01

    This Act on nuclear third party liability provides that the maximum amount of liability of the operator of a nuclear installation in the Netherlands is set at 100 million guilders in accordance with the Paris Convention; it also implements the Brussels Supplementary Convention's additional compensation mechanism. The new Act further provides that if damage is suffered on the Netherlands' territory as a result of a nuclear incident for which compensation is payable pursuant to the Brussels Convention or to the Act, and that the funds available for this purpose are insufficient to secure compensation of such damage to an amount of one thousand million guilders, the State shall make available the public funds needed to compensate such damage up to that amount. (NEA) [fr

  5. Radiation Damage in Nuclear Fuel for Advanced Burner Reactors: Modeling and Experimental Validation

    Energy Technology Data Exchange (ETDEWEB)

    Jensen, Niels Gronbech; Asta, Mark; Ozolins, Nigel Browning' Vidvuds; de Walle, Axel van; Wolverton, Christopher

    2011-12-29

    The consortium has completed its existence and we are here highlighting work and accomplishments. As outlined in the proposal, the objective of the work was to advance the theoretical understanding of advanced nuclear fuel materials (oxides) toward a comprehensive modeling strategy that incorporates the different relevant scales involved in radiation damage in oxide fuels. Approaching this we set out to investigate and develop a set of directions: 1) Fission fragment and ion trajectory studies through advanced molecular dynamics methods that allow for statistical multi-scale simulations. This work also includes an investigation of appropriate interatomic force fields useful for the energetic multi-scale phenomena of high energy collisions; 2) Studies of defect and gas bubble formation through electronic structure and Monte Carlo simulations; and 3) an experimental component for the characterization of materials such that comparisons can be obtained between theory and experiment.

  6. The regulation for enforcing the law concerning indemnification of nuclear damage

    International Nuclear Information System (INIS)

    1977-01-01

    The atomic energy entrepreneurs wishing to obtain the approval according to Item 1, Article 7 of the Law Concerning Indemnification of Nuclear Damage should file application (one original and one duplicate) describing the following items to the Director of the Science and Technology Agency: (1) in case of taking indemnification measures including the conclusion of responsibility insurance contracts and indemnification contracts, the particulars of the contracts including the sum of money involved, (2) in case of taking indemnification measures including deposit, the particulars of the deposit including the sum of money involved, and (3) in case of taking loss indemnification measures including the conclusion of responsibility insurance contracts and indemnification contracts or other measures than deposit, the particulars of such measures. (Rikitake, Y.)

  7. Detecting Structural Damage of Nuclear Power Plant by Interactive Data Mining Approach

    International Nuclear Information System (INIS)

    Yufei Shu

    2006-01-01

    This paper presents a nonlinear structural damage identification technique, based on an interactive data mining approach, which integrates a human cognitive model in a data mining loop. A mining control agent emulating human analysts is developed, which directly interacts with the data miner, analyzing and verifying the output of the data miner and controlling the data mining process. Additionally, an artificial neural network method, which is adopted as a core component of the proposed interactive data mining method, is evolved by adding a novelty detecting and retraining function for handling complicated nuclear power plant quake-proof data. Plant quake-proof testing data has been applied to the system to show the validation of the proposed method. (author)

  8. Tracking of Airborne Radionuclides from the Damaged Fukushima Dai-Ichi Nuclear Reactors by European Networks

    DEFF Research Database (Denmark)

    Masson, O.; Baeza, A.; Bieringer, J.

    2011-01-01

    Radioactive emissions into the atmosphere from the damaged reactors of the Fukushima Dai-ichi nuclear power plant (NPP) started on March 12th, 2011. Among the various radionuclides released, iodine-131 (131I) and cesium isotopes (137Cs and 134Cs) were transported across the Pacific toward the North...... period and spatial variations across more than 150 sampling locations in Europe made it possible to characterize the contaminated air masses. After the Chernobyl accident, only a few measurements of the gaseous 131I fraction were conducted compared to the number of measurements for the particulate...... reactors have provided a significant amount of new data on the ratio of the gaseous 131I fraction to total 131I, both on a spatial scale and its temporal variation. It can be pointed out that during the Fukushima event, the 134Cs to 137Cs ratio proved to be different from that observed after the Chernobyl...

  9. Fundamental Processes of Coupled Radiation Damage and Mechanical Behavior in Nuclear Fuel Materials for High Temperature Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Phillpot, Simon; Tulenko, James

    2011-09-08

    The objective of this work has been to elucidate the relationship among microstructure, radiation damage and mechanical properties for nuclear fuel materials. As representative nuclear materials, we have taken an hcp metal (Mg as a generic metal, and Ti alloys for fast reactors) and UO2 (representing fuel). The degradation of the thermo-mechanical behavior of nuclear fuels under irradiation, both the fissionable material itself and its cladding, is a longstanding issue of critical importance to the nuclear industry. There are experimental indications that nanocrystalline metals and ceramics may be more resistant to radiation damage than their coarse-grained counterparts. The objective of this project look at the effect of microstructure on radiation damage and mechanical behavior in these materials. The approach to be taken was state-of-the-art, large-scale atomic-level simulation. This systematic simulation program of the effects of irradiation on the structure and mechanical properties of polycrystalline Ti and UO2 identified radiation damage mechanisms. Moreover, it will provided important insights into behavior that can be expected in nanocrystalline microstructures and, by extension, nanocomposites. The fundamental insights from this work can be expected to help in the design microstructures that are less susceptible to radiation damage and thermomechanical degradation.

  10. Fundamental Processes of Coupled Radiation Damage and Mechanical Behavior in Nuclear Fuel Materials for High Temperature Reactors

    International Nuclear Information System (INIS)

    Phillpot, Simon; Tulenko, James

    2011-01-01

    The objective of this work has been to elucidate the relationship among microstructure, radiation damage and mechanical properties for nuclear fuel materials. As representative nuclear materials, we have taken an hcp metal (Mg as a generic metal, and Ti alloys for fast reactors) and UO2 (representing fuel). The degradation of the thermo-mechanical behavior of nuclear fuels under irradiation, both the fissionable material itself and its cladding, is a longstanding issue of critical importance to the nuclear industry. There are experimental indications that nanocrystalline metals and ceramics may be more resistant to radiation damage than their coarse-grained counterparts. The objective of this project look at the effect of microstructure on radiation damage and mechanical behavior in these materials. The approach to be taken was state-of-the-art, large-scale atomic-level simulation. This systematic simulation program of the effects of irradiation on the structure and mechanical properties of polycrystalline Ti and UO2 identified radiation damage mechanisms. Moreover, it will provided important insights into behavior that can be expected in nanocrystalline microstructures and, by extension, nanocomposites. The fundamental insights from this work can be expected to help in the design microstructures that are less susceptible to radiation damage and thermomechanical degradation.

  11. Law no. 6.453 of 17th October, 1977 on civil liability for nuclear damage and criminal responsibility for acts relating to nuclear activities, and other provisions

    International Nuclear Information System (INIS)

    1977-01-01

    This Act was published on 17 october 1977. Under the Act the operator of a nuclear installation is exclusively liable regardless of fault for compensation of nuclear damage due to a nuclear incident. This exclusive liability is limited to an amount equal to 1,500,000 Treasury Bonds and the operator must take out the maintain insurance or other financial security to cover his liability. The Federative Government will guarantee, up to the prescribed limit, payment of compensation for nuclear damage where it is acknowledged that the operator's liability is involved. As regards apportionment of compensation, persons are granted priority over property. This Act is original in that it contains provisions on criminal liability with penalties ranging from two to ten years imprisonment

  12. Three technical issues in fatigue damage assessment of nuclear power plant components

    International Nuclear Information System (INIS)

    Ware, A.G.; Shah, V.N.

    1991-01-01

    This paper addresses three technical issues that affect the fatigue damage assessment of nuclear power plant components: the effect of the environment on the fatigue life, the importance of the loading sequence in calculating the fatigue crack-initiation damage, and the adequacy of current inservice inspection requirements and methods to characterize fatigue cracks. The environmental parameters that affect the fatigue life of carbon and low alloy steel components are the sulphur content in the steel, the temperature, the amount of dissolved oxygen in the coolant, and the presence of oxidizing agents such as copper oxide. The occurrence of large-amplitude stress cycles early in a component's life followed by low-amplitude stress cycles may cause crack initiation at a cumulative usage factor less than 1.0. The current inservice inspection requirements include volumetric inspections of welds but not of some susceptible sites in the base metal. In addition, the conventional ultrasonic testing techniques need to be improved for reliable detection and accurate sizing of fatigue cracks. 28 refs., 4 figs., 1 tab

  13. Review of legislation on civil liability for nuclear damage; Revision de la legislacion relativa a la responsabilidad civil por danos nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Menendez-Moran, E.

    2011-07-01

    The entry into force of Law 12/2011 is postponed until the Protocols modifying the Paris and Brussels conventions take effect, since their content complements that of the Conventions. The most significant modifications are the extension of the suppositions of nuclear damage, the geographical scope of application and the time period for claiming personal damages, which is accompanied by higher coverage limits of up to 1,200 million euros. It also includes liability for damages caused by radioactive materials in the custody of the installation owner. (Author)

  14. Compensation for damages in case of a nuclear accident; L'indemnisation des prejudices en cas d'accident nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Leger, M. [CEA Saclay, 91 - Gif sur Yvette (France)

    2011-01-15

    This article presents the system of compensation for damages in case of a nuclear accident. This system of civil liability for nuclear damage, as a specific regime, departs on several points from the common rules of civil liability, in order to provide an adequate and equitable compensation for the damages suffered by the victims of nuclear accidents. The French system of civil liability for nuclear damage results from two International Conventions integrated in French law (Paris convention 1960 and Brussels convention 1963) and the French law of 1968, October 30 on civil liability in the area of nuclear energy. These texts define the conditions under which a nuclear operator could be held liable in case of a nuclear accident. The protocols to amend the Paris and Brussels Conventions of 2004, not yet come into force, are also presented. They ensure that increased resources are available to compensate a greater number of victims of a nuclear accident. (author)

  15. About the burial of nuclear power plants, damaged or in the process of decommissioning

    International Nuclear Information System (INIS)

    Elbrond, J.

    1994-01-01

    Some underground mining methods leave deep empty holes in the earth's surface behind them. In this paper it is described how to use such mining methods for the burial of damaged nuclear power plants and for the decommissioning by burial of nuclear reactors. The design of a new power plant should be integrated with that of an escapeway - an underground arrangement for burial. The described mining methods are block caving for catastrophy burial, and various stoping methods for planned burial and decommissioning. Blind shaft sinking by full face boring machines for burial and decommissioning of the reactor vessel is also described. All the described activities of mining and shaft sinking are well known. The total costs of burial by these methods are estimated using standard mining industry cost data. These include the costs for normal mine ventilation and groundwater control. However, the estimates of the cost and duration do not include the capital and operational costs of the pre- and post burial activities of ventilation and groundwater control related to the radioactivity. (author)

  16. Probabilistic approaches applied to damage and embrittlement of structural materials in nuclear power plants

    International Nuclear Information System (INIS)

    Vincent, L.

    2012-01-01

    The present study deals with the long-term mechanical behaviour and damage of structural materials in nuclear power plants. An experimental way is first followed to study the thermal fatigue of austenitic stainless steels with a focus on the effects of mean stress and bi-axiality. Furthermore, the measurement of displacement fields by Digital Image Correlation techniques has been successfully used to detect early crack initiation during high cycle fatigue tests. A probabilistic model based on the shielding zones surrounding existing cracks is proposed to describe the development of crack networks. A more numeric way is then followed to study the embrittlement consequences of the irradiation hardening of the bainitic steel constitutive of nuclear pressure vessels. A crystalline plasticity law, developed in agreement with lower scale results (Dislocation Dynamics), is introduced in a Finite Element code in order to run simulations on aggregates and obtain the distributions of the maximum principal stress inside a Representative Volume Element. These distributions are then used to improve the classical Local Approach to Fracture which estimates the probability for a microstructural defect to be loaded up to a critical level. (author) [fr

  17. Acetylation dynamics of human nuclear proteins during the ionizing radiation-induced DNA damage response

    DEFF Research Database (Denmark)

    Bennetzen, Martin; Andersen, J.S.; Lasen, D.H.

    2013-01-01

    Genotoxic insults, such as ionizing radiation (IR), cause DNA damage that evokes a multifaceted cellular DNA damage response (DDR). DNA damage signaling events that control protein activity, subcellular localization, DNA binding, protein-protein interactions, etc. rely heavily on time...

  18. Mycobacterium tuberculosis Ku can bind to nuclear DNA damage and sensitize mammalian cells to bleomycin sulfate.

    Science.gov (United States)

    Castore, Reneau; Hughes, Cameron; Debeaux, Austin; Sun, Jingxin; Zeng, Cailing; Wang, Shih-Ya; Tatchell, Kelly; Shi, Runhua; Lee, Kyung-Jong; Chen, David J; Harrison, Lynn

    2011-11-01

    Radiotherapy and chemotherapy are effective cancer treatments due to their ability to generate DNA damage. The major lethal lesion is the DNA double-strand break (DSB). Human cells predominantly repair DSBs by non-homologous end joining (NHEJ), which requires Ku70, Ku80, DNA-PKcs, DNA ligase IV and accessory proteins. Repair is initiated by the binding of the Ku heterodimer at the ends of the DSB and this recruits DNA-PKcs, which initiates damage signaling and functions in repair. NHEJ also exists in certain types of bacteria that have dormant phases in their life cycle. The Mycobacterium tuberculosis Ku (Mt-Ku) resembles the DNA-binding domain of human Ku but does not have the N- and C-terminal domains of Ku70/80 that have been implicated in binding mammalian NHEJ repair proteins. The aim of this work was to determine whether Mt-Ku could be used as a tool to bind DSBs in mammalian cells and sensitize cells to DNA damage. We generated a fusion protein (KuEnls) of Mt-Ku, EGFP and a nuclear localization signal that is able to perform bacterial NHEJ and hence bind DSBs. Using transient transfection, we demonstrated that KuEnls is able to bind laser damage in the nucleus of Ku80-deficient cells within 10 sec and remains bound for up to 2 h. The Mt-Ku fusion protein was over-expressed in U2OS cells and this increased the sensitivity of the cells to bleomycin sulfate. Hydrogen peroxide and UV radiation do not predominantly produce DSBs and there was little or no change in sensitivity to these agents. Since in vitro studies were unable to detect binding of Mt-Ku to DNA-PKcs or human Ku70/80, this work suggests that KuEnls sensitizes cells by binding DSBs, preventing human NHEJ. This study indicates that blocking or decreasing the binding of human Ku to DSBs could be a method for enhancing existing cancer treatments.

  19. Nuclear medicine in the detection of radiation associated normal tissue damage of kidney, brain and salivary glands

    International Nuclear Information System (INIS)

    Liu Xiaomei; Li Dongxue; Pan Liping

    2005-01-01

    The radiation induced damage of kidney, brain and salivary glands is an important complicating disease after limit radiotherapy. The routine technology of nuclear medicine, such as tracing and imaging technique conduce to dose-effect calculations used in the planning of modern radiotherapy to three major organ systems and early detection of irradiation induced organ dysfunctions, as well as increased availability of radiotherapy. (authors)

  20. Optional Protocol concerning the compulsory settlement of disputes to the Vienna Convention on civil liability for nuclear damage

    International Nuclear Information System (INIS)

    1999-01-01

    The document reproduces the text of the Optional Protocol Concerning the Compulsory Settlement of Disputes to the Vienna Convention on Civil Liability for Nuclear Damage which was adopted on 21 May 1963 by the International Conference held in Vienna from 29 April to 19 May 1963. It came into force on 13 May 1999

  1. TDP1 repairs nuclear and mitochondrial DNA damage induced by chain-terminating anticancer and antiviral nucleoside analogs

    Science.gov (United States)

    Huang, Shar-yin N.; Murai, Junko; Dalla Rosa, Ilaria; Dexheimer, Thomas S.; Naumova, Alena; Gmeiner, William H.; Pommier, Yves

    2013-01-01

    Chain-terminating nucleoside analogs (CTNAs) that cause stalling or premature termination of DNA replication forks are widely used as anticancer and antiviral drugs. However, it is not well understood how cells repair the DNA damage induced by these drugs. Here, we reveal the importance of tyrosyl–DNA phosphodiesterase 1 (TDP1) in the repair of nuclear and mitochondrial DNA damage induced by CTNAs. On investigating the effects of four CTNAs—acyclovir (ACV), cytarabine (Ara-C), zidovudine (AZT) and zalcitabine (ddC)—we show that TDP1 is capable of removing the covalently linked corresponding CTNAs from DNA 3′-ends. We also show that Tdp1−/− cells are hypersensitive and accumulate more DNA damage when treated with ACV and Ara-C, implicating TDP1 in repairing CTNA-induced DNA damage. As AZT and ddC are known to cause mitochondrial dysfunction, we examined whether TDP1 repairs the mitochondrial DNA damage they induced. We find that AZT and ddC treatment leads to greater depletion of mitochondrial DNA in Tdp1−/− cells. Thus, TDP1 seems to be critical for repairing nuclear and mitochondrial DNA damage caused by CTNAs. PMID:23775789

  2. Lightweight Damage Tolerant, High-Temperature Radiators for Nuclear Power and Propulsion

    Science.gov (United States)

    Craven, Paul D.; SanSoucie, Michael P.

    2015-01-01

    NASA is increasingly emphasizing exploration to bodies beyond near-Earth orbit. New propulsion systems and new spacecraft are being built for these missions. As the target bodies get further out from Earth, high energy density systems, e.g., nuclear fusion, for propulsion and power will be advantageous. The mass and size of these systems, including supporting systems such as the heat exchange system, including thermal radiators, will need to be as small as possible. Conventional heat exchange systems are a significant portion of the total thermal management mass and size. Nuclear electric propulsion (NEP) is a promising option for high-speed, in-space travel due to the high energy density of nuclear fission power sources and efficient electric thrusters. Heat from the reactor is converted to power for use in propulsion or for system power. The heat not used in the power conversion is then radiated to space as shown in figure 1. Advanced power conversion technologies will require high operating temperatures and would benefit from lightweight radiator materials. Radiator performance dictates power output for nuclear electric propulsion systems. Pitch-based carbon fiber materials have the potential to offer significant improvements in operating temperature, thermal conductivity, and mass. These properties combine to allow significant decreases in the total mass of the radiators and significant increases in the operating temperature of the fins. A Center-funded project at NASA Marshall Space Flight Center has shown that high thermal conductivity, woven carbon fiber fins with no matrix material, can be used to dissipate waste heat from NEP systems and because of high specific power (kW/kg), will require less mass and possibly less total area than standard metal and composite radiator fins for radiating the same amount of heat. This project uses an innovative approach to reduce the mass and size required for the thermal radiators to the point that in-space NEP and power

  3. Damage Curves of a Nuclear Reactor Structure exposed to Air Blast Loading

    International Nuclear Information System (INIS)

    Brandys, I.; Ornai, D.; Ronen, Y.

    2014-01-01

    Nuclear Power Plant (NPP) radiological hazards due to accidental failure or deliberated attacks are of most concern due to their destructive and global consequences: large area contaminations, injuries, exposure to ionizing radiation (which can cause death or illness, depends on the levels of exposure), loss of lives of both humans and animals, and severe damage to the environment. Prevention of such consequences is of a global importance and it has led to the definition of safety & design guidelines, and regulations by various authorities such as IAEA, U.S. NRC, etc. The guidelines define general requirements for the integrity of a NPP’s physical barriers (such as protective walls) when challenged by external events, for example human induced explosion. A more specific relation to the design of a NPP is that its structures and equipment (reactor building, fuel building, safeguards building, diesel-generator building, pumping station, nuclear auxiliaries building, and effluent treatment building) must function properly: shutdown the reactor, removal of decayed heat, storage of spent fuel, and treatment and containment of radioactive effluents) under external explosion. It requires that the NPP’s structures and equipment resistance to external explosion should be analyzed and verified. The air blast loading created by external explosion, as well as its effects & consequences on different kinds of structures are described in the literature. Structural elements response to the air blast can be analyzed in general by a Single Degree of Freedom (SDOF) system that converts a distributed mass, loads, and resistance to concentrated mass, force, and stiffness located at a representative point of the structure's element where the displacements are the highest one. Proper shielding should be designed if the explosion blast effects are greater than the resistance capacity.External explosion effects should be considered within the Screening Distance Value (SDV) of the NPP

  4. Preliminary analysis of an hydrogen generator system based on nuclear energy in the Laguna Verde site; Analisis preliminar de un sistema generador de hidrogeno basado en energia nuclear en el sitio de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Flores y Flores, A [FI-UNAM, 04500 Mexico D.F. (Mexico); Francois L, J L [FI-UNAM, Jiutepec, Morelos (Mexico)

    2003-07-01

    The shortage of fossil fuels in the next future, as well as the growing one demand of energetics and the high cost of the production of alternating fuels, it forces us to take advantage of to the maximum the fossil fuel with the one which we count and to look for the form of producing alternating fuels at a low cost and better even if these supply sources are reliable and non pollutants. It is intended a solution to the shortage of fuel; to use the thermal energy liberated of some appropriate nuclear reactor to be able to obtain a fuel but clean and relatively cheap as it is the hydrogen. In the first place the methods were looked for to produce hydrogen using thermal energy, later it was analyzed the temperature liberated by the existent nuclear reactors as well as the advanced designs, according to this liberated temperature settled down that the methods but feasible to produce hydrogen its were the one of reformed with water stream of the natural gas (methane) and the other one of the S-I thermochemical cycle, and the nuclear reactors that give the thermal energy for this production they are those of gas of high temperature. Once established the processes and the appropriate reactors, it was analyzed the site of Laguna Verde, with relationship to the free space to be able to place the reactor and the plant producer of hydrogen, as well as the direction in which blow the dominant winds and the near towns to the place, it was carried out an analysis of some explosion of tanks that could store hydrogen and the damage that its could to cause depending from the distance to which its were of the fire. Finally it was carried out an evaluation of capital and of operation costs for those two methods of hydrogen production. (Author)

  5. Radiation damage study in montmorillonites. Application to the high-level nuclear waste disposal in France

    International Nuclear Information System (INIS)

    Sorieul, St.

    2003-11-01

    Smectite is a major component of bentonite, a material considered for engineered barriers in high level nuclear wastes repositories (HLNWR). In order to predict the long-term performance of the bentonite, various physical and chemical factors such as, e.g., thermal gradient, redox potential or mechanical stresses are currently considered. By contrast, little is known about radiation effects in smectite, although it might affect the properties of this mineral through cumulative radiation damages produced by ionizing radiations. The present study focuses on radiation damage in montmorillonite considered herein as a simplified model of bentonite. Two reference clays have been selected, one from Liaoning (China, CHI), containing native radiation-induced defects, and the other (called MX) separated from the MX80 reference bentonite (Wyoming, USA). They are distinguished by layer composition, particularly iron content (1 % and 4 % for CHI and MX, respectively). Radiation effects have been studied by combining X-ray diffraction, Fourier transform infrared spectroscopy, Electron Paramagnetic Resonance (EPR) and Moessbauer spectroscopies. Ionizing irradiation induces two main effects. First, several paramagnetic point defects are identified as trapped holes located on oxygen atoms of the smectite structure. These defects are characterized by different thermal stabilities, according to annealing experiments. Their creation is limited by saturation curve with maximum damage around 100 MGy. The response of the two montmorillonites is different in terms of nature and production of point defects, indicating a role of layer composition and structural precursors. Besides, EPR and Moessbauer results show substantial modifications of the oxidation state of structural iron, which are sample and dose-dependent. Irradiation induces reduction and oxidation of iron in CHI and MX samples, respectively. Moreover, physico-chemical treatments show that intensity of redox effects varies

  6. Stochastic evaluation of the dynamic response and the cumulative damage of nuclear power plant piping

    International Nuclear Information System (INIS)

    Suzuki, Kohei; Aoki, Shigeru; Hanaoka, Masaaki

    1981-01-01

    This report deals with a fundamental study concerning an evaluation of uncertainties of the nuclear piping response and cumulative damage under excess-earthquake loadings. The main purposes of this study cover following several problems. (1) Experimental estimation analysis of the uncertainties concerning the dynamic response and the cumulative failure by using piping test model. (2) Numerical simulation analysis by Monte Carlo method under the assumption that relation between restoring force and deformation is characterized by perfectly elasto-plastic one. (Checking the mathematical model.) (3) Development of the conventional uncertainty estimating method by introducing a perturbation technique based on an appropriate equivalently linearized approach. (Checking the estimation technique.) (4) An application of this method to more realistical cases. Through above mentioned procedures some important results are obtained as follows; First, fundamental statistical properties of the natural frequencies and the number of cycle to failure crack initiation are evaluated. Second, the effect of the frequency fluctuation and the yielding fluctuation are estimated and examined through Monte Carlo simulation technique. It has become clear that the yielding fluctuation gives significant effect on the piping power response up to its failure initiation. Finally some results through proposed perturbation technique are discussed. Statistical properties estimated coincide fairly well with those through numerical simulation. (author)

  7. Long-term prediction of corrosion damage in nuclear waste systems

    International Nuclear Information System (INIS)

    Hidekazu Asano; Feron, Damien; Gens, Robert; Padovani, Cristiano; Naoki Taniguchi

    2014-01-01

    Complete text of publication follows: The Fifth International Workshop on Long-Term Prediction of Corrosion Damage in Nuclear Waste Systems was held at the Taisetsu Crystal Hall in Asahikawa, Hokkaido, Japan from October 6 to 10, 2013, following the four previous successful workshops (Cadarache, France, 2001; Nice, France, 2004; Pennsylvania State University, USA, 2007 and Bruges, Belgium, 2010). It was organised by the Japan Society of Corrosion Engineering (JSCE) and supported by the European Federation of Corrosion (EFC): Nuclear Corrosion Working Party (WP4) as of EFC event No.360. Furthermore, it was supported by the Division of Nuclear Fuel Cycle and Environment (NUCE) of the Atomic Energy Society of Japan (AESJ) and The Japan Society of Mechanical Engineers (JSME). Twenty nine (29) oral presentations were distributed among eleven (11) sessions covering a broad range of subjects. Another twenty eight (28) studies were presented at a poster session. A total of sixty seven (67) participants from twelve (12) countries attended the event. The presentations and the following discussion provided contextual information about the state of some national programmes and covered in detail a range of experimental and modelling studies aimed at evaluating the corrosion behaviour of a range of candidate materials and designs for the storage and disposal of radioactive wastes considered across the globe. These included modelling studies aimed at evaluating the durability of container designs for high level waste (HLW), spent nuclear fuel (SNF) and intermediate level waste (ILW), experimental studies of the corrosion behaviour of copper, carbon steel, and stainless steel in conditions relevant to storage (atmospheric) or disposal (near neutral or alkaline), as well as studies of archaeological artifacts and natural analogues aimed at supporting long-term predictions. Specific sessions were dedicated to microbial induced corrosion (MIC) and to the corrosion properties of

  8. A role for nuclear translocation of tripeptidyl-peptidase II in reactive oxygen species-dependent DNA damage responses

    Energy Technology Data Exchange (ETDEWEB)

    Preta, Giulio; Klark, Rainier de [Center for Molecular Medicine (CMM), Department of Medicine, Karolinska Institutet, Karolinska University Hospital, 171 76 Stockholm (Sweden); Glas, Rickard, E-mail: rickard.glas@ki.se [Center for Molecular Medicine (CMM), Department of Medicine, Karolinska Institutet, Karolinska University Hospital, 171 76 Stockholm (Sweden)

    2009-11-27

    Responses to DNA damage are influenced by cellular metabolism through the continuous production of reactive oxygen species (ROS), of which most are by-products of mitochondrial respiration. ROS have a strong influence on signaling pathways during responses to DNA damage, by relatively unclear mechanisms. Previous reports have shown conflicting data on a possible role for tripeptidyl-peptidase II (TPPII), a large cytosolic peptidase, within the DNA damage response. Here we show that TPPII translocated into the nucleus in a p160-ROCK-dependent fashion in response to {gamma}-irradiation, and that nuclear expression of TPPII was present in most {gamma}-irradiated transformed cell lines. We used a panel of nine cell lines of diverse tissue origin, including four lymphoma cell lines (T, B and Hodgkins lymphoma), a melanoma, a sarcoma, a colon and two breast carcinomas, where seven out of nine cell lines showed nuclear TPPII expression after {gamma}-irradiation. Further, this required cellular production of ROS; treatment with either N-acetyl-Cysteine (anti-oxidant) or Rotenone (inhibitor of mitochondrial respiration) inhibited nuclear accumulation of TPPII. The local density of cells was important for nuclear accumulation of TPPII at early time-points following {gamma}-irradiation (at 1-4 h), indicating a bystander effect. Further, we showed that the peptide-based inhibitor Z-Gly-Leu-Ala-OH, but not its analogue Z-Gly-(D)-Leu-Ala-OH, excluded TPPII from the nucleus. This correlated with reduced nuclear expression of p53 as well as caspase-3 and -9 activation in {gamma}-irradiated lymphoma cells. Our data suggest a role for TPPII in ROS-dependent DNA damage responses, through alteration of its localization from the cytosol into the nucleus.

  9. Harmonization of the Romanian legislation in the field of civil liability for nuclear damages with the international legislation in the field

    International Nuclear Information System (INIS)

    Chiripus, Vlad

    2005-01-01

    The paper is an overview of the Romanian legal provisions in the filed of civil liability for nuclear damages in the last three decades introducing the concept and the evolution of its legal regime towards a total harmonization with the European legislation. Its modernity even from (and in spite of) its communist beginnings in 1947 (Law no. 61 regarding the deployment of nuclear activities in the Romanian Socialist Republic) is emphasized. It focuses on the key laws - Law no. 703/2001 on civil liability for nuclear damages, and Government Decision no. 894/2003 for the approval of the Norms for enforcement of Law no. 703/2001- that currently define the Romanian regime for civil liability for nuclear damages. This encompasses the relevant responsibilities of nuclear operators, the Romanian nuclear damage compensation system, statute of limitation for claims, types of insurance and financial guarantees. These refer civil liability for nuclear damages, limits of nuclear operators' liability, specific requirements regarding the insurance, responsibilities of control and supervision bodies, assessment of nuclear damage. This makes Romania - in terms of legislation - one of the most advanced countries in the field. (author)

  10. ANALISIS PENYEBAB BANJIR KALI JUANA

    Directory of Open Access Journals (Sweden)

    Teguh Marhendi

    2017-04-01

    Full Text Available Kali Juana yang berada di Kabupaten Pati dan Kudus serta sebagian kecil di Kabupaten Grobogan dan Blora, merupakan kawasan banjir. Kejadian banjir di Kali Juana, sudah menjadi rutinitas setiap musim hujan.Dari Januari sampai bulan Mei 2016tercatat terjadi 11 kejadian banjir dibeberapa wilayah, seperti Kecamatan Kaliwungu, Undaan dan Mejobo (Kab. Kudus serta Pati, Margorejo dan Juwana (Kab. Pati. Kali Juana merupakan bifurkasi Kali Serang pada Pintu Wilalung, yang berfungsi sebagai pintu pengatur banjir (dibangun pada zaman Belanda tahun 1918, melalui Kali Babalan menuju ke Kali Juana. Tulisan inidimaksudkan untuk menganalisis penyebab kejadian banjir di Kali Juana. Analisis dilakukan dengan melakukan kajani dan analisis hujan serta mekanisme aliran. Hasil analisis menunjukkan bahwa kondisi Kali Juana dari pertemuan Kali Logung di pintu Wilalung sampai hilir telah mengalami pendangkalan akibat kemiringan dasar atau topografi yang landai, dan mengakibatkan mudah terjadi sedimentasi sehingga mengurangi kapasitas pengaliran. Hal ini menyebabkan luapan banjir sering menggenangi wilayah Kabupaten Kudus dan Pati.

  11. Nuclear magnetic resonance analysis of freeze-thaw damage in natural pumice concrete

    Directory of Open Access Journals (Sweden)

    Wang, Xiaoxiao

    2016-06-01

    Full Text Available This paper presents an analysis of the damage propagation features of the pore structure of natural pumice lightweight aggregate concrete (LWC under freeze-thaw cyclic action. After freeze-thaw cycling, we conducted nuclear magnetic resonance (NMR tests on the concrete and acquired the porosity, distribution of transverse relaxation time T2, and magnetic resonance imaging (MRI results. The results showed the following. The T2 distribution of the LWC prior to freeze-thaw cycling presented four peaks representative of a preponderance of small pores. After 50, 100, 150, and 200 freeze-thaw cycles, the total area of the T2 spectrum and the porosity increased significantly. The MRI presented the changing spatial distribution of pores within the LWC during freeze-thaw cycling. Ultrasonic testing technology was applied simultaneously to analyze the NMR results, which verified that the new NMR technology demonstrated high accuracy and practicability for research regarding freeze-thaw concrete damage.En este trabajo se analiza la propagación de los daños que se producen en la estructura porosa de hormigón aligerado a base de piedra pómez natural sometido a la acción cíclica de hielo-deshielo. Después de realizarse los ensayos de hielo-deshielo, el hormigón se analizó mediante resonancia magnética nuclear (RMN, determinándose la porosidad y la distribución del tiempo de relajación transversal, T2, y registrándose las imágenes captadas por resonancia magnética. De acuerdo con los resultados obtenidos, antes de los ciclos de hielo-deshielo la distribución de T2 del hormigón aligerado presentaba cuatro picos, indicativos de un predominio de poros pequeños. Después de que se sometiera a 50, 100, 150, y 200 ciclos, se observó un aumento importante tanto de la porosidad como de la superficie total del espectro de T2. Las imágenes captadas por resonancia magnética evidenciaron la modificación de la distribución espacial de los poros del

  12. Metallographic examination of damaged N reactor spent nuclear fuel element SFEC5,4378

    Energy Technology Data Exchange (ETDEWEB)

    Marschman, S.C.; Pyecha, T.D.; Abrefah, J.

    1997-08-01

    N-Reactor spent nuclear fuel (SNF) is currently residing underwater in the K Basins at the Hanford site, in Richland, Washington. This report presents results of the metallographic examination of specimens cut from an SNF element (Mark IV-E) with breached cladding. The element had resided in the K-West (KW) Storage Basin for at least 10 years after it was discharged from the N-Reactor. The storage containers in the KW Basin were nominally closed, isolating the SNF elements from the open pool environment. Seven specimens from this Mark IV-E outer fuel element were examined using an optical metallograph. Included were two specimens that had been subjected to a conditioning process recommended by the Independent Technical Assessment Team, two specimens that had been subjected to a conditioning process recommended in the Integrated Process Strategy Report, and three that were in the as-received, as-cut condition. One of the as-received specimens had been cut from the damaged (or breached) end of the element. All other specimens were cut from the undamaged mid-region of the fuel element. The specimens were visually examined to (1) identify uranium hydride inclusions present in the uranium metal fuel, (2) measure the thickness of the oxide layer formed on the uranium edges and assess the apparent integrity and adhesion of the oxide layer, and (3) look for features in the microstructure that might provide an insight into the various corrosion processes that occurred during underwater storage in the KW Basin. These features included, but were not limited to, the integrity of the cladding and the fuel-to-cladding bond, obvious anomalies in the microstructure, excessive pitting or friability of the fuel matrix, and obvious anomalies in the distribution of uranium hydride or uranium carbide inclusions. Also, the observed metallographic features of the conditioned specimens were compared with those of the as-received (unconditioned) specimens. 11 refs., 93 figs., 2 tabs.

  13. ANALISIS LITERASI EKONOMI

    Directory of Open Access Journals (Sweden)

    Peter Garlans Sina

    2012-10-01

    Full Text Available Abstract: Analysis of Economic Literacy. The aim of this research is as an effort to increase economic literacy for individuals and households who want to achieve prosperity. Therefore, the obligation of improving the economic literacy needs to be done in a well-planned manner and come from the strong intention to learn in order to improve the economic literacy. It could have an effect on the assets accumulation, a better debt management, as a protection, as well as to increase savings and managing spending intelligently.   Keyword: economic literacy, asset, debt, protection, saving, spending   Abstrak: Analisis Literasi Ekonomi. Tulisan ini bertujuan sebagai upaya meningkatkan literasi ekonomi bagi individu maupun rumah tangga yang menginginkan mencapai kesejahteraan. Oleh karena itu, kewajiban meningkatkan literasi ekonomi perlu dilakukan secara terencana dan diawali dari niat untuk belajar meningkatkan literasi ekonomi karena dapat berefek pada akumulasi aset, pengelolaan utang yang tepat, proteksi, meningkatkan tabungan dan cerdas mengelola pengeluaran.   Kata kunci: literasi ekonomi, aset, utang, proteksi, menabung, pengeluaran

  14. The alkaline comet assay as a biomarker of primary DNA damage in peripheral blood leukocytes of nuclear medicine personnel

    International Nuclear Information System (INIS)

    Kopjar, N.; Garaj-Vrhovac, V.

    2003-01-01

    The aim of this study was to assess whether occupational exposure to chronic low doses of ionizing radiation in nuclear medicine departments may lead to genotoxicity. The alkaline comet assay was selected as a bio-marker of exposure to evaluate the levels of primary DNA damage in peripheral blood leukocytes of exposed and corresponding control subjects. Statistically significant differences were found between comet tail length and tail moment values measured in leukocytes from the exposed and control groups. Within exposed group significant inter-individual differences in DNA damage were assessed, indicating different genome sensitivity. In majority of exposed subjects the levels of DNA damage were in positive correlation with the duration of occupational exposure, while the influences of age and dosimeter readings could be excluded. However, the levels of primary DNA damage detected both in control and exposed subjects were significantly influenced by smoking. The present study indicates the possibility of genotoxic risks related to occupational exposure in nuclear medicine departments. Therefore, the exposed personnel should carefully apply the radiation protection procedures to minimize, as low as possible, radiation exposure to avoid possible genotoxic effects. According to results obtained, the alkaline comet assay could be usefully applied as a sensitive additional bio-marker in the regular health screening of workers occupationally exposed to low doses of ionizing radiation. (authors)

  15. 75 FR 43945 - Convention on Supplementary Compensation for Nuclear Damage Contingent Cost Allocation

    Science.gov (United States)

    2010-07-27

    ... of nuclear power around the world to meet the challenges of climate change, energy security, and... than power reactors having a thermal power rating of over 300 Megawatts. Also, nuclear facilities other... United States nuclear reactor operators. 934(a)(1). \\3\\ The Price-Anderson Act (``Price-Anderson'' or...

  16. Co-visualization of DNA damage and ion traversals in live mammalian cells using a fluorescent nuclear track detector

    International Nuclear Information System (INIS)

    Kodaira, Satoshi; Konishi, Teruaki; Kobayashi, Alisa

    2015-01-01

    The geometric locations of ion traversals in mammalian cells constitute important information in the study of heavy ion-induced biological effect. Single ion traversal through a cellular nucleus produces complex and massive DNA damage at a nanometer level, leading to cell inactivation, mutations and transformation. We present a novel approach that uses a fluorescent nuclear track detector (FNTD) for the simultaneous detection of the geometrical images of ion traversals and DNA damage in single cells using confocal microscopy. HT1080 or HT1080–53BP1-GFP cells were cultured on the surface of a FNTD and exposed to 5.1-MeV/n neon ions. The positions of the ion traversals were obtained as fluorescent images of a FNTD. Localized DNA damage in cells was identified as fluorescent spots of γ-H2AX or 53BP1-GFP. These track images and images of damaged DNA were obtained in a short time using a confocal laser scanning microscope. The geometrical distribution of DNA damage indicated by fluorescent γ-H2AX spots in fixed cells or fluorescent 53BP1-GFP spots in living cells was found to correlate well with the distribution of the ion traversals. This method will be useful for evaluating the number of ion hits on individual cells, not only for micro-beam but also for random-beam experiments. (author)

  17. Scoping of material damage with FISPACT-II and different nuclear data libraries: transmutation, activation, and PKAs

    International Nuclear Information System (INIS)

    Gilbert, M.R.; Sublet, J.-Ch.

    2016-01-01

    The uncertainty associated with nuclear data, and the simulated predictions of transmutation, activation, and primary damage events derived from them, is not only that derived based on the quantified errors in a particular nuclear library. Uncertainty also manifests in comparisons between different libraries – if they do not produce the same results, then, since it often impossible to know a priori which library is best, predicted results must be considered to have an uncertainty (at least) as much as the variation between libraries. Of course, this situation is further complicated by the fact that it is not always possible, or practical, to produce results with multi-libraries. There is thus a need, within the nuclear data community, to assess different libraries, and make recommendations about the best choice of library for particular applications, in this case material science

  18. IAEA advisory group meeting on nuclear data for radiation damage assessment and related safety aspects, Vienna, 12-16 October 1981

    International Nuclear Information System (INIS)

    Kocherov, N.

    1982-01-01

    This Advisory Group Meeting on Nuclear Data for Radiation Damage Assessment and Related Safety Aspects was convened by the IAEA Nuclear Data Section, at IAEA Headquarters in Vienna, Austria, from 12-16 October 1981. The meeting was attended by 34 participants from 15 countries and 2 international organizations. The main objective of the meeting was to review the requirements for and the status of nuclear data needed for radiation damage estimates in reactor structural materials and related reactor safety aspects, and to develop recommendations to the Nuclear Data Section of the IAEA for its future activities in this field. (author)

  19. The Chernobyl case: its repercussions on the International System on Civil Liability for Nuclear Damages

    International Nuclear Information System (INIS)

    Gonzalez Guadarrama, J.L.

    1992-01-01

    With the discovery of the Nuclear Energy the world has been development her life the present investigation is based in the accident of the one of the most important Nuclear Power Plant in the world, situated in the Union of Socialist Sovietic Republics. The Nuclear Power Plant of Chernobyl. Us found in the investigation what not exist one legislation agree with the needs of development of the actual world in matter of the liability civil in case of the nuclear accidents. Found only the Convention of the Vienna. the Convention of the Brussels the which only cover the transportation the Nuclear substances in ships and others transportation medios. The complementary a the convention of the Paris and actually The Communication in case of the nuclear accidents and radiological accidents. In the present work think what the Community International haven the needs of created one legislation with character international what can help a the many countries what have Nuclear Power Plants, on all for protection of the her habitants. The International Atomic Energy Agency together with the International Justice Court and the United Nations Organization (U.N.O.) aplicated the law in matter of the nuclear accidents derivates of the liability responsibility in the use of the Nuclear Plants for elaboration the Electrical Energy or for Investigation in matter the nuclear energy both with identical responsibility civil in case the nuclear accident. (Author)

  20. Damage of the Unit 1 reactor building overhead bridge crane at Onagawa Nuclear Power Station caused by the Great East Japan Earthquake and its repair works

    International Nuclear Information System (INIS)

    Sugamata, Norihiko

    2014-01-01

    The driving shaft bearings of the Unit 1 overhead bridge crane were damaged by the Great East Japan Earthquake at Onagawa Nuclear Power Station. The situation, investigation and repair works of the bearing failure are introduced in this paper. (author)

  1. Vienna convention on civil liability for nuclear damage. Signatures, ratifications, accessions and successions and text of reservations/declarations. Status as of 31 December 1996

    International Nuclear Information System (INIS)

    1997-01-01

    The document refers to the Vienna Convention on Civil Liability for Nuclear Damage (IAEA-INFCIRC-500), giving the status of signatures, ratifications, accessions and successions, and the texts of reservations/declarations as of 31 December 1996

  2. Vienna convention on civil liability for nuclear damage. Signatures, ratifications, accessions and successions and text of reservations/declarations. Status as of 31 December 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-28

    The document refers to the Vienna Convention on Civil Liability for Nuclear Damage (IAEA-INFCIRC-500), giving the status of signatures, ratifications, accessions and successions, and the texts of reservations/declarations as of 31 December 1996.

  3. PENERAPAN ANALISIS SWOC DALAM RENCANA STRATEGIS PENDIDIKAN

    Directory of Open Access Journals (Sweden)

    Hardianto -

    2018-01-01

    Full Text Available Analisis SWOC merupakan salah satu langkah yang bisa diambil dalam membuat sebuah rencana strategis pendidikan. Analisis ini dilakukan untuk melihat secara mendalam situasi internal dan eksternal organisasi. Situasi internal yang dilihat adalah kekuatan (Strenghts dan kelemahan (Weaknesses organisasi pendidikan. Situasi eksternal berupa peluang (Opportinities dan tantangan (Challenges. Untuk membuat sebuah rencana strategis yang baik dapat dilakukan dengan menganalisis setiap kekuatan, kelemahan, peluang dan tantangan. Teknik kartu salju (snow card bisa digunakan dalam melakukan analisis SWOC. Hasil analisis tersebut nantinya akan melahirkan kombinasi strategi kekuatan-peluang, kekuatan-tantangan, kelemahan-peluang dan kelemahan-tantangan.

  4. Evaluation of nuclear power plant component failure probability and core damage probability using simplified PSA model

    International Nuclear Information System (INIS)

    Shimada, Yoshio

    2000-01-01

    It is anticipated that the change of frequency of surveillance tests, preventive maintenance or parts replacement of safety related components may cause the change of component failure probability and result in the change of core damage probability. It is also anticipated that the change is different depending on the initiating event frequency or the component types. This study assessed the change of core damage probability using simplified PSA model capable of calculating core damage probability in a short time period, which is developed by the US NRC to process accident sequence precursors, when various component's failure probability is changed between 0 and 1, or Japanese or American initiating event frequency data are used. As a result of the analysis, (1) It was clarified that frequency of surveillance test, preventive maintenance or parts replacement of motor driven pumps (high pressure injection pumps, residual heat removal pumps, auxiliary feedwater pumps) should be carefully changed, since the core damage probability's change is large, when the base failure probability changes toward increasing direction. (2) Core damage probability change is insensitive to surveillance test frequency change, since the core damage probability change is small, when motor operated valves and turbine driven auxiliary feed water pump failure probability changes around one figure. (3) Core damage probability change is small, when Japanese failure probability data are applied to emergency diesel generator, even if failure probability changes one figure from the base value. On the other hand, when American failure probability data is applied, core damage probability increase is large, even if failure probability changes toward increasing direction. Therefore, when Japanese failure probability data is applied, core damage probability change is insensitive to surveillance tests frequency change etc. (author)

  5. Damage-Tolerant, Lightweight, High-Temperature Radiator for Nuclear Powered Spacecraft

    Data.gov (United States)

    National Aeronautics and Space Administration — Game-changing propulsion systems are often enabled by novel designs using advanced materials. Radiator performance dictates power output for nuclear electric...

  6. Necessity of radiation education suggested from press report during earthquake damage of Kashiwazaki-Kariwa Nuclear Power Station

    International Nuclear Information System (INIS)

    Hamamoto, Kazuko; Narabayashi, Tadashi; Itami, Toshio; Kobayashi, Masahide; Akizuki, Teruo; Onishi, Hidetoshi

    2009-01-01

    Although Kashiwazaki-Kariwa Nuclear Power Station was affected by Chuetsu-Oki earthquake, the important components in the reactor building were hardly damaged, and fundamental nuclear safety was ensured. However, as the mass communication media reported the pictures of the black smoke of fire accident of the transformer, sloshing of the pool, etc. without declaration of 'Safety' by the Central Government or sufficient explanation, the habitants on the site and the Japan's people were put into anxiety and thus, harmful rumor was spread. The people obtain the information from the mass communication media, and they believed all the reports of the mass media. Behind it, there is a fundamental knowledge among them that Radiation = 'dangerous', 'bad for health' and 'awful' = Nuclear Power Generation. This knowledge has been fixed more firmly due to the report of the earthquake damage. In order to escape from this deep-rooted scheme, it is necessary to spread the correct knowledge on the radiation. At this time, the Official Curriculum Guidelines for Junior High School are revised, and the radiation education is started for the first time in 30 years. We analyzed and evaluated the results of the survey performed by Radiation Education Forum, and, simultaneously, we considered the necessity of the radiation education judging from the reports of the mass communication media. (author)

  7. Applications of seismic damage hazard analysis for the qualification of existing nuclear and offshore facilities

    International Nuclear Information System (INIS)

    Bazzurro, P.; Manfredini, G.M.; Diaz Molina, I.

    1995-01-01

    The Seismic Damage Hazard Analysis (SDHA) is a methodology which couples conventional Seismic Hazard Analysis (SHA) and non-linear response analysis to seismic loadings. This is a powerful tool in the retrofit process: SDHA permits the direct computation of the probability of occurrence of damage and, eventually, collapse of existing and upgraded structural systems. The SDHA methodology is a significant step towards a better understanding and quantification of structural seismic risk. SDHA incorporates and explicitly accounts for seismic load variability, seismic damage potential variability and structural resistance uncertainty. In addition, SDHA makes available a sound strategy to perform non-linear dynamic analyses. A limited number of non-linear dynamic analyses is sufficient to obtain estimates of damage and its probability of occurrence. The basic concepts of the SDHA methodology are briefly reviewed. Illustrative examples are presented, regarding a power house structure, a tubular structure and seabed slope stability problem. (author)

  8. Account of the effect of nuclear collision cascades in model of radiation damage of RPV steels

    International Nuclear Information System (INIS)

    Kevorkyan, Yu.R.; Nikolaev, Yu.A.

    1997-01-01

    A kinetic model is proposed for describing the effect of collision cascades in model of radiation damage of reactor pressure vessel steels. This is a closed system of equations which can be solved only by numerical methods in general case

  9. Indemnification of damage to the environment caused by non-nuclear industrial activities

    International Nuclear Information System (INIS)

    Smets, H.

    1985-01-01

    Environmental damage has reached catastrophic proportions, implying the death of hundreds of people or expenses of many hundreds of million dollars. The financial impact of this damage is however small at the level of the industrial sector concerned which could bear its costs. If States would take measures to redistribute such costs, they would avoid having to compensate victims of the gravest accidents. Special procedures were introduced for this purpose in certain industrial sectors. (NEA) [fr

  10. The order for enforcing the law on indemnity agreement for compensation of nuclear damage

    International Nuclear Information System (INIS)

    1987-01-01

    This report shows the Cabinet Order No.46 of March 6, 1962. The Order consists of eleven Articles. The provisions under Article 1 and Article 2 specify requirements for conforming to the Law concerning Contract for Compensation and Indemnity for Nuclear Energy Loss. The provisions under Article 3 provide for the compensation premium rate (5/10,000). Data to be reported to the government are given under Article 4. Such data include purpose, type and thermal output of the reactor; location and structure of the nuclear reactor facilities; arrangements in the nuclear reactor facilities; plan for operation of the nuclear reactor; type and yearly amount of nuclear fuel substances used; method for disposal of spent fuel; matters concerning contract for liability insurance; location, structure, etc. of processing facilities, reprocessing facilities and waste disposal facilities; route and method for transporting materials contaminated with nuclear source materials or nuclear fuel substances; etc. Managers of nuclear energy business should pay the security money every year, which goes to the national treasury. (Nogami, K.)

  11. Analisis Cadangan Devisa Indonesia

    Directory of Open Access Journals (Sweden)

    Lusia Bunga Uli

    2016-09-01

    Full Text Available Abstract This study aims to determine the relationship between variables export, import, and exchange rate against Foreign Exchange Reserves in Indonesia. The data used in the empirical study of a sequence of data monthly time of year 2011.01 through 2014.12 from Bank Indonesia and the Central Statistics Agency (BPS. The analysis tool used is Auto Regression Vector Model (VAR. The results of this study indicate that the one-way relationship between the variables of foreign reserves and export. Then one-way relationship between exchange rate and exports. Lastly, there is a two-way relationship between imports and foreign exchange reserves, two-way relationship between exchange rate and foreign exchange reserves, two-way relationship between imports and exports, two-way relationship between the exchange rate and imports. The results also showed foreign exchange reserves are significantly influenced by the movement itself at a probability of 1 %. Export variable negative and not significantly affect the foreign exchange reserves. While imports of positive and not significant to the foreign exchange reserves. Foreign Exchange Reserves Indonesia is positively influenced by the exchange rate and not significant. Keywords: Foreign exchange reserves, exports, imports, exchange rate   Abstrak. Penelitian ini bertujuan untuk mengetahui seberapa keterkaitan antar variabel ekspor, impor, dan nilai tukar rupiah terhadap Cadangan Devisa Indonesia. Data yang digunakan dalam kajian empiris ini merupakan data runtutaan waktu bulanan dari tahun 2011.01 sampai 2014. 12 yang berasal dari Bank Indonesia dan Badan Pusat Statistik (BPS. Alat analisis yang digunakan yaitu Vector Autoregression Model (VAR. Hasil dari penelitian ini menunjukkan bahwa hubungan searah antara variabel cadangan devisa ke ekspor. Lalu hubungan searah antara kurs terhadap ekspor Terakhir, terdapat hubungan dua arah antara impor dan cadangan devisa, hubungan dua arah antara kurs dan cadangan

  12. Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Apendices

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A; Lopez M, R [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1995-07-01

    This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)

  13. Federal Act of 29 April 1964 on Liability for Nuclear Damage (Atomic Liability Act)

    International Nuclear Information System (INIS)

    Under this Act, the operator of a nuclear installation is liable for any nuclear incident occurring in such installation or which is caused by nuclear substances in his charge. If an incident is caused by a radioisotope, the person in possession of the radioisotope at the time of the incident is liable therefore. When an incident occurs during transport of nuclear substances, the carrier is liable in three cases only: when such substances are neither despatched to nor originating from installations on Austrian territory; when they are despatched without the written consent of the Austrian operator who is to receive them; and when they are not destined for a nuclear installation. Other provisions of the Act fix liability ceilings, a basis for apportionment of compensation when several victims are involved and the amount of security for coverage of the operators liability. The Act came into force on 1 September 1964. (NEA) [fr

  14. Ion-irradiation-induced damage in nuclear materials: Case study of a-SiO2 and MgO

    International Nuclear Information System (INIS)

    Bachiller-Perea, Diana

    2016-01-01

    One of the most important challenges in Physics today is the development of a clean, sustainable, and efficient energy source that can satisfy the needs of the actual and future society producing the minimum impact on the environment. For this purpose, a huge international research effort is being devoted to the study of new systems of energy production; in particular, Generation IV fission reactors and nuclear fusion reactors are being developed. The materials used in these reactors will be subjected to high levels of radiation, making necessary the study of their behavior under irradiation to achieve a successful development of these new technologies. In this thesis two materials have been studied: amorphous silica (a-SiO 2 ) and magnesium oxide (MgO). Both materials are insulating oxides with applications in the nuclear energy industry. High-energy ion irradiations have been carried out at different accelerator facilities to induce the irradiation damage in these two materials; then, the mechanisms of damage have been characterized using principally Ion Beam Analysis (IBA) techniques. One of the challenges of this thesis was to develop the Ion Beam Induced Luminescence or iono-luminescence (which is not a widely known IBA technique) and to apply it to the study of the mechanisms of irradiation damage in materials, proving the power of this technique. For this purpose, the iono-luminescence of three different types of silica (containing different amounts of OH groups) has been studied in detail and used to describe the creation and evolution of point defects under irradiation. In the case of MgO, the damage produced under 1.2 MeV Au + irradiation has been characterized using Rutherford backscattering spectrometry in channeling configuration and X-ray diffraction. Finally, the iono-luminescence of MgO under different irradiation conditions has also been studied.The results obtained in this thesis help to understand the irradiation-damage processes in materials

  15. Economic analysis of extended cycles in the Laguna Verde nuclear power plant; Analisis economico de ciclos de extendidos en la Central Nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez N, H.; Hernandez M, J.L.; Francois L, J.L. [Facultad de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico)]. E-mail: hermilo@correo.unam.mx

    2004-07-01

    The present work presents a preliminary analysis of economic type of extended cycles of operation of the Unit One in the Laguna Verde nuclear power plant. It is analysed an equilibrium cycle of 18 months firstly, with base to the Plan of Use of Energy of the Federal Commission of Electricity, being evaluated the cost of the energy until the end of the useful life of the plant. Later on an alternative recharge scenario is presented with base to an equilibrium cycle of 24 months, implemented to the beginning of the cycle 11, without considering transition cycles. It is added in both cycles the cost of the substitution energy, considering the unitary cost of the fuel of a dual thermoelectric power station of 350 M We and evaluating in each operation cycle, in both scenarios, the value of the substitution energy. The results show that a reduction of the days of recharge in the cycle of 24 months could make this option but favorable economically. The duration of the period of recharge rebounds in considerable grade in the cost of energy generation for concept of fuel. (Author)

  16. Use of classical criterions of a decision making for choice of measures on decrease of economic damage from nuclear and radiation accidents

    International Nuclear Information System (INIS)

    Rylov, M.I.; Kamynov, Sh.V.; Mozhaev, A.S.; Anisimov, N.A.; Nikitin, V.S.

    2004-01-01

    Application of classical criteria of decision making for choice of measures on the decrease of economic damage from possible nuclear and radiation accidents during spent fuel unloading from nuclear submarines and storage in the process of their utilization was demonstrated. Economic damage was chosen as optimization index, three versions of possible accidents and limited number of measures on the decrease of their effect were treated for illustration of the suggested approach. On the base of analysis of classical criteria the optimal strategy for decrease of economic damage was chosen [ru

  17. The nuclear accident of Fukushima Daiichi - Management of contaminated waters from damaged reactors. Situation at the end of June 2103

    International Nuclear Information System (INIS)

    2013-01-01

    This report first describes the water accumulation and continuous flow in buildings of the Fukushima nuclear power station. This water has different origins: some was used to cool the damaged reactors, and some comes from the underground. Waters under buildings must to pumped, processed and stored. The report describes the main objectives of water processing (desalinating and partial removal of radionuclides) and how they are addressed by Tepco. The last part briefly describes how and where Tepco is storing this always increasing volume of processed waters, with of course other water-tightness problems

  18. Act No. 732 of December 7, 1988. Act to amend the Act on civil liability for nuclear damage

    International Nuclear Information System (INIS)

    1988-01-01

    This Act amends Act No. 332 of June 19, 1974 on civil liability for nuclear damage, enabling Denmark to ratify the 1982 Protocols to amend the Paris Convention and the Brussels Supplementary Convention as well as the 1988 Joint Protocol relating to the application of the Vienna and the Paris Convention. The 1988 Act raises the nuclear operator's liability from 75 million DKr to 60 million SDRs while cover involving State funds is raised from 120 million units of account to 300 million SDRs. The Act entered into force on July 1, 1989 except for the provision on State funds which becomes effective when the 1982 Protocol amending the Brussels Convention comes into force. (NEA) [fr

  19. Analisis Semiotik Sajak Bulang Cahaya

    Directory of Open Access Journals (Sweden)

    Junaidi Junaidi

    2014-11-01

    Full Text Available Penelitian ini bertujuan menggali makna tanda yang terdapat dalam sajak Bulang Cahaya karya Rida K Liamsi. Untuk menggali makna itu, pendekatan analisis semiotik Roland Barthes digunakan. Hasil penelitian menunjukkan bahwa sajak ini berisi tanda-tanda bersumber dari kosa kata Melayu lama. Sajak ini juga berisi simbol-simbol yang berkaitan dengan kehidupan orang Melayu. Penggunaan kata-kata Melayu lama dan simbol Melayu memperkuat setting Melayu dalam sajak ini. Analisis makna menunjukkan bahwa seseorang merasakan kedukaan sangat mendalam ketika cintanya harus berakhir, tetapi ia terus merasakan kerinduan dengan kekasihnya yang telah pergi. Mitos cinta yang terdapat dalam pusinya adalah orang tahu bahwa putus cinta itu menyakitkan tetapi orang tetap saja jatuh cinta.

  20. Dark current spectroscopy of space and nuclear environment induced displacement damage defects in pinned photodiode based CMOS image sensors

    International Nuclear Information System (INIS)

    Belloir, Jean-Marc

    2016-01-01

    CMOS image sensors are envisioned for an increasing number of high-end scientific imaging applications such as space imaging or nuclear experiments. Indeed, the performance of high-end CMOS image sensors has dramatically increased in the past years thanks to the unceasing improvements of microelectronics, and these image sensors have substantial advantages over CCDs which make them great candidates to replace CCDs in future space missions. However, in space and nuclear environments, CMOS image sensors must face harsh radiation which can rapidly degrade their electro-optical performances. In particular, the protons, electrons and ions travelling in space or the fusion neutrons from nuclear experiments can displace silicon atoms in the pixels and break the crystalline structure. These displacement damage effects lead to the formation of stable defects and to the introduction of states in the forbidden bandgap of silicon, which can allow the thermal generation of electron-hole pairs. Consequently, non ionizing radiation leads to a permanent increase of the dark current of the pixels and thus a decrease of the image sensor sensitivity and dynamic range. The aim of the present work is to extend the understanding of the effect of displacement damage on the dark current increase of CMOS image sensors. In particular, this work focuses on the shape of the dark current distribution depending on the particle type, energy and fluence but also on the image sensor physical parameters. Thanks to the many conditions tested, an empirical model for the prediction of the dark current distribution induced by displacement damage in nuclear or space environments is experimentally validated and physically justified. Another central part of this work consists in using the dark current spectroscopy technique for the first time on irradiated CMOS image sensors to detect and characterize radiation-induced silicon bulk defects. Many types of defects are detected and two of them are identified

  1. Analisis Industri Ritel Di Indonesia

    OpenAIRE

    Soliha, Euis

    2008-01-01

    This article presents an overview the analisys of retail industry in Indonesia.Retail industry in Indonesia grow rapidly. Industrial presence of modern retailbasically exploits public shopping pattern especially middle-weight and to which donot want to mill around in traditional market. Analysis Five Forces is used toanalysis retail industry. Analysis five force is bargaining power of buyers,bargaining power of suppliers, threat of new entrants, threat of new substituteproducts, and rivalry a...

  2. Light ions cyclotron bombardment to simulate fast neutron radiation damage in nuclear materials

    International Nuclear Information System (INIS)

    Segura, E.; Lucki, G.; Aguiar, D.

    1984-01-01

    The applicability and limitations of the use of cyclotron light ions bombardment to simulate the effects of the neutron irradiation are presented. Light ions with energies of about 10 MeV are capable to produce homogeneous damage in specimens suitable for measuring bulk mechanical properties although their low damage rate of 10 -5 dpa.sec -1 limit the dose range to a few dpa. On the other hand, cyclotron alpha particle implantation provides a fast and convenient way of introducing helium with a minimum of side effects so that we can take advantage of this technique to get better understanding of the mechanism by which this insoluble gas produces high temperature embrittlement. Some experimental details such as dimensions and cooling techniques are described. Finally a description of the infrastructure for cyclotron alpha particle implantation and a creep-test facility of the Division of Radiation Damage at IPEN-CNEN/SP are presented. (Author) [pt

  3. ANALISIS POSITIONING RESTORAN CEPAT SAJI

    Directory of Open Access Journals (Sweden)

    Osa Omar Sharif

    2017-04-01

    Full Text Available Penelitian ini bertujuan untuk meneliti positioning restoran cepat saji McDonald's, Kentucky Fried Chicken, California Fried Chicken, A&W, dan Texas Chicken. Penelitian dilakukan di Kota Bandung dengan mengambil sebanyak 400 responden. Analisis yang digunakan dalam penelitian ini adalah analisis multidimensional scaling, analisis memberikan gambaran positioning dari restoran cepat saji yang ditampilkan dalam perceptual map. Restoran cepat saji yang memiliki layanan paling baik adalah McD dan yang memiliki layanan paling buruk adalah CFC. Restoran cepat saji yang memiliki rasa makanan paling enak adalah McD dan yang memiliki rasa makanan tidak enak adalah CFC. KFC dinilai paling ideal karena selalu berhasil menduduki peringkat satu dan dua jika dilihat dari sudut pandang restoran cepat saji yang lain. Pesaing terdekat McD adalah KFC. McD mendapatkan ranking pertama dari segi atribut layanan, kebersihan, variasi makanan, dan rasa makanan. Dengan posisi seperti ini McD seharusnya tetap menjaga kualitas layanan, kebersihan, variasi makanan, dan rasa makanan agar konsumen tetap memilih untuk datang ke McD. KFC sebaiknya tetap menjaga suasana yang membuat konsumen nyaman akan suasana di dalam atau diluar restoran

  4. Evaluation of fatigue damage in nuclear power plants: evolution and new tools of analysis

    International Nuclear Information System (INIS)

    Cicero, R.; Corchon, F.

    2011-01-01

    This paper presents new fatigue mechanisms requiring analysis, tools developed for evaluation and the latest trends and studies that are currently working in the nuclear field, and allow proper management referring facilities the said degradation mechanism.

  5. Fukushima Daiichi nuclear acccident. Damaged facilities of the site - Situation as on March 2018

    International Nuclear Information System (INIS)

    2018-03-01

    After a recall of the events that led to the Fukushima Daiichi accident, this note presents the situation in March 2018 of the actions of control of the damaged facilities and of their effluents. The last part presents the three steps of the facility control recovery plan retained by TEPCO

  6. Nuclear insulin-like growth factor 1 receptor phosphorylates proliferating cell nuclear antigen and rescues stalled replication forks after DNA damage.

    Science.gov (United States)

    Waraky, Ahmed; Lin, Yingbo; Warsito, Dudi; Haglund, Felix; Aleem, Eiman; Larsson, Olle

    2017-11-03

    We have previously shown that the insulin-like growth factor 1 receptor (IGF-1R) translocates to the cell nucleus, where it binds to enhancer-like regions and increases gene transcription. Further studies have demonstrated that nuclear IGF-1R (nIGF-1R) physically and functionally interacts with some nuclear proteins, i.e. the lymphoid enhancer-binding factor 1 (Lef1), histone H3, and Brahma-related gene-1 proteins. In this study, we identified the proliferating cell nuclear antigen (PCNA) as a nIGF-1R-binding partner. PCNA is a pivotal component of the replication fork machinery and a main regulator of the DNA damage tolerance (DDT) pathway. We found that IGF-1R interacts with and phosphorylates PCNA in human embryonic stem cells and other cell lines. In vitro MS analysis of PCNA co-incubated with the IGF-1R kinase indicated tyrosine residues 60, 133, and 250 in PCNA as IGF-1R targets, and PCNA phosphorylation was followed by mono- and polyubiquitination. Co-immunoprecipitation experiments suggested that these ubiquitination events may be mediated by DDT-dependent E2/E3 ligases ( e.g. RAD18 and SHPRH/HLTF). Absence of IGF-1R or mutation of Tyr-60, Tyr-133, or Tyr-250 in PCNA abrogated its ubiquitination. Unlike in cells expressing IGF-1R, externally induced DNA damage in IGF-1R-negative cells caused G 1 cell cycle arrest and S phase fork stalling. Taken together, our results suggest a role of IGF-1R in DDT. © 2017 by The American Society for Biochemistry and Molecular Biology, Inc.

  7. Civil liability for nuclear damage: selected questions connected with the revision of the Vienna Convention

    International Nuclear Information System (INIS)

    Lopuski, J.

    1993-01-01

    This paper concentrates on certain issues raised by the revision of the Vienna Convention. After a general theoretical review of the risk of and the responsibility for nuclear activities in the existing international civil liability regime, the author analyzes the concept of liability, its extent - whether nuclear liability can be absolute and refers to the possible exonerations - and the channelling of risk and liability in this field. The potential sources of compensation and funds for the operator's liability are also taken into consideration. The author also proposes several solutions taking into account the similar systems already established by other international conventions in force, mainly in the maritime field. 14 refs

  8. Neutron irradiation damage of nuclear graphite studied by high-resolution transmission electron microscopy and Raman spectroscopy

    Energy Technology Data Exchange (ETDEWEB)

    Krishna, R. [Dalton Cumbrian Facility, Dalton Nuclear Institute, The University of Manchester, Westlakes Science & Technology Park, Moor Row, Whitehaven, Cumbria, CA24 3HA (United Kingdom); Jones, A.N., E-mail: Abbie.Jones@manchester.ac.uk [Nuclear Graphite Research Group, School of MACE, The University of Manchester, Manchester, M13 9PL (United Kingdom); McDermott, L.; Marsden, B.J. [Nuclear Graphite Research Group, School of MACE, The University of Manchester, Manchester, M13 9PL (United Kingdom)

    2015-12-15

    Nuclear graphite components are produced from polycrystalline artificial graphite manufacture from a binder and filler coke with approximately 20% porosity. During the operational lifetime, nuclear graphite moderator components are subjected to fast neutron irradiation which contributes to the change of material and physical properties such as thermal expansion co-efficient, young's modulus and dimensional change. These changes are directly driven by irradiation-induced changes to the crystal structure as reflected through the bulk microstructure. It is therefore of critical importance that these irradiation changes and there implication on component property changes are fully understood. This work examines a range of irradiated graphite samples removed from the British Experimental Pile Zero (BEPO) reactor; a low temperature, low fluence, air-cooled Materials Test Reactor which operated in the UK. Raman spectroscopy and high-resolution transmission electron microscopy (HRTEM) have been employed to characterise the effect of increased irradiation fluence on graphite microstructure and understand low temperature irradiation damage processes. HRTEM confirms the structural damage of the crystal lattice caused by irradiation attributed to a high number of defects generation with the accumulation of dislocation interactions at nano-scale range. Irradiation-induced crystal defects, lattice parameters and crystallite size compared to virgin nuclear graphite are characterised using selected area diffraction (SAD) patterns in TEM and Raman Spectroscopy. The consolidated ‘D’peak in the Raman spectra confirms the formation of in-plane point defects and reflected as disordered regions in the lattice. The reduced intensity and broadened peaks of ‘G’ and ‘D’ in the Raman and HRTEM results confirm the appearance of turbulence and disordering of the basal planes whilst maintaining their coherent layered graphite structure. - Highlights: • Irradiated graphite

  9. Neutron irradiation damage of nuclear graphite studied by high-resolution transmission electron microscopy and Raman spectroscopy

    International Nuclear Information System (INIS)

    Krishna, R.; Jones, A.N.; McDermott, L.; Marsden, B.J.

    2015-01-01

    Nuclear graphite components are produced from polycrystalline artificial graphite manufacture from a binder and filler coke with approximately 20% porosity. During the operational lifetime, nuclear graphite moderator components are subjected to fast neutron irradiation which contributes to the change of material and physical properties such as thermal expansion co-efficient, young's modulus and dimensional change. These changes are directly driven by irradiation-induced changes to the crystal structure as reflected through the bulk microstructure. It is therefore of critical importance that these irradiation changes and there implication on component property changes are fully understood. This work examines a range of irradiated graphite samples removed from the British Experimental Pile Zero (BEPO) reactor; a low temperature, low fluence, air-cooled Materials Test Reactor which operated in the UK. Raman spectroscopy and high-resolution transmission electron microscopy (HRTEM) have been employed to characterise the effect of increased irradiation fluence on graphite microstructure and understand low temperature irradiation damage processes. HRTEM confirms the structural damage of the crystal lattice caused by irradiation attributed to a high number of defects generation with the accumulation of dislocation interactions at nano-scale range. Irradiation-induced crystal defects, lattice parameters and crystallite size compared to virgin nuclear graphite are characterised using selected area diffraction (SAD) patterns in TEM and Raman Spectroscopy. The consolidated ‘D’peak in the Raman spectra confirms the formation of in-plane point defects and reflected as disordered regions in the lattice. The reduced intensity and broadened peaks of ‘G’ and ‘D’ in the Raman and HRTEM results confirm the appearance of turbulence and disordering of the basal planes whilst maintaining their coherent layered graphite structure. - Highlights: • Irradiated graphite exhibits

  10. Analysis of displacement damage in materials in nuclear fusion facilities (DEMO, IFMIF and TechnoFusion)

    International Nuclear Information System (INIS)

    Mota, F.; Vila, R.; Ortiz, C.; Garcia, A.; Casal, N.; Ibarra, A.; Rapisarda, D.; Queral, V.

    2011-01-01

    Present pathway to fusion reactors includes a rigorous material testing program. To reach this objective, irradiation facilities must produce the displacement damage per atom (dpa), primary knock-on atom (PKA) spectrum and gaseous elements by transmutation reactions (He, H) as closely as possible to the ones expected in the future fusion reactors (as DEMO).The irradiation parameters (PKA spectra and damage function) of some candidate materials for fusion reactors (Al 2 O 3 , SiC and Fe) have been studied and then, the suitability of some proposed experimental facilities, such as IFMIF and TechnoFusion, to perform relevant tests with these materials has been assessed.The following method has been applied: neutron fluxes present in different irradiation modules of IFMIF have been calculated by the neutron transport McDeLicious code. In parallel, the energy differential cross sections of PKA have been calculated by using the NJOY code. After that, the damage generated by the PKA spectra was analyzed using the MARLOWE code (binary collision approximation) and custom analysis codes. Finally, to analyze the ions effects in different irradiation conditions in the TechnoFusion irradiation area, the SRIM and Marlowe codes have been used. The results have been compared with the expected ones for a DEMO HCLL reactor.

  11. Analysis of displacement damage in materials in nuclear fusion facilities (DEMO, IFMIF and TechnoFusion)

    Energy Technology Data Exchange (ETDEWEB)

    Mota, F., E-mail: fernando.mota@ciemat.es [Laboratorio Nacional de Fusion por Confinamiento Magnetico-CIEMAT, 28040 Madrid (Spain); Vila, R.; Ortiz, C.; Garcia, A.; Casal, N.; Ibarra, A.; Rapisarda, D.; Queral, V. [Laboratorio Nacional de Fusion por Confinamiento Magnetico-CIEMAT, 28040 Madrid (Spain)

    2011-10-15

    Present pathway to fusion reactors includes a rigorous material testing program. To reach this objective, irradiation facilities must produce the displacement damage per atom (dpa), primary knock-on atom (PKA) spectrum and gaseous elements by transmutation reactions (He, H) as closely as possible to the ones expected in the future fusion reactors (as DEMO).The irradiation parameters (PKA spectra and damage function) of some candidate materials for fusion reactors (Al{sub 2}O{sub 3}, SiC and Fe) have been studied and then, the suitability of some proposed experimental facilities, such as IFMIF and TechnoFusion, to perform relevant tests with these materials has been assessed.The following method has been applied: neutron fluxes present in different irradiation modules of IFMIF have been calculated by the neutron transport McDeLicious code. In parallel, the energy differential cross sections of PKA have been calculated by using the NJOY code. After that, the damage generated by the PKA spectra was analyzed using the MARLOWE code (binary collision approximation) and custom analysis codes. Finally, to analyze the ions effects in different irradiation conditions in the TechnoFusion irradiation area, the SRIM and Marlowe codes have been used. The results have been compared with the expected ones for a DEMO HCLL reactor.

  12. Multifunctional Ebselen drug functions through the activation of DNA damage response and alterations in nuclear proteins.

    Science.gov (United States)

    Azad, Gajendra K; Balkrishna, Shah Jaimin; Sathish, Narayanan; Kumar, Sangit; Tomar, Raghuvir S

    2012-01-15

    Several studies have demonstrated that Ebselen is an anti-inflammatory and anti-oxidative agent. Contrary to this, studies have also shown a high degree of cellular toxicity associated with Ebselen usage, the underlying mechanism of which remains less understood. In this study we have attempted to identify a possible molecular mechanism behind the above by investigating the effects of Ebselen on Saccharomyces cerevisiae. Significant growth arrest was documented in yeast cells exposed to Ebselen similar to that seen in presence of DNA damaging agents (including methyl methane sulfonate [MMS] and hydroxy urea [HU]). Furthermore, mutations in specific lysine residues in the histone H3 tail (H3 K56R) resulted in increased sensitivity of yeast cells to Ebselen presumably due to alterations in post-translational modifications of histone proteins towards regulating replication and DNA damage repair. Our findings suggest that Ebselen functions through activation of DNA damage response, alterations in histone modifications, activation of checkpoint kinase pathway and derepression of ribonucleotide reductases (DNA repair genes) which to the best of our knowledge is being reported for the first time. Interestingly subsequent to Ebselen exposure there were changes in global yeast protein expression and specific histone modifications, identification of which is expected to reveal a fundamental cellular mechanism underlying the action of Ebselen. Taken together these observations will help to redesign Ebselen-based therapy in clinical trials. Copyright © 2011 Elsevier Inc. All rights reserved.

  13. Research status on radiation damage in nuclear materials and recommendations for IAEA activities. Technical report

    International Nuclear Information System (INIS)

    Caro, Alfredo; Caro, Magdalena

    2002-03-01

    This report addresses the synergy between the continuous progress of parallel computing and the spectacular advances in the theoretical framework that describes materials. Together, they contributed to significantly advance our comprehension of materials properties like mechanical behavior. It also highlights its impact on nuclear technology, as it provides physical insight into the complex processes responsible for the degradation of structural materials under neutron irradiation

  14. Fire damage data analysis as related to current testing practices for nuclear power applications

    International Nuclear Information System (INIS)

    Klevan, J.; MacDougall, E.A.; Hall, R.E.

    1978-01-01

    A review of reports of specific fires which have occurred in nuclear power plants in the United States is presented. A limited comparison of cable and similar fires with results of the IEEE 383 fire test used to evaluate cable insulation is also presented

  15. Dual Liability for Nuclear Damage in Conventions and Finnish Legislation in the Field of Transport

    International Nuclear Information System (INIS)

    Manninen, J.

    1986-01-01

    The exception made in the 1960 Paris Convention on Third Party Liability in the Field of Nuclear Energy to the otherwise absolute channelling of liability in order to avoid conflicts with the then existing international agreements in the field of transport is briefly described. The dual liability created by this provision is studied, as well as the question whether and when the victim might prefer to base his claim on a transport agreement instead of the Paris Convention. The so-called nuclear clauses in the new agreements in the transport field are analysed. The problems caused by the absence of a nuclear clause in the Guatemala City and Montreal Protocols, amending the Warsaw Convention relating to international air carriage are noted. Finally the relationship between nuclear liability legislation and transport legislation in Finland, as well as the cases where a dual liability existed at the time of the ratification of the Paris Convention and the changes which have taken place since then are described. (NEA) [fr

  16. Analysis of the accident at Fukushima Daiichi nuclear power plant in an A BWR reactor; Analisis del accidente de la planta nucleoelectrica de Fukushima Daiichi en un reactor tipo ABWR

    Energy Technology Data Exchange (ETDEWEB)

    Escorcia O, D. [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico); Salazar S, E., E-mail: daniel.escorcia.ortiz@gmail.com [UNAM, Facultad de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, 62250 Jiutepec, Morelos (Mexico)

    2016-09-15

    The present work aims to recreate the accident occurred at the Fukushima Daiichi nuclear power plant in Japan on March 11, 2011, making use of an academic simulator of forced circulation of the A BWR reactor provided by the IAEA to know the scope of this simulator. The simulator was developed and distributed by the IAEA for academic purposes and contains the characteristics and general elements of this reactor to be able to simulate transients and failures of different types, allowing also to observe the general behavior of the reactor, as well as several phenomena and present systems in the same. Is an educational tool of great value, but it does not have a scope that allows the training of plant operators. To recreate the conditions of the Fukushima accident in the simulator, we first have to know what events led to this accident, as well as the actions taken by operators and managers to reduce the consequences of this accident; and the sequence of events that occurred during the course of the accident. Differences in the nuclear power plant behavior are observed and interpreted throughout the simulation, since the Fukushima plant technology and the simulator technology are not the same, although they have several elements in common. The Fukushima plant had an event that by far exceeded the design basis, which triggered in an accident that occurred in the first place by a total loss of power supply, followed by the loss of cooling systems, causing a level too high in temperature, melting the core and damaging the containment accordingly, allowing the escape of hydrogen and radioactive material. As a result of the simulation, was determined that the scope of the IAEA academic simulator reaches the entrance of the emergency equipment, so is able to simulate almost all the events occurred at the time of the earthquake and the arrival of the tsunami in the nuclear power plant of Fukushima Daiichi. However, due to its characteristics, is not able to simulate later

  17. Outline of the Guidelines on the Scope of Nuclear Damage. Annex III of Technical Volume 5

    International Nuclear Information System (INIS)

    2015-01-01

    Damage associated with evacuation - Subject areas: evacuation area (restricted area), in-house evacuation area, deliberate evacuation area, evacuation-prepared area in case of emergency, evacuation recommendation spot, and areas for which temporary evacuation was requested by Minamisoma City. – Evacuation, temporary entry, homecoming expenses (evacuation expenses are paid only until evacuee remove to a new residence). – Injury or death (medical treatment expenses, etc., due for instance to a deterioration in the state of health resulting from evacuation and other such actions). – Mental anguish. – Loss or reduction, etc., of property value (including cost of refinement and decontamination in addition to actual loss or reduction of value): – Real estate within Area 3 is estimated to be a total loss. – Real estate value within Areas 1 and 2 is estimated to have decreased from pre-accident prices. – Securing of homes: – For residential houses, compensation for up to 75% of the difference between the original price and the pre-accident price of the house. – For housing land in Area 3, compensation for the difference between the price of newly acquired land and the price of land formerly held. For housing land in Areas 1 and 2, in case where mitigation is allowed as reasonable, compensation of 75% of the difference between the two prices. – For rented houses, compensation for the difference in rent between the new houses and houses standing for the previous eight years. – Business damage (agriculture, forestry and fisheries, general industry, including manufacturing). – Damages due to inability to work. – Examination expenses (human and material)

  18. ASME Section XI philosophy related to operating nuclear plant fatigue damage protection

    International Nuclear Information System (INIS)

    Gosselin, S.R.

    1995-01-01

    When faced with operating fatigue concerns, nuclear plants traditionally look to the requirements contained in the original construction design code, ASME Section 3, as a basis for component operability. These rules constitute the requirements for nuclear power plant vessel and component construction and, when combined with the Owner's Design Specification, provide reasonable assurance of reliable operation. However, once construction is complete and operation begins, the purpose of any subsequent evaluations shifts from component ''design qualification'' to component ''fitness for service.'' This is a role that has been assumed for ASME Section 11. This paper presents a philosophy, recently endorsed by the ASME Section 11 Executive Committee, intended to guide future Code activities regarding fatigue and its impact on component serviceability

  19. Accidents in the operation of nuclear power stations. Action for damages against foreign operators

    International Nuclear Information System (INIS)

    Willner, K.

    1986-01-01

    On the occasion of a lecture evening of the Leo Goodman Library in Munich questions of civil liability of foreign reactor operators in cases of nuclear accidents were discussed by participants of various universities. Special subjects were i.a. problems of civil procedural and insurance law, absolute liability according to sec. 25 Atomic Energy Act as well as questions of applicable law. (WG) [de

  20. Determination of possible damage/degradation of the Sandia National Laboratories Personal Nuclear Accident Dosimeter (PNAD)

    International Nuclear Information System (INIS)

    Potter, Charles Augustus; Ward, Dann C.

    2008-01-01

    This report describes the results of an inspection performed on the existing stock of SNL Personal Nuclear Accident Dosimeters (PNADs). The current stock is approximately 20 years old, and has not been examined since their initial acceptance. A small random sample of PNADs were opened (a destructive process) and the contents visually examined. Sample contents were not degraded and indicate that the existing stock of SNL PNADs is acceptable for continued use

  1. ANALISIS PERBAIKAN SISTEM PENTANAHAN TELEKOMUNIKASI

    Directory of Open Access Journals (Sweden)

    Umar Umar

    2015-04-01

    Hasil dari penelitian ini adalah perbaikan sistem pentanahan site Kampung Baru dengan menggunakan konfigurasi single point connection window (SPCW, untuk mengamankan sistem telekomunikasi dari kebocoran arus dan petir serta imbasnya.  Perbaikan sistem pentanahan di site Kampung Baru menggunakan banyak elektroda yang membentuk persegi dikarenakan topografi tempat di sana yang memungkinkan dan efektif adalah menggunakan sistem tersebut. Berdasarkan hasil analisis dan perhitungan perbaikan sistem di site Kampung Baru, didapatkan nilai perhitungan sistem pentanahan adalah 1.34 Ohm serta pengukurannya 1.21-1.25 Ohm.

  2. Determination of nitrogen in wheat flour through Activation analysis using Fast neutron flux of a Thermal nuclear reactor; Determinacion de nitrogeno en harina de trigo mediante analisis por activacion empleando el flujo de neutrones rapidos de un reactor nuclear termico

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez G, T

    1976-07-01

    In this work is done a technical study for determining Nitrogen (protein) and other elements in wheat flour Activation analysis, with Fast neutrons from a Thermal nuclear reactor. Initially it is given an introduction about the basic principles of the methods of analysis. Equipment used in Activation analysis and a brief description of the neutron source (Thermal nuclear reactor). The realized experiments for determining the flux form in the irradiation site, the half life of N-13 and the interferences due to the sample composition are included too. Finally, the obtained results by Activation and the Kjeldahl method are tabulated. (Author)

  3. Analysis of the documents about the core envelopment of nuclear reactor at the Laguna Verde U-1 power plant; Analisis de documentos de los materiales de la envolvente del nucleo del reactor nuclear de la CLV U-1

    Energy Technology Data Exchange (ETDEWEB)

    Zamora R, L.; Medina F, A. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    1999-07-01

    The degradation of internal components at BWR type reactors is an important subject to consider in the performance availability of the power plant. The Wuergassen nuclear reactor license was confiscated due to the presence of cracking in the core envelopment. In consequence it is necessary carrying out a detailed study with the purpose to avoid these problems in the future. This report presents a review and analysis of documents and technical information referring to the core envelopment of a BWR/5/6 and the Laguna Verde Unit 1 nuclear reactor in Mexico. In this document are presented design data, documents about fabrication processes, and manufacturing of core envelopment. (Author)

  4. Radioactive impact in South Korea from the damaged nuclear reactors in Fukushima: evidence of long and short range transport

    International Nuclear Information System (INIS)

    Hong, G H; Lee, H M; Kim, S H; Hernández-Ceballos, M A; Lozano, R L; Bolívar, J P; Kim, Y I; Yeh, S-W; Baskaran, M

    2012-01-01

    Traces of long-lived fallout-derived radioisotopes ( 134 Cs and 137 Cs) were found in wet and dry deposition samples collected from the west and east coasts of South Korea from March to May 2011 following the release of radionuclides from the damaged nuclear power plants in Fukushima, Japan. The analysis of air mass back trajectory and atmospheric pressure systems indicated that the Fukushima-derived radiocaesium had predominantly reached South Korea from the west by surface westerlies from 11 March to 5 April; however, after 6 April, air masses arrived from Japan directly due to a high pressure system that developed to the east of Japan. Spatial variation of deposition fluxes of radiocaesium in South Korea was partly attributed to the presence of local longitudinal orography. (paper)

  5. An Experimental Investigation On Minimum Compressive Strength Of Early Age Concrete To Prevent Frost Damage For Nuclear Power Plant Structures In Cold Climates

    International Nuclear Information System (INIS)

    Koh, Kyungtaek; Kim, Dogyeum; Park, Chunjin; Ryu, Gumsung; Park, Jungjun; Lee, Janghwa

    2013-01-01

    Concrete undergoing early frost damage in cold weather will experience significant loss of not only strength, but also of permeability and durability. Accordingly, concrete codes like ACI-306R prescribe a minimum compressive strength and duration of curing to prevent frost damage at an early age and secure the quality of concrete. Such minimum compressive strength and duration of curing are mostly defined based on the strength development of concrete. However, concrete subjected to frost damage at early age may not show a consistent relationship between its strength and durability. Especially, since durability of concrete is of utmost importance in nuclear power plant structures, this relationship should be imperatively clarified. Therefore, this study verifies the feasibility of the minimum compressive strength specified in the codes like ACI-306R by evaluating the strength development and the durability preventing the frost damage of early age concrete for nuclear power plant. The results indicate that the value of 5 MPa specified by the concrete standards like ACI-306R as the minimum compressive strength to prevent the early frost damage is reasonable in terms of the strength development, but seems to be inappropriate in the viewpoint of the resistance to chloride ion penetration and freeze-thaw. Consequently, it is recommended to propose a minimum compressive strength preventing early frost damage in terms of not only the strength development, but also in terms of the durability to secure the quality of concrete for nuclear power plants in cold climates

  6. DART, a BCA code to assess and compare primary irradiation damage in nuclear materials submitted to neutron and ion flux - 02002

    International Nuclear Information System (INIS)

    Luneville, L.; Simeone, D.

    2016-01-01

    When a material is subjected to a flux of high-energy particles, its constituent atoms can be knocked from their equilibrium positions with a wide range of energies, depending on the exact nature of the collision. The spectrum of damage energy, derived from the exact knowledge of the recoil spectra for each nuclear reaction occurring in the solid, constitutes a vital data set required for understanding how materials evolve under irradiation. The knowledge of such damage energy is relevant to compare the impact of different facilities on the structural behavior and relevant properties of materials. The DART code was developed for two distinct reasons: the first one was a correct determination of the Primary Knocked on Atoms (PKA) spectrum from reliable cross section data libraries and the second was a crude estimation of the damage energy induced by different irradiations. This last term can be a quick estimation of radiation damage produced in the same material by different nuclear plants and particle accelerators. Based on the Binary Collision Approximation, this code allows computing the primary spectra produced by neutrons, ions and electrons as well as the damage energy deposited by these particles in a poly atomic material. It is then a tool to compare radiation damage induced in nuclear reactors as well as in ion beam facilities. This brief paper is followed by the slides of the presentation

  7. An Experimental Investigation On Minimum Compressive Strength Of Early Age Concrete To Prevent Frost Damage For Nuclear Power Plant Structures In Cold Climates

    Energy Technology Data Exchange (ETDEWEB)

    Koh, Kyungtaek; Kim, Dogyeum; Park, Chunjin; Ryu, Gumsung; Park, Jungjun; Lee, Janghwa [Korea Institute Construction Technology, Goyang (Korea, Republic of)

    2013-06-15

    Concrete undergoing early frost damage in cold weather will experience significant loss of not only strength, but also of permeability and durability. Accordingly, concrete codes like ACI-306R prescribe a minimum compressive strength and duration of curing to prevent frost damage at an early age and secure the quality of concrete. Such minimum compressive strength and duration of curing are mostly defined based on the strength development of concrete. However, concrete subjected to frost damage at early age may not show a consistent relationship between its strength and durability. Especially, since durability of concrete is of utmost importance in nuclear power plant structures, this relationship should be imperatively clarified. Therefore, this study verifies the feasibility of the minimum compressive strength specified in the codes like ACI-306R by evaluating the strength development and the durability preventing the frost damage of early age concrete for nuclear power plant. The results indicate that the value of 5 MPa specified by the concrete standards like ACI-306R as the minimum compressive strength to prevent the early frost damage is reasonable in terms of the strength development, but seems to be inappropriate in the viewpoint of the resistance to chloride ion penetration and freeze-thaw. Consequently, it is recommended to propose a minimum compressive strength preventing early frost damage in terms of not only the strength development, but also in terms of the durability to secure the quality of concrete for nuclear power plants in cold climates.

  8. Advances in the development of the Mexican platform for analysis and design of nuclear reactors: AZTLAN Platform; Avances en el desarrollo de la plataforma mexicana para analisis y diseno de reactores nucleares: AZTLAN Platform

    Energy Technology Data Exchange (ETDEWEB)

    Gomez T, A. M.; Puente E, F. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, 07738 Ciudad de Mexico (Mexico); Francois L, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico); Espinosa P, G., E-mail: armando.gomez@inin.gob.mx [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Ciudad de Mexico (Mexico)

    2017-09-15

    The AZTLAN platform project: development of a Mexican platform for the analysis and design of nuclear reactors, financed by the SENER-CONACYT Energy Sustain ability Fund, was approved in early 2014 and formally began at the end of that year. It is a national project led by the Instituto Nacional de Investigaciones Nucleares (ININ) and with the collaboration of Instituto Politecnico Nacional (IPN), the Universidad Autonoma Metropolitana (UAM) and Universidad Nacional Autonoma de Mexico (UNAM) as part of the development team and with the participation of the Laguna Verde Nuclear Power Plant, the National Commission of Nuclear Safety and Safeguards, the Ministry of Energy and the Karlsruhe Institute of Technology (Kit, Germany) as part of the user group. The general objective of the project is to modernize, improve and integrate the neutronic, thermo-hydraulic and thermo-mechanical codes, developed in Mexican institutions, in an integrated platform, developed and maintained by Mexican experts for the benefit of Mexican institutions. Two years into the process, important steps have been taken that have consolidated the platform. The main results of these first two years have been presented in different national and international forums. In this congress, some of the most recent results that have been implemented in the platform codes are shown in more detail. The current status of the platform from a more executive view point is summarized in this paper. (Author)

  9. UPVAPOR: computer application for the analysis of the results of Cofrentes Nuclear Power Plant production; UPVAPOR: Aplicacion informatica para el analisis de resultados de produccion en Central Nuclear Cofrentes

    Energy Technology Data Exchange (ETDEWEB)

    Palomo, M. J.; Baraza Peregrin, A.; Bucho Piqueras, L.; Vaquer Perez, J. I.; Lopez Lopez, B.

    2010-07-01

    UPVapor is a software developed for the Cofrentes Nuclear Power Plant Group of Results. This application presents a graphical environment for analysis in which the user has available many variables registered to configure the graphics. This application saves a lot of time at work because it allows other users to do their own analysis without resorting to analysts.

  10. Improving performance of high risk organizations Spanish nuclear sector from the analysis of organizational culture factors; Mejora del desempeno de las organizaciones de alto riesgo del sector nuclear espanol a partir del analisis de los factores de cultura organizativa

    Energy Technology Data Exchange (ETDEWEB)

    La Salabarnada, E.; German, S.; Silla, I.; Navajas, J.

    2012-07-01

    This paper presents the research project funded by UNESA and conducted by the CISOT-CIEMAT that aims to contribute to improving the operating performance of the Spanish nuclear power plants. This paper aims to identify the factors and key organizational processes to improve efficiency, in order to advance knowledge about the influence of organizational culture on the safety of high reliability organizations.

  11. Radiation exposure and health damage of residents at Semipalatinsk nuclear test site

    International Nuclear Information System (INIS)

    Tolebay, Rakhypbekov; Noso, Yoshihiro; Takechi, Nobuo

    2016-01-01

    Although the nuclear test site of Semipalatinsk (former Soviet Union and presently the Republic of Kazakhstan) stopped nuclear tests 25 years ago, there are presumably more than 200,000 victims near the site, including persons with a low dose and a high dose. Semey Medical University and Shimane University, together with the Kazakh Scientific Institute for Radiation Medicine and Ecology, have been conducting the measurement of radiation concentration of soil and the thyroid screening of residents. The following were surveyed: (1) chromosomal abnormality for 55 female residents (average 45 years in age) in heavily polluted areas and 25 female residents (average 42 years in age) in non-polluted areas, (2) mental abnormality of residents in polluted areas and non-polluted areas of Semey City, and (3) changes in the frequency of surgery cases for cancer between 1989 and 2014 at Semey Medical University Cancer Center. As for chromosomal abnormality, 3-5 times many mutation cases were observed in heavily polluted areas than in non-polluted areas. The nodules of thyroid gland were four times more frequent in heavily polluted areas. The frequency of a whole variety of cancers was nearly twice in polluted areas compared with in non-polluted areas, most of which were digestive system cancer, lung cancer, and breast cancer in the order. The frequency of mental abnormality has also increased nearly twice as compared to non-polluted areas, and it included neurological disorder, adjustment disorder, neuralgia, moderate depression, and learning disability. These results suggest that some physical effects can be caused by exposure. In the future, this study will investigate the effects of radiation exposure at the nuclear test site. (A.O.)

  12. Concrete Materials with Ultra-High Damage Resistance and Self- Sensing Capacity for Extended Nuclear Fuel Storage Systems

    Energy Technology Data Exchange (ETDEWEB)

    Li, Mo [Univ. of California, Irvine, CA (United States); Nakshatrala, Kalyana [Univ. of Houston, TX (United States); William, Kasper [Univ. of Houston, TX (United States); Xi, Yungping [Univ. of Colorado, Boulder, CO (United States)

    2017-02-08

    The objective of this project is to develop a new class of multifunctional concrete materials (MSCs) for extended spent nuclear fuel (SNF) storage systems, which combine ultra-high damage resistance through strain-hardening behavior with distributed multi-dimensional damage self-sensing capacity. The beauty of multifunctional concrete materials is two-fold: First, it serves as a major material component for the SNF pool, dry cask shielding and foundation pad with greatly improved resistance to cracking, reinforcement corrosion, and other common deterioration mechanisms under service conditions, and prevention from fracture failure under extreme events (e.g. impact, earthquake). This will be achieved by designing multiple levels of protection mechanisms into the material (i.e., ultrahigh ductility that provides thousands of times greater fracture energy than concrete and normal fiber reinforced concrete; intrinsic cracking control, electrochemical properties modification, reduced chemical and radionuclide transport properties, and crack-healing properties). Second, it offers capacity for distributed and direct sensing of cracking, strain, and corrosion wherever the material is located. This will be achieved by establishing the changes in electrical properties due to mechanical and electrochemical stimulus. The project will combine nano-, micro- and composite technologies, computational mechanics, durability characterization, and structural health monitoring methods, to realize new MSCs for very long-term (greater than 120 years) SNF storage systems.

  13. Once again: The inviolability of fundamental rights and the exclusion of damage in connection with the nuclear law

    International Nuclear Information System (INIS)

    Wagner, H.

    1979-01-01

    According to the opinion stated by the author, the Atomic Energy Act and the relevant ordinances are guarenteiing to a sufficient extent the inviolability of fundamental rights, and the courts are effectively safeguarding these rights. The objective standard of value set up by the basic law and on legal system cannot be interpreted to be intended to completely exclude damage, but rather to institute precantions to be taken in order to prevent damage, taking into account the rights and risks involved and considering all of the declared purposes of the Atomic Energy Act, namely not only that of protection from hazards but also that of furtheranice of the paceful use of nuclear energy. In contrast to this, the opponent in the discussion argues that the present Atomic Energy Act is to be interpreted to contain a preventive prohibition reserving the right to grant licenses, and that any activity likely to represent a prejudice to our Basic Law is not in accordance with the constitution. It is the duty of the judiciary, the opponent says, to try to reconcile the requirements of technology and prosperity for the benefit of human life. (HSCH) [de

  14. Loosening and damage mechanism of thread-joined structures in nuclear power equipment

    International Nuclear Information System (INIS)

    Tang Hui

    1999-01-01

    The author proposes a loosening mechanism of thread-joined structures under vibrate environments in the nuclear power equipment and structures, which is on the base of the macro and imperceptible-mechanics analysis. It has answered the problems on the seizing, the adhesive wearing, the generation of cracks, the thread-tooth fracture. So it has a conclusion that the loosening of thread-joined structures is essential trend, in other words, the locking property of thread-pair is failure under vibrate environments

  15. Damage-tolerant design and inspection philosophy for nuclear and other pressure vessels

    International Nuclear Information System (INIS)

    Adams, N.J.I.

    1980-01-01

    Statistical analyses of pressure vessel failure rates indicate that, to date, the record is very good. However, the public hazard and environmental consequences of failure in certain industrial processes now give cause for much greater concern. With the exception of an Appendix in ASME III, the current design codes and requirements for new vessels are all based on the assumption that they are free from cracklike defects, but engineers recognize tht such perfect vessels cannot be manufactured. Taking into account failure mechanisms, material properties, pre- and in-service inspection, proof testing, failure statistics and probabilistic methods, views are put forward on how a damage-tolerant design and inspection philosophy may be developed to reduce further the possibility of ''rogue'' vessel failure. 21 refs

  16. Application of positron annihilation line-shape analysis to fatigue damage for nuclear plant materials

    International Nuclear Information System (INIS)

    Maeda, N.; Uchida, M.; Ohta, Y.; Yoshida, K.

    1996-01-01

    Positron annihilation line-shape analysis is sufficiently sensitive to detect microstructural defects such as vacancies and dislocations. We are developing a portable positron annihilation system and applying this technique to fatigue damage in type 316 stainless steel and SA508 low alloy steel. The positron annihilation technique was found to be sensitive in the early fatigue life, i.e. up to 10% of the fatigue life, but showed little sensitivity in later stages of the fatigue life in type 316 stainless steel and SA508 low alloy steel. Type 316 stainless steel a higher positron annihilation sensitivity than that of SA508. It was considered that the amount of dislocation density change in the stainless steel was greater than that in the low alloy steel, because the initial microstructure contained a low dislocation density because of the solution heat treatment for the type 316 stainless steel. (orig.)

  17. Diffuse vascular damage in a transplanted kidney: an indication for nuclear magnetic resonance?

    Science.gov (United States)

    Burdese, M; Consiglio, V; Mezza, E; Savio, D; Guarena, C; Rossetti, M; Messina, M; Soragna, G; Suriani, C; Rabbia, C; Segoloni, G P; Piccoli, G B

    2005-06-01

    Vascular lesions are an increasing challenge after renal transplantation due to the wider indications for recipients and acceptance criteria for donors. Diagnostic approach and prognostic interpretation are still matter of controversy. The case reported herein may summarize some of the issues in this regard. A 54-year-old woman, on renal replacement therapy since 1974, and a kidney graft recipient from 1975 to 1999, received a second graft in 2001. The donor age was 65 years (cold ischemia 22 hours; two mismatches). The early posttransplant follow-up was characterized by delayed graft function, hypertension, and diabetes. During the initial hypertension workup, renal graft ultrasound (US) Doppler demonstrated increased vascular resistances, stable over time (resistance index 0.74 to 0.77); renal scintiscan displayed homogeneously parenchymoa and angio-magnetic resonance imaging (MRI), an homogeneous parenchymal vascularization. Initial immunosuppression with tacrolimus and steroids was modulated by adding mycophenolate mofetil to taper tacrolimus (to reduce nephrotoxicity and hypertension). Despite this, kidney function slowly deteriorated; serum creatinine reached 3 to 3.5 mg/dL by the second year. After a severe hypertensive crisis with unchanged scintiscan and US doppler examinations, angio-MRI revealed the almost complete disappearance of parenchymal enhancement beyond the lobar arteries. A renal biopsy confirmed the severe vascular damage. The patient was switched to rapamycine and a low-dose of an angiotension converting enzyme (ACE) inhibitor. She did relatively well (serum creatinine 2.2 to 3 mg/dL) for 6 months, when rapid functional impairment forced her to restart hemodialysis. This case, almost paradigmatic of the problems occurring when the rigid vasculature of long-term dialysis patients is matched with "marginal kidneys," suggests that MRI may be a sensible good to define vascular damage in the grafted kidney.

  18. Ubiquitin Accumulation on Disease Associated Protein Aggregates Is Correlated with Nuclear Ubiquitin Depletion, Histone De-Ubiquitination and Impaired DNA Damage Response.

    Directory of Open Access Journals (Sweden)

    Adi Ben Yehuda

    Full Text Available Deposition of ubiquitin conjugates on inclusion bodies composed of protein aggregates is a definitive cytopathological hallmark of neurodegenerative diseases. We show that accumulation of ubiquitin on polyQ IB, associated with Huntington's disease, is correlated with extensive depletion of nuclear ubiquitin and histone de-ubiquitination. Histone ubiquitination plays major roles in chromatin regulation and DNA repair. Accordingly, we observe that cells expressing IB fail to respond to radiomimetic DNA damage, to induce gamma-H2AX phosphorylation and to recruit 53BP1 to damaged foci. Interestingly ubiquitin depletion, histone de-ubiquitination and impaired DNA damage response are not restricted to PolyQ aggregates and are associated with artificial aggregating luciferase mutants. The longevity of brain neurons depends on their capacity to respond to and repair extensive ongoing DNA damage. Impaired DNA damage response, even modest one, could thus lead to premature neuron aging and mortality.

  19. Semiotika Teks: Sebuah Pendekatan Analisis Teks

    Directory of Open Access Journals (Sweden)

    Yasraf Amir Piliang

    2004-12-01

    tanda-tanda yang membentuk apa yang disebut sebagai ‘teks’. Analisis teks, menurut Roland Barthes, akan menghasilkan makna denotatif, yakni makna tanda yang bersifat eksplisit, dan makna konotatif, yaitu makna tanda lapis kedua yang bersifat implisit.

  20. Damage evaluation of 500 MWe Indian Pressurized Heavy Water Reactor nuclear containment for aircraft impact

    Energy Technology Data Exchange (ETDEWEB)

    Kukreja, Mukesh [Reactor Safety Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400085 (India)]. E-mail: mrkukreja@yahoo.com

    2005-08-01

    Safety assessment of Indian nuclear containments has been carried out for aircraft impact. The loading time history for Boeing and Airbus categories of aircrafts is generated based on the principle of momentum transfer of crushable aircrafts. The case studies include the analysis of BWR Mark III containment as a benchmark problem and analyses of Pressurised Heavy Water Reactor containment (inner and outer containment) for impulsive loading due to aircraft impact. Initially, the load is applied on outer containment wall model and subsequently the load is transferred to inner containment after the local perforation of the outer containment wall is noticed in the transient simulation. The analysis methodology evolved in the present work would be useful for studying the behavior of double containment walls and multi barrier structural configurations for aircraft impact with higher energies. The present analysis illustrates that with the provision of double containments for Indian nuclear power plants, adequate reserve strength is available for the case of an extremely low probability event of missile impact generated due to the commercial aircrafts operated in India.

  1. Damage evaluation of 500 MWe Indian Pressurized Heavy Water Reactor nuclear containment for aircraft impact

    International Nuclear Information System (INIS)

    Kukreja, Mukesh

    2005-01-01

    Safety assessment of Indian nuclear containments has been carried out for aircraft impact. The loading time history for Boeing and Airbus categories of aircrafts is generated based on the principle of momentum transfer of crushable aircrafts. The case studies include the analysis of BWR Mark III containment as a benchmark problem and analyses of Pressurised Heavy Water Reactor containment (inner and outer containment) for impulsive loading due to aircraft impact. Initially, the load is applied on outer containment wall model and subsequently the load is transferred to inner containment after the local perforation of the outer containment wall is noticed in the transient simulation. The analysis methodology evolved in the present work would be useful for studying the behavior of double containment walls and multi barrier structural configurations for aircraft impact with higher energies. The present analysis illustrates that with the provision of double containments for Indian nuclear power plants, adequate reserve strength is available for the case of an extremely low probability event of missile impact generated due to the commercial aircrafts operated in India

  2. Monitoring and modeling stress corrosion and corrosion fatigue damage in nuclear reactors

    International Nuclear Information System (INIS)

    Andresen, P.L.; Ford, F.P.; Solomon, H.D.; Taylor, D.F.

    1990-01-01

    Stress corrosion and corrosion fatigue are significant problems in many industries, causing economic penalties from decreased plant availability and component repair or replacement. In nuclear power reactors, environmental cracking occurs in a wide variety of components, including reactor piping and steam generator tubing, bolting materials and pressure vessels. Life assessment for these components is complicated by the belief that cracking is quite irreproducible. Indeed, for conditions which were once viewed as nominally similar, orders of magnitude variability in crack growth rates are observed for stress corrosion and corrosion fatigue of stainless steels and low-alloy steels in 288 degrees C water. This paper shows that design and life prediction approaches are destined to be overly conservative or to risk environmental failure if life is predicted by quantifying only the effects of mechanical parameters and/or simply ignoring or aggregating environmental and material variabilities. Examples include the Nuclear Regulatory Commission (NRC) disposition line for stress-corrosion cracking of stainless steel in boiling water reactor (BWR) water and the American Society of Mechanical Engineers' Section XI lines for corrosion fatigue

  3. LORD-Q: a long-run real-time PCR-based DNA-damage quantification method for nuclear and mitochondrial genome analysis

    Science.gov (United States)

    Lehle, Simon; Hildebrand, Dominic G.; Merz, Britta; Malak, Peter N.; Becker, Michael S.; Schmezer, Peter; Essmann, Frank; Schulze-Osthoff, Klaus; Rothfuss, Oliver

    2014-01-01

    DNA damage is tightly associated with various biological and pathological processes, such as aging and tumorigenesis. Although detection of DNA damage is attracting increasing attention, only a limited number of methods are available to quantify DNA lesions, and these techniques are tedious or only detect global DNA damage. In this study, we present a high-sensitivity long-run real-time PCR technique for DNA-damage quantification (LORD-Q) in both the mitochondrial and nuclear genome. While most conventional methods are of low-sensitivity or restricted to abundant mitochondrial DNA samples, we established a protocol that enables the accurate sequence-specific quantification of DNA damage in >3-kb probes for any mitochondrial or nuclear DNA sequence. In order to validate the sensitivity of this method, we compared LORD-Q with a previously published qPCR-based method and the standard single-cell gel electrophoresis assay, demonstrating a superior performance of LORD-Q. Exemplarily, we monitored induction of DNA damage and repair processes in human induced pluripotent stem cells and isogenic fibroblasts. Our results suggest that LORD-Q provides a sequence-specific and precise method to quantify DNA damage, thereby allowing the high-throughput assessment of DNA repair, genotoxicity screening and various other processes for a wide range of life science applications. PMID:24371283

  4. Internal event analysis for Laguna Verde Unit 1 Nuclear Power Plant. Accident sequence quantification and results; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Cuantificacion de secuencias de accidente y resultados

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A; Aguilar T, O; Nunez C, A; Lopez M, R [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1994-07-01

    The Level 1 results of Laguna Verde Nuclear Power Plant PRA are presented in the {sup I}nternal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant, CNSNS-TR 004, in five volumes. The reports are organized as follows: CNSNS-TR 004 Volume 1: Introduction and Methodology. CNSNS-TR4 Volume 2: Initiating Event and Accident Sequences. CNSNS-TR 004 Volume 3: System Analysis. CNSNS-TR 004 Volume 4: Accident Sequence Quantification and Results. CNSNS-TR 005 Volume 5: Appendices A, B and C. This volume presents the development of the dependent failure analysis, the treatment of the support system dependencies, the identification of the shared-components dependencies, and the treatment of the common cause failure. It is also presented the identification of the main human actions considered along with the possible recovery actions included. The development of the data base and the assumptions and limitations in the data base are also described in this volume. The accident sequences quantification process and the resolution of the core vulnerable sequences are presented. In this volume, the source and treatment of uncertainties associated with failure rates, component unavailabilities, initiating event frequencies, and human error probabilities are also presented. Finally, the main results and conclusions for the Internal Event Analysis for Laguna Verde Nuclear Power Plant are presented. The total core damage frequency calculated is 9.03x 10-5 per year for internal events. The most dominant accident sequences found are the transients involving the loss of offsite power, the station blackout accidents, and the anticipated transients without SCRAM (ATWS). (Author)

  5. The convention on supplementary compensation for nuclear damage and asian states: the advantages and disadvantages of Korea's adherence to the convention

    International Nuclear Information System (INIS)

    Park, K.G.

    2000-01-01

    This paper intends to make some assessments of the advantages and disadvantages which would result from Korea's ratification of the Convention on Supplementary Compensation for Nuclear Damage (CSC), opened for signature on 29 September 1997 in Vienna, Austria. I have presented elsewhere a view on the creation of an Asian regional regime in the event of a transboundary nuclear accident, but here I will focus on the applicability of a global regime especially to Asian States. (author)

  6. Risk analysis; Analisis de riesgos

    Energy Technology Data Exchange (ETDEWEB)

    Baron, J H; Nunez McLeod, J; Rivera, S S [Universidad Nacional de Cuyo, Mendoza (Argentina). Instituto de Capacitacion Especial y Desarrollo de Ingenieria Asistida por Computadora (CEDIAC)

    1997-07-01

    This book contains a selection of research works performed in the CEDIAC Institute (Cuyo National University) in the area of Risk Analysis, with specific orientations to the subjects of uncertainty and sensitivity studies, software reliability, severe accident modeling, etc. This volume presents important material for all those researches who want to have an insight in the risk analysis field, as a tool to solution several problems frequently found in the engineering and applied sciences field, as well as for the academic teachers who want to keep up to date, including the new developments and improvements continuously arising in this field. [Spanish] Este libro contiene una seleccion de trabajos de investigacion realizados dentro del Instituto de Capacitacion Especial y Desarrollo de la Ingenieria Asistida por Computadora en el area del analisis de riesgos, con una orientacion hacia el estudio de incertidumbres y sensibilidad, confiabilidad de software, modelacion de accidentes severos, etc. Este volumen recoge un material de indudable importancia e interes para todos aquellos investigadores y profesionales que desean incursionar en este campo del analisis de riesgos como herramienta para la solucion de problemas frecuentemente encontrados en la ingenieria y las ciencias aplicadas, asi como para los academicos que desean mantenerse al dia, conociendo los nuevos desarrollos y tecnicas que constantemente aparecen en su area.

  7. Analisis Kebijakan dan Efektivitas Organisasi

    Directory of Open Access Journals (Sweden)

    Amir Syarifudin Kiwang

    2015-05-01

    Full Text Available Penerapan Peraturan Gubernur Nusa Tenggara Timur Nomor 8 Tahun 2011 tentang Organisasi dan Tata Kerja Unit Pelaksana Teknis Pendidikan dan Pelatihan Koperasi dan Usaha Mikro Kecil dan Menengah pada Dinas Koperasi dan Usaha Mikro Kecil dan Menengah Provinsi Nusa Tenggara Timur adalah dalam rangka untuk meningkatkan efektivitas kerja organisasi pada UPT Diklat Koperasi dan UMKM. Penelitian ini berusaha untuk melihat dampak kebijakan organisasi terhadap efektivitas organisasi dengan menggunakan enam elemen variabel dari kebijakan dan praktik manajemen. Keenam elemen tersebut adalah penetapan tujuan strategis, pencarian dan pemanfaatan sumber daya, lingkungan prestasi, proses komunikasi, kepemimpinan dan pengambilan keputusan, serta adaptasi dan inovasi organisasi. Penelitian kualitatif ini menggunakan pendekatan studi kasus. Teknik analisis data yang digunakan adalah analisis data model Miles dan Huberman, yang terdiri atas reduksi data, display/penyajian data, dan kesimpulan/verifikasi. Hasil penelitian menunjukkan bahwa efektivitas organisasi pada UPT Diklat koperasi dan UMKM belum berjalan secara baik, hal ini dapat dilihat dari beberapa hal antara lain, belum adanya tenaga spesialisasi pengelola diklat dan tenaga khusus (sarjana di bidang perkoperasian dan kondisi lingkungan kerja (lingkungan prestasi pada UPT Diklat koperasi dan UMKM yang belum efektif. Penempatan pegawai juga belum tepat, mutasi ke UPT Diklat Koperasi dan UMKM tidak memperhatikan latar belakang pendidikan dan spesialisasi/keahlian pegawai sehingga membutuhkan waktu dalam proses penyesuaian serta menurunkan jumlah pelaksanaan diklat dikarenakan keterbatasan alokasi dana.

  8. ANALISIS DAYA SAING KEDELAI INDONESIA

    Directory of Open Access Journals (Sweden)

    Sarwono Sarwono

    2014-09-01

    Full Text Available RCA (Revealed Comparative Advantage index of soybean in Indonesia from 1983 up to 2013 is less than one, mostly. It means that the competitiveness of soybean in Indonesia is low. The purpose of this study is to analyze the factors influence the soybean competitiveness. OLS (Ordinary Least Square was used as the analysis method. Hypotheses test based on that analysis model is not bias, so that, classic divergence test is needed. It is for getting the Best Linier Unbiased Estimator (BLUE appraisal. T statistic and F statistic were also applied. The result of this research shows that production and export have positive and significant influence. In addition, exchange rate and government policy do not influence the Indonesia soybean competitiveness.Indeks RCA (Revealed Comparative Advantage kedelai Indonesia dari tahun 1983-2013 kecenderungan bernilai kurang dari satu yang berarti daya saing kedelai Indonesia rendah.Penelitian ini bertujuan untuk menganalisis faktor-faktor yang mempengaruhi daya saing kedelai Indonesia.Metode analisis yang digunakan adalah Ordinary Least Square (OLS.Pengujian hipotesis berdasarkan model analisis tersebut tidak bias maka perlu dilakukan uji penyimpangan klasik yang tujuannya agar diperoleh penaksiran yang bersifat Best Linier Unbiased Estimator (BLUE.Pengujian statistik menggunakan uji t statistikdan uji f statistik.Hasil penelitian ini menunjukkan bahwa produksi dan ekspor berpengaruh secara positif dan signifikan terhadap daya saing kedelai Indonesia. Nilai tukar rupiah dan kebijakan pemerintah tidak berpengaruh terhadap daya saing kedelai Indonesia.

  9. Analisis Harmonisa Inverter PWM Satu Fasa

    OpenAIRE

    Rejeki Simanjorang

    2008-01-01

    Pada tesis ini dianalisis harmonisa inverter PWM satu fasa. Inverter PWM satu fasa yang akan ditinjau adalah inverter satu fasa jembatan penuh (konvensional) dan inverter komposit. Analisis difokuskan pada penentuan pola penyaklaran yang optimum agar pembangkitan harmonisa dan switching losses inverter rendah. Untuk menentukan pola penyaklaran optimum maka dilakukan analisis yang berbasis pada rangkaian ekivalen harmonisa inverter satu fasa. Dengan menggunakan pola penyaklaran optimum, kedua ...

  10. Comparative analysis to determine asphalt density and content, using nuclear and traditional methods; Analisis comparativo para la determinacion de densidad y contenido de asfalto, mediante metodo nuclear y metodo tradicional

    Energy Technology Data Exchange (ETDEWEB)

    Margffoy S, F R; Robayo S, A M

    1989-07-01

    Quality control for flex pavement construction in Colombia for asphaltic mix, as well as for granular and granular sub base layers is made by means of methods that does not guarantee the quality of the job, due to the difficult execution of tests, which impede more to be done or due to inherent problems of the test process. Thanks to the inherent characteristics and advantages of nuclear techniques, those become the optimal alternative to this quality control job. The present research project has been developed with the objective of justifying the use of new technologies applied to road construction; making a comparative analysis between traditional methods used in our country and nuclear techniques that have been using in United States with great success in quality control in road construction.

  11. Impact analysis of modifying the composition of the nuclear fuel of a BWR with beryllium oxide; Analisis del impacto de modificar la composicion del combustible nuclear de un BWR con oxido de berilio

    Energy Technology Data Exchange (ETDEWEB)

    Gallardo V, J. M.; Morales S, J. B., E-mail: euqrop@hotmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2013-10-15

    The beryllium oxide (Be O) presents excellent physical properties, especially its high thermal conductivity that contrasts clearly with that of the uranium dioxide (UO{sub 2}) used at the present as fuel in a great number of nuclear plants. The present work models a nuclear reactor cooled by light water in boiling with two external recirculation loops (BWR/5) using the code for the transitory analysis and postulated accidents Trac-B F1, implementing a UO{sub 2} mixture and different fractions of Be O, with the objective of improving the thermal conductivity of the fuel. The numeric results and the realized analyses indicate that when adding a fraction in volume of 10% the central temperature decreases in 30.4% in stationary state, while during the large break loss of coolant accident the peak cladding temperature diminishes in 7%. Although the real interaction of the mixture has not been determined experimentally, the obtained results are promising. (Author)

  12. Environmental impact of nuclear industry and power generation in the Russian Federation: assessment of contribution to general damage

    International Nuclear Information System (INIS)

    Vetrov, V.

    2002-01-01

    wastewater, agriculture, communal effluents, wash-off from polluted watershed. Among the vast amount of surface freshwater resource in Russia, it is only in the Techa River (The Mayak Combined Works impact zone, Urals, Ob river basin) that the technogenous 90 Sr concentrations are close to or exceeds MPC for drinking water. The total area of forests loss in the RF as a result of radioactive contamination throughout the nuclear history is approximately one order of magnitude less than those distracted by cumulative man-made factors during just 1998. Therefore, a simple analysis allows a conclusion that the leading nuclear industry enterprises are out of the list of major sources of hazardous pollution and environmental damage in the provinces of their locations

  13. Economic analysis of the hydrogen production by means of the thermo-chemistry process iodine-sulfur with nuclear energy; Analisis economico de la produccion de hidrogeno mediante el proceso termoquimico yodo-azufre con energia nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Solorzano S, C.; Francois L, J. L., E-mail: cuausos@comunidad.unam.mx [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac No. 8532, Col. Progreso, 62550 Jiutepec, Morelos (Mexico)

    2011-11-15

    In this work an economic study was realized about a centralized plant of hydrogen production that works by means of a thermo-chemistry cycle of sulfur-iodine and uses heat coming from a nuclear power plant of IV generation, with base in the software -Hydrogen Economic Evaluation Programme- obtained through the IAEA. The sustainable technology that is glimpsed next for the generation of hydrogen is to great scale and based on processes of high temperature coupled to nuclear power plants, being the most important the cycle S-I and the electrolysis to high temperature, for what objective references are presented that can serve as base for the taking of decisions for its introduction in Mexico. After detailing the economic models that uses the software for the calculation of the even cost of hydrogen production and the characteristics, so much of the nuclear plant constituted by fourth generation reactors, as of the plant of hydrogen production, is proposed a -base- case, obtaining a preliminary even cost of hydrogen production with this process; subsequently different cases are studied starting from which are carried out sensibility analysis in several parameters that could rebound in this cost, taking into account that these reactors are still in design and planning stages. (Author)

  14. Those who 'Cry Wolf' about nuclear safety damage their own credibility

    Energy Technology Data Exchange (ETDEWEB)

    Shepherd, John [nuclear 24, Redditch (United Kingdom)

    2016-06-15

    Do you recall the fable of the boy who cried wolf? I was reminded of this following the latest call by Germany's Federal Environment Minister, Barbara Hendricks, for Belgium to take two of its nuclear reactors off the grid, citing ''questions'' about the units' safety. Those in positions of power and influence in one country should take care to be as responsible in their dealings with their neighbours as they are in handling domestic matters of state. Those who see 'danger' where there is none are not being good neighbours. They are generating fear and alarm without good cause and should mind their own business.

  15. International Court of Justice on Potential Transboundary Damage and its Consequences in Nuclear Law

    International Nuclear Information System (INIS)

    Cletienne, M.

    2010-01-01

    On 4 May 2006, Argentina filed in the International Court of Justice ('ICJ') an application instituting proceedings against Uruguay. Argentina claimed that Uruguay, by authorizing the construction of a pulp mill (the 'CMB mill') and the construction and commissioning of another pulp mill (the 'Orion mill'), breached its obligations under the 1975 Statute of the River Uruguay, a treaty between Argentina and Uruguay, notably the obligation to take all necessary measures for the optimum and rational utilisation of the River Uruguay. On 20 April 2010,1 the court rendered its decision settling this environmental dispute between Argentina and Uruguay. This paper will first summarize the judgement and then consider the main contribution of this decision to international environmental law, e.g. the recognition of an international customary rule to conduct an environmental impact assessment. Finally, the potential consequences of the decision in nuclear law will be addressed in the last part

  16. Qualification of the WIMS lattice code, for the design, operation and accident analysis of nuclear reactors; Calificacion del programa WIMS de calculo neutronico para diseno, seguimiento de operacion y analisis de accidentes de reactores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Lerner, A M [Ente Nacional Regulador Nuclear, Buenos Aires (Argentina)

    1997-12-31

    A basic problem in nuclear reactor physics in that of the description of the neutron population behaviour in the multiplicative medium of a nuclear fuel. Due to the magnitude of the physical problem involved and the present degree of technological evolution regarding computing resources, of increasing complexity and possibilities, the calculation programs or codes have turned to be a basic auxiliary tool in reactor physics. In order to analyze the global problem, several aspects should be taken into consideration. The first aspect to be considered is that of the availability of the necessary nuclear data. The second one is the existence of a variety of methods and models to perform the calculations. The final phase for this kind of analysis is the qualification of the computing programs to be used, i.e. the verification of the validity domain of its nuclear data and the models involved. The last one is an essential phase, and in order to carry it on great variety of calculations are required, that will check the different aspects contained in the code. We here analyze the most important physical processes that take place in a nuclear reactor cell, and we consider the qualification of the lattice code WIMS, that calculates the neutronic parameters associated with such processes. Particular emphasis has been put in the application to natural uranium fuelled reactor, heavy water cooled and moderated, as the Argentinean power reactors now in operation. A wide set of experiments has been chosen: a.-Fresh fuel in zero-power experimental facilities and power reactors; b.-Irradiated fuel in both types of facilities; c.-Benchmark (prototype) experiments with loss of coolant. From the whole analysis it was concluded that for the research reactors, as well as for the heavy water moderated power reactors presently operating in our country, or those that could operate in a near future, the lattice code WIMS is reliable and produces results within the experimental values and

  17. Damage evaluation of 500 MWe Indian pressurized heavy water reactor nuclear containment for air craft impact

    International Nuclear Information System (INIS)

    Kukreja, Mukesh; Singh, R.K; Vaze, K.K; Kushwaha, H.S.

    2003-01-01

    Non-linear transient dynamic analysis of 500 MWe Indian Pressurized Heavy Water Reactor (PHWR) nuclear containment has been carried out for the impact of Boeing and Airbus category of aircraft operated in India. The impulsive load time history is generated based on the momentum transfer of the crushable aircraft (soft missiles) of Boeing and Airbus families on the containment structure. The case studies include the analyses of outer containment wall (OCW) single model and the combined model with outer and inner containment wall (ICW) for impulsive loading due to aircraft impact. Initially the load is applied on OCW single model and subsequently the load is transferred to ICW after the local perforation of the OCW is noticed in the transient simulation. In the first stage of the analysis it is demonstrated that the OCW would suffer local perforation with a peak local deformation of 117 mm for impact due to B707-320 and 196 mm due to impact of A300B4 without loss of the overall integrity. However, this first barrier (OCW) cannot absorb the full impulsive load. In the second stage of the analysis of the combined model, the ICW is subjected to lower impulse duration as the load is transferred after 0.19 sec for B707-320 and 0.24 sec for A300B4 due to the local perforation of OCW. This results in the local deformation of approx. 115 mm for B707-320 and 124 mm for A300B4 in ICW and together both the structures (OCW and ICW) are capable of absorbing the full impulsive load. The analysis methodology evolved in the present work would be useful for studying the behaviour of double containment walls and multi barrier structural configurations for aircraft impact with higher energies. The present analysis illustrates that with the provision of double containments for Indian nuclear power plants, adequate reserve strength is available for the case of an extremely low probability event of missile impact generated due commercial aircraft operated in India. (author)

  18. Morocco. Act no. 12-02 on civil liability for nuclear damage. Promulgated on 7 january 2005. Chapter 1. General provisions

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    Three texts concern Morocco with the Act on civil liability for Nuclear damage (2005), International Atomic energy Agency with the code of conduct on the safety of research reactors (2004), United Nations with U.N. Security Council Resolution 1540 (2004). (N.C.)

  19. Economic models of compensation for damages caused by nuclear accidents: some lessons for the revision of the Paris and Vienna Conventions

    International Nuclear Information System (INIS)

    Faure, Michael G.

    1995-01-01

    Alternative systems of compensation for damages caused by nuclear accidents have been proposed. In respect, the question merits attention to whether these alternative models of compensation discussed in the economic literature could be implemented when discussing the revision of the Paris and Vienna Conventions. 55 refs., 1 tab

  20. Analysis of environmental impact phase in the life cycle of a nuclear power plant; Analisis de la fase de impacto ambiental en el ciclo de vida de una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez del M, C.

    2015-07-01

    The life-cycle analysis covers the environmental aspects of a product throughout its life cycle. The focus of this study was to apply a methodology of life-cycle analysis for the environmental impact assessment of a nuclear power plant by analyzing international standards ISO 14040 and 14044. The methodology of life-cycle analysis established by the ISO 14044 standard was analyzed, as well as the different impact assessment methodologies of life cycle in order to choose the most appropriate for a nuclear power plant; various tools for the life-cycle analysis were also evaluated, as is the use of software and the use of databases to feed the life cycle inventory. The functional unit chosen was 1 KWh of electricity, the scope of analysis ranging from the construction and maintenance, disposal of spent fuel to the decommissioning of the plant, the manufacturing steps of the fuel were excluded because in Mexico is not done this stage. For environmental impact assessment was chosen the Recipe methodology which evaluates up to 18 impact categories depending on the project. In the case of a nuclear power plant were considered only categories of depletion of the ozone layer, climate change, ionizing radiation and formation of particulate matter. The different tools for life-cycle analysis as the methodologies of impact assessment of life cycle, different databases or use of software have been taken according to the modeling of environmental sensitivities of different regions, because in Mexico the methodology for life-cycle analysis has not been studied and still do not have all the tools necessary for the evaluation, so the uncertainty of the data supplied and results could be higher. (Author)

  1. Nuclear techniques (PIXE and RBS) applied to analysis of pre hispanic metals of the Templo Mayor at Tenochtitlan; Tecnicas nucleares (PIXE y RBS) aplicadas al analisis de metales prehispanicos del Templo Mayor de Tenochtitlan

    Energy Technology Data Exchange (ETDEWEB)

    Mendez U, I.; Tenorio, D.; Galvan, J.L. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2000-07-01

    This work has the objective of determining by means of the utilization of nuclear techniques (PIXE and RBS) the composition and the alloy type of diverse aztec ornaments corresponding to Post classic period, they were manufactured principally with copper and gold such as bells, beads and disks; all they belonging at 9 oblations of Templo Mayor of Tenochtitlan. It is presented here briefly the historical and archaeological antecedents of the devices as well as the analytical methods for conclude with the results obtained. (Author)

  2. Design of nuclear fuel cells by means of a statistical analysis and a sensibility study; Diseno de celdas de combustible nuclear mediante un analisis estadistico y un estudio de sensibilidad

    Energy Technology Data Exchange (ETDEWEB)

    Jauregui C, V. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98060 Zacatecas (Mexico); Castillo M, J. A.; Ortiz S, J. J.; Montes T, J. L.; Perusquia del C, R., E-mail: alejandro.castillo@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2013-10-15

    This work contains the results of the statistical analysis realized to study the nuclear fuel cells performance, considering the frequencies for the election of fuel bars used in the design of the same ones. The election of the bars used for the cells design are of 3 types, the first election shows that to the plotting the respective frequency is similar to a normal distribution, in the second case the frequencies graph is of type inverted square X{sup 2} and the last election is when the bars are chosen in aleatory form. The heuristic techniques used for the cells design were the neural networks, the ant colonies and a hybrid between the dispersed search and the trajectories re-linkage. To carry out the statistical analysis in the cells design were considered the local power peak factor and the neutron infinite multiplication factor (k∞) of this. On the other hand, the performance of the designed cells was analyzed when verifying the position of the bars containing gadolinium. The results show that is possible to design cells of nuclear fuel with a good performance, when considering the frequency of the bars used in their design. (Author)

  3. Analysis of the scenarios with the participation of nuclear energy in the Mexican electric sector using the Decades program; Analisis de escenarios con la participacion de la energia nuclear en el sector electrico mexicano utilizando el programa DECADES

    Energy Technology Data Exchange (ETDEWEB)

    Sosa P, E.; Trejo G, M.G.; Martin del Campo M, C.; Francois L, J.L. [FI-UNAM, 04500 Mexico D.F. (Mexico)] e-mail: edithsosa@hotmail.com

    2003-07-01

    At the moment the energetic planning demands a technical, economic and environmental analysis of the different options of electric generation to be able to find the best solution of supply and energy readiness, already that it is indispensable for the development of the productive activities and to assure the competitiveness of the economy of a country. The expansion analyses of the Mexican Electric Sector its are carried out daily in the Federal Commission of Electricity (CFE) with some programs, among them Decades. However, up to where we have information only there is been considering a type of reactor like candidate being that exist several options that show promising characteristics for what its should be considered in the analyses. With this work its got rich the Decades database of the nuclear power stations that can be used as candidates to consider in the variable system of the expansion studies. Its have been carried out some comparative analysis between two types of nuclear centrals that at the moment offer in the market, specifically the AP600 type PWR reactor of 600 M We and the one BWR with capacity of 1300 M We. Later on it is sought to analyze two or three scenarios of the system of electric generation in Mexico to a term of twenty or twenty-five years. (Author)

  4. RAD18 and associated proteins are immobilized in nuclear foci in human cells entering S-phase with ultraviolet light-induced damage

    International Nuclear Information System (INIS)

    Watson, Nicholas B.; Nelson, Eric; Digman, Michelle; Thornburg, Joshua A.; Alphenaar, Bruce W.; McGregor, W. Glenn

    2008-01-01

    Proteins required for translesion DNA synthesis localize in nuclear foci of cells with replication-blocking lesions. The dynamics of this process were examined in human cells with fluorescence-based biophysical techniques. Photobleaching recovery and raster image correlation spectroscopy experiments indicated that involvement in the nuclear foci reduced the movement of RAD18 from diffusion-controlled to virtual immobility. Examination of the mobility of REV1 indicated that it is similarly immobilized when it is observed in nuclear foci. Reducing the level of RAD18 greatly reduced the focal accumulation of REV1 and reduced UV mutagenesis to background frequencies. Fluorescence lifetime measurements indicated that RAD18 and RAD6A or polη only transferred resonance energy when these proteins colocalized in damage-induced nuclear foci, indicating a close physical association only within such foci. Our data support a model in which RAD18 within damage-induced nuclear foci is immobilized and is required for recruitment of Y-family DNA polymerases and subsequent mutagenesis. In the absence of damage these proteins are not physically associated within the nucleoplasm

  5. Inducibility of nuclear Rad51 foci after DNA damage distinguishes all Fanconi anemia complementation groups from D1/BRCA2

    Energy Technology Data Exchange (ETDEWEB)

    Godthelp, Barbara C. [Department of Toxicogenetics, Leiden University Medical Center, Wassenaarseweg 72, NL-2333 AL Leiden (Netherlands); Wiegant, Wouter W. [Department of Toxicogenetics, Leiden University Medical Center, Wassenaarseweg 72, NL-2333 AL Leiden (Netherlands); Waisfisz, Quinten [Department of Clinical Genetics and Human Genetics, Free University Medical Center, Van der Boechorststraat 7, NL-1081 BT Amsterdam (Netherlands); Medhurst, Annette L. [Department of Clinical Genetics and Human Genetics, Free University Medical Center, Van der Boechorststraat 7, NL-1081 BT Amsterdam (Netherlands); Arwert, Fre [Department of Clinical Genetics and Human Genetics, Free University Medical Center, Van der Boechorststraat 7, NL-1081 BT Amsterdam (Netherlands); Joenje, Hans [Department of Clinical Genetics and Human Genetics, Free University Medical Center, Van der Boechorststraat 7, NL-1081 BT Amsterdam (Netherlands); Zdzienicka, Malgorzata Z. [Department of Toxicogenetics, Leiden University Medical Center, Wassenaarseweg 72, NL-2333 AL Leiden (Netherlands) and Department of Molecular Cell Genetics, Collegium Medicum, N. Copernicus University, Bydgoszcz (Poland)]. E-mail: m.z.zdzienicka@lumc.nl

    2006-02-22

    Fanconi anemia (FA) is a cancer susceptibility disorder characterized by chromosomal instability and hypersensitivity to DNA cross-linking agents. So far 11 complementation groups have been identified, from which only FA-D1/BRCA2 and FA-J are defective downstream of the central FANCD2 protein as cells from these groups are capable of monoubiquitinating FANCD2. In this study we show that cells derived from patients from the new complementation groups, FA-I, FA-J and FA-L are all proficient in DNA damage induced Rad51 foci formation, making the cells from FA-D1/BRCA2 patients that are defective in this process the sole exception. Although FA-B patient HSC230 was previously reported to also have biallelic BRCA2 mutations, we found normal Rad51 foci formation in cells from this patient, consistent with the recent identification of an X-linked gene being mutated in four unrelated FA-B patients. Thus, our data show that none of the FA proteins, except BRCA2, are required to sequester Rad51 into nuclear foci. Since cells from the FA-D1 and FA-J patient groups are both able to monoubiquitinate FANCD2, the 'Rad51 foci phenotype' provides a convenient assay to distinguish between these two groups. Our results suggest that FANCJ and FANCD1/BRCA2 are part of the integrated FANC/BRCA DNA damage response pathway or, alternatively, that they represent sub-pathways in which only FANCD1/BRCA2 is directly connected to the process of homologous recombination.

  6. Inducibility of nuclear Rad51 foci after DNA damage distinguishes all Fanconi anemia complementation groups from D1/BRCA2

    International Nuclear Information System (INIS)

    Godthelp, Barbara C.; Wiegant, Wouter W.; Waisfisz, Quinten; Medhurst, Annette L.; Arwert, Fre; Joenje, Hans; Zdzienicka, Malgorzata Z.

    2006-01-01

    Fanconi anemia (FA) is a cancer susceptibility disorder characterized by chromosomal instability and hypersensitivity to DNA cross-linking agents. So far 11 complementation groups have been identified, from which only FA-D1/BRCA2 and FA-J are defective downstream of the central FANCD2 protein as cells from these groups are capable of monoubiquitinating FANCD2. In this study we show that cells derived from patients from the new complementation groups, FA-I, FA-J and FA-L are all proficient in DNA damage induced Rad51 foci formation, making the cells from FA-D1/BRCA2 patients that are defective in this process the sole exception. Although FA-B patient HSC230 was previously reported to also have biallelic BRCA2 mutations, we found normal Rad51 foci formation in cells from this patient, consistent with the recent identification of an X-linked gene being mutated in four unrelated FA-B patients. Thus, our data show that none of the FA proteins, except BRCA2, are required to sequester Rad51 into nuclear foci. Since cells from the FA-D1 and FA-J patient groups are both able to monoubiquitinate FANCD2, the 'Rad51 foci phenotype' provides a convenient assay to distinguish between these two groups. Our results suggest that FANCJ and FANCD1/BRCA2 are part of the integrated FANC/BRCA DNA damage response pathway or, alternatively, that they represent sub-pathways in which only FANCD1/BRCA2 is directly connected to the process of homologous recombination

  7. Analysis of a Multi-Venturi filter for the venting of the primary container of a nuclear reactor; Analisis de un filtro multiventuri para el venteo del contenedor primario de un reactor nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Reyes G, A. A.; Sainz M, E.; Ortiz V, J., E-mail: alejandroantonioreyess@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    Since the Chernobyl nuclear accident, European nuclear power plants have opted to install filters in the containment vent pipes, whose function is to help mitigate the consequences of a severe accident, by means of the controlled depressurization of the containment passively through of a containment filtering vent system. These systems are designed to relieve the internal pressure of containment by deliberately opening pressure relief devices, either a valve or rupture disk during a severe accident and being channeled to the filtering unit. In this work, the hydraulic response of a liquid gas washing filtration system is evaluated, since this information is necessary to estimate the effect of the increase of the containment pressure on the venting capacity of the vent pipes. Through CFD simulation, using the programs with open source license CaeLinux-2014 and OpenFoam, the hydrodynamic characteristics of the Multi-Venturi system were obtained for the washing of the gases coming from the containment, which could be included in the general model of the vent pipe. Representative models of the venturi tubes of each concentric sector that are part of the washing system were generated and by parametric calculations the average mass expense established by each venturi was estimated, according to its dimensions and depth to which is located inside the tank. In the same way, the pressure and mass expense required to activate each concentric sector was calculated according to the pressure and mass load from the containment, in order to estimate the maximum expenditure that is established through the filter. The velocity profiles and the characteristic pressure at which each sector operates were also calculated, as well as the local and global discharge pressure drop. (Author)

  8. Safety and dose management during decommissioning of a fire damaged nuclear reactor

    International Nuclear Information System (INIS)

    Pomfret, D.G.

    2000-01-01

    Windscale Piles 1 and 2 in Cumbria in the UK were constructed in the early 1950s. They were not intended to produce electricity but were for military purposes only. They were graphite-moderated, air-cooled reactors with horizontal fuel channels fuelled with uranium rods clad in finned aluminium. In October 1957, Windscale Pile 1 suffered a core fire during a planned release of Wigner energy and both Piles were subsequently closed down. Following the fire, Pile 2 was defuelled entirely and as much fuel as was possible was removed from Pile 1. However, it is estimated that up to 15 Te of fuel remains in the core, a large proportion of which is located in the central Fire Affected Zone (FAZ). The condition of the fuel and graphite moderator in the FAZ is not known. It is possible that the moderator could contain voidage, greatly reduced density graphite and fused materials in a disordered matrix. It is probable that there is residual Wigner energy in the graphite. Use of water as part of the attempt to extinguish the fire, together with the possibility that the solidification of molten materials or other local sealing mechanisms could have excluded air mean that uranium hydrides, carbides and other pyrophorics may be present within the core. Pile 1 is now being decommissioned and a considerable amount of preparatory work has already been carried out during Phase 1. Phase 2 decommissioning, which will remove the residual fuel, the moderator and associated steelwork, condition the wastes and place them in a purpose built store is now underway. This work will be carried out for the site licensee, the United Kingdom Energy Authority, by a consortium of British Nuclear Fuels plc, Rolls Royce and NUKEM. This paper will describe the methods to be used to decommission Pile 1 and the systems and procedures which will be used to ensure that it is done safely and with the lowest reasonably practicable environmental impact. It will also describe the methods which will be used to

  9. ANALISIS IMPOR BERAS DI INDONESIA

    Directory of Open Access Journals (Sweden)

    Ratih Kumala Sari

    2014-10-01

    Full Text Available Abstrak ___________________________________________________________________ Salah satu kebijakan pemerintah untuk memenuhi kebutuhan beras yaitu dengan menggenjot produksi beras dalam negeri. Namun dengan semakin meningkatnya jumlah penduduk akan meningkatkan permintaan terhadap beras dan upaya peningkatan produktivitas dalam negeri tidak dapat memenuhi kebutuhan beras dalam negeri. Sehingga untuk menutupi kekurangan tersebut pemerintah mengambil keputusan untuk melakukan impor beras dari negara lain. Akan tetapi pada kenyataannya impor beras dilakukan ketika data statistik menunjukkan bahwa Indonesia sedang mengalami surplus beras. Penelitian ini bertujuan untuk mengetahui faktor-faktor apa saja yang mempengaruhi impor beras di Indonesia. Metode analisis yang digunakan adalah analisis regresi linier berganda dengan model Error Correction Model (ECM. Berdasarkan hasil penelitian disimpulkan bahwa secara parsial maupun secara bersama-sama produksi beras, konsumsi beras, harga beras dalam negeri dan nilai tukar rupiah terhadap dollar AS berpengaruh dan signifikan terhadap impor beras di Indonesia. Abstract ___________________________________________________________________ One of the government’s policy to fulfill the need of rice is to boost the domestic production. However, by increasing the population, the demand of rice will also increase and the effort of increasing the domestic productivity cannot supply domestic rice need. So, to cover the shortage the government make decision to import rice from other countries. Yet, in fact importing rice is occurred when the statistical data showed that the supply of rice in Indonesia is surplus. The purpose of this research is necessary to study the factors which influence the import of rice in Indonesia. The analysis method used is multiple linear regression analysis model with Error Correction Model (ECM. Based on the research proven that partially or jointly the production, the consumption, the

  10. Hydrogen peroxide-induced DNA damage is independent of nuclear calcium but dependent on redox-active ions.

    Science.gov (United States)

    Jornot, L; Petersen, H; Junod, A F

    1998-01-01

    In cells undergoing oxidative stress, DNA damage may result from attack by .OH radicals produced by the Fenton reaction, and/or by nucleases activated by nuclear calcium. In the present study, the participation of these two mechanisms was investigated in HeLa cells. Nuclear-targeted aequorin was used for selectively monitoring Ca2+ concentrations within the nuclei ([Ca2+]n), in conjunction with the cell-permeant calcium chelator bis-(o-aminophenoxy)ethane-N,N,N', N'-tetraacetic acid acetoxymethyl ester (BAPTA/AM), the lipid-soluble broad-spectrum metal chelator with low affinity for Ca2+ and Mg2+ N,N,N',N'-tetrakis(2-pyridylmethyl)ethylenediamine (TPEN), and the high-affinity iron/copper chelator 1, 10-phenanthroline (PHE). In Ca2+-containing medium, H2O2 induced extensive DNA strand breaks and an increase in [Ca2+]n that was almost identical to that observed in the cytosol ([Ca2+]c). In cells bathed in Ca2+-free/EGTA medium, in which the increases in [Ca2+]n and [Ca2+]c due to H2O2 were significantly reduced, similar levels of DNA fragmentation also occurred. In cells preloaded with BAPTA/AM or TPEN, the small increase of [Ca2+]n normally elicited by H2O2 in Ca2+-free medium was completely buffered, and DNA damage was largely prevented. On the other hand, pretreatment with PHE did not affect the calcium response in the nuclei, but completely prevented DNA strand breakage induced by H2O2. Re-addition of 100 microM CuSO4 and 100 microM FeSO4 to TPEN- and PHE-treated cells prior to H2O2 challenge reversed the effect of TPEN and PHE, whereas 1 mM was necessary to negate the effect of BAPTA/AM. The levels of DNA strand breakage observed, however, did not correlate with the amounts of 8-hydroxy 2'-deoxyguanosine (8-OHdG): H2O2 did not produce 8-OHdG, whereas PHE alone slightly increased 8-OHdG levels. CuSO4 and FeSO4 enhanced the effects of PHE, particularly in the presence of H2O2. Exposure of cells to a mixture of CuSO4/FeSO4 also resulted in a significant increase in

  11. Analysis of the implementation of a sand bed type filter for the venting of a nuclear power plant; Analisis de la implementacion de un filtro tipo lecho de arena para el venteo de una central nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Cuevas V, D.; Sainz M, E.; Ortiz V, J., E-mail: delfy.cu@gmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    The filtered venting of the containment has been adopted in European countries to mitigate the consequences derived from the excess pressure of the containment during a severe accident. When venting has taken place, the fission products are released directly into the environment, unless a filter is placed in the path of the same, so various types of filters are used to trap the fission products. The containment venting filters currently installed use different filtering technologies that involve more than one medium. Those who use water as the first stage of filtration are called wet systems, are equipped with additional stages to eliminate water drops and emissions of fine aerosols, and may even be equipped with an element that contains certain means of absorption for the gaseous iodine species filtration. Other designs, based on deep bed filtration as the main retention stage, called dry filters; use metal fiber, ceramic or sand filtration media to trap aerosols. The present work evaluates the hydraulic characteristics of the sand bed type filter designed by EDF as a candidate to be installed in the containment of the BWR Mark II (primary containment type of the Laguna Verde nuclear power plant). The evaluation of the sand bed filter was performed using the OpenFOAM open source software package. Models of each zone of the filtering device were generated and by means of a series of parametric calculations of computational fluid mechanics, the relevant hydrodynamic characteristics of the device were obtained, such as pressure drops against mass flow and pressure fields and velocity under different operating conditions. On the other hand, the validation of the sand bed filter model was made when comparing the results of experimental tests carried out in a sand column of the PITEAS program (1985-1986) against the simulation in OpenFOAM. The results obtained are very close to those obtained experimentally. (Author)

  12. Liability for nuclear damage: financial and definitional limitations with particular reference to the EEC rules prohibiting subsidies and anti-competitive practices and agreements

    International Nuclear Information System (INIS)

    Sands, P.

    1992-01-01

    In March 1990 the Commission of the European Communities (EEC) held that a package of state aids (subsidies) to the United Kingdom nuclear industry were compatible with Article 92 of the EEC Treaty. The decision was significant because it held that the package of measures constituted ''state aids'' and that the nuclear industry was subject to Article 92 of the EEC Treaty; and it set some of the parameters to determine the conditions under which the Commission will authorise such state aids. The decision has implications for the emerging rules governing civil liability for damage caused by waste, including nuclear waste, currently being prepared by the EC Commission and the International Atomic Energy Agency Standing Committee on Nuclear Liability. (author)

  13. Analysis of the microstructural evolution of the damage by neutron irradiation in the pressure vessel of a nuclear power reactor BWR

    International Nuclear Information System (INIS)

    Moranchel y R, M.

    2012-01-01

    Nuclear reactor pressure vessel type BWR, installed in Mexico and in many other countries, are made of an alloy of low carbon steel. The American Society for Testing and Materials (Astm) classifies this alloy as A533-B, class 1. Both the vessel and other internal structures are continuously exposed to the neutron flux from the reactions of fission in nuclear fuel. A large number of neutrons reach the vessel and penetrate certain depth depending on their energy. Its penetration in the neutron collides with the nuclei of the atoms out of their positions in the crystal lattice of steel, producing vacancies, interstitial, segregations, among other defects, capable of affecting its mechanical properties. Analyze the micro-structural damage to the vessel due to neutron irradiation, is essential for reasons of integrity of this enclosure and safety of any nuclear power plant. The objective of this thesis work is theoretical and experimentally determine the microstructural damage of a type nuclear reactor vessel steel BWR, due to neutron radiation from the reactor core, using microscopic and spectroscopic techniques as well as Monte Carlo simulation. Microscopy Optical, Scanning Electron Microscopy, Transmission Electron Microscopy, Energy Dispersion of X-rays Spectrometry and X-rays Diffractometry were the techniques used in this research. These techniques helped in the characterization of both the basis of design of pressure vessel steel and steel irradiated, after eight years of neutron irradiation on the vessel, allowing know the surface morphology and crystal structures of the previous steel and post-irradiation, analyze the change in the microstructure of the steel vessel, morphological damage to surface level in an irradiated sample, among which are cavities in the order of microns produced by Atomic displacements due to the impact of neutronic, above all in the first layers of thickness of the vessel, the effect of swelling, regions of greater damage and Atomic

  14. Diffusional mass transport phenomena in the buffer material and damaged zone of a borehole wall in an underground nuclear fuel waste vault

    International Nuclear Information System (INIS)

    Page, S.; Cheung, S.C.H.

    1983-06-01

    The effects of the geometry of the borehole and the characteristics of the damaged borehole rock wall on the movement of the radionuclides from an underground nuclear waste vault have been studied. The results show that radionuclide transport will occur mainly through the buffer into the damaged zone of the borehole wall. As the degree of facturing of the damaged zone increases, the total radionuclide flux will increase up to a limit which can be approximated by a one-dimensional radial diffusion model. For large degrees of fracturing of the damaged zone, an increase in the radial buffer material thickness will decrease the total flux, whereas, for small degrees of fracturing, an increase in the radial buffer thickness may slightly increase the total flux. Increasing the vertical buffer thickness will significantly decrease the total flux when the degree of fracturing of the damaged zone is small. An increase in the vertical extent of the damaged zone will cause an increase in total flux

  15. Risk analysis in the chemical industry; Analisis de riesgos en la industria quimica

    Energy Technology Data Exchange (ETDEWEB)

    Rea Soto, Rogelio; Sandoval Valenzuela, Salvador [Instituto de Investigaciones Electricas, Temixco, Morelos (Mexico)

    2000-07-01

    The Instituto de Investigaciones Electricas has a group of risk analysis (GAR), specialized in the most advanced methodologies to apply them in diverse industries of the productive sector, such as the nuclear, the oil and the chemical industries. In this work the integrated methodology that the GAR uses to make risk analysis in the chemical and oil industries is described. These analyses have as an objective to make a meticulous evaluation of the system design, the operation practices, the maintenance and inspection policies and the emergency plans. [Spanish] El Instituto de Investigaciones Electricas cuenta con un grupo de analisis de riesgo (GAR), especializado en las metodologias mas avanzadas para aplicarlas en diversas industrias del sector productivo, como lo son la nuclear, la petrolera y la quimica. En este trabajo se describe la metodologia integrada que el GAR utiliza para realizar analisis de riesgos en las industrias quimica y petrolera. Estos analisis tienen como objetivo realizar una minuciosa evaluacion del diseno del sistema, las practicas de operacion, las politicas de mantenimiento e inspeccion y los planes de emergencia.

  16. A three-dimensional methodology for the assessment of neutron damage and nuclear energy deposition in graphite components of advanced gas-cooled reactors

    Energy Technology Data Exchange (ETDEWEB)

    Morgan, D.O.; Robinson, A.T.; Allen, D.A.; Picton, D.J.; Thornton, D.A. [TCS, Serco, Rutherford House, Olympus Park, Quedgeley, Gloucester, Gloucestershire GL2 4NF (United Kingdom); Shaw, S.E. [EDF Energy, Barnet Way, Barnwood, Gloucester GL4 3RS (United Kingdom)

    2011-07-01

    This paper describes the development of a three-dimensional methodology for the assessment of neutron damage and nuclear energy deposition (or nuclear heating) throughout the graphite cores of the UK's Advanced Gas-cooled Reactors. Advances in the development of the Monte Carlo radiation transport code MCBEND have enabled the efficient production of detailed fully three-dimensional models that utilise three-dimensional source distributions obtained from Core Follow data supplied by the reactor physics code PANTHER. The calculational approach can be simplified to reduce both the requisite number of intensive radiation transport calculations, as well as the quantity of data output. These simplifications have been qualified by comparison with explicit calculations and they have been shown not to introduce significant systematic uncertainties. Simple calculational approaches are described that allow users of the data to address the effects on neutron damage and nuclear energy deposition predictions of the feedback resulting from the mutual dependencies of graphite weight loss and nuclear energy deposition. (authors)

  17. Analisis Value Chain Di Industri Otomotif

    OpenAIRE

    Hendri, Hendri

    2017-01-01

    Penelitian ini untuk menganalisis industri otomotif. Tujuan dari penelitian ini adalah untuk menganalisis dan mengetahui aktivitas dan kondisi internal proses industri manufaktur dengan menggunakan value chain guna masukan dimasa akan datang bagi industri otomotif secara khusus. Value Chain merupakan rantai nilai yang dapat mengetahui kekuatan Perusahaan, keuntungan dan kesuksesan dari rantai aktivitas dalam Perusahaan atau industri manufaktur.Metode analisis menggunakan Statistika Deskript...

  18. Cumulative damage fatigue tests on nuclear reactor Zircaloy-2 fuel tubes at room temperature and 3000C

    International Nuclear Information System (INIS)

    Pandarinathan, P.R.; Vasudevan, P.

    1980-01-01

    Cumulative damage fatigue tests were conducted on the Zircaloy-2 fuel tubes at room temperature and 300 0 C on the modified Moore type, four-point-loaded, deflection-controlled, rotating bending fatigue testing machine. The cumulative cycle ratio at fracture for the Zircaloy-2 fuel tubes was found to depend on the sequence of loading, stress history, number of cycles of application of the pre-stress and the test temperature. A Hi-Lo type fatigue loading was found to be very much damaging at room temperature and this feature was not observed in the tests at 300 0 C. Results indicate significant differences in damage interaction and damage propagation under cumulative damage tests at room temperature and at 300 0 C. Block-loading fatigue tests are suggested as the best method to determine the life-time of Zircaloy-2 fuel tubes under random fatigue loading during their service in the reactor. (orig.)

  19. ANALISIS KESELAMATAN TERMOHIDROLIK BULK SHIELDING REAKTOR KARTINI

    Directory of Open Access Journals (Sweden)

    Azizul Khakim

    2015-10-01

    Full Text Available ABSTRAK ANALISIS KESELAMATAN TERMOHIDROLIK BULK SHIELDING REAKTOR KARTINI. Bulk shielding merupakan fasilitas yang terintegrasi dengan reaktor Kartini yang berfungsi sebagai penyimpanan sementara bahan bakar bekas. Fasilitas ini merupakan fasilitas yang termasuk dalam struktur, sistem dan komponen (SSK yang penting bagi keselamatan. Salah satu fungsi keselamatan dari sistem penanganan dan penyimpanan bahan bakar adalah mencegah kecelakaan kekritisan yang tak terkendali dan membatasi naiknya temperatur bahan bakar. Analisis keselamatan paling kurang harus mencakup analisis keselamatan dari sisi neutronik dan termo hidrolik Bulk shielding. Analisis termo hidrolik ditujukan untuk memastikan perpindahan panas dan proses pendinginan bahan bakar bekas berjalan baik dan tidak terjadi akumulasi panas yang mengancam integritas bahan bakar. Code tervalidasi PARET/ANL digunakan untuk analisis pendinginan dengan mode konveksi alam. Hasil perhitungan menunjukkan bahwa mode pendinginan konvekasi alam cukup memadai dalam mendinginkan panas sisa tanpa mengakibatkan kenaikan temperatur bahan bakar yang signifikan. Kata kunci: Bulk shielding, bahan bakar bekas, konveksi alam, PARET.   ABSTRACT THERMAL HYDRAULIC SAFETY ANALYSIS OF BULK SHIELDING KARTINI REACTOR. Bulk shielding is an integrated facility to Kartini reactor which is used for temporary spent fuels storage. The facility is one of the structures, systems and components (SSCs important to safety. Among the safety functions of fuel handling and storage are to prevent any uncontrolable criticality accidents and to limit the fuel temperature increase. Safety analyses should, at least, cover neutronic and thermal hydraulic calculations of the bulk shielding. Thermal hydraulic analyses were intended to ensure that heat removal and the process of the spent fuels cooling takes place adequately and no heat accumulation that challenges the fuel integrity. Validated code, PARET/ANL was used for analysing the

  20. Dynamic event Tress applied to sequences Full Spectrum LOCA. Calculating the frequency of exceedance of damage by integrated Safety Analysis Methodology; Arboles de sucesos dinamicos aplicados a secuencias Full Spectrum LOCA. Calculo de la frequencia de excedencia del dano mediante la metodologia Analisis Integrados de Seguridad (ISA)

    Energy Technology Data Exchange (ETDEWEB)

    Gomez-Magan, J. J.; Fernandez, I.; Gil, J.; Marrao, H.; Queral, C.; Gonzalez-Cadelo, J.; Montero-Mayorga, J.; Rivas, J.; Ibane-Llano, C.; Izquierdo, J. M.; Sanchez-Perea, M.; Melendez, E.; Hortal, J.

    2013-09-01

    The Integrated Safety Analysis (ISA) methodology, developed by the Spanish Nuclear Safety council (CSN), has been applied to obtain the dynamic Event Trees (DETs) for full spectrum Loss of Coolant Accidents (LOCAs) of a Westinghouse 3-loop PWR plant. The purpose of this ISA application is to obtain the Damage Exceedance Frequency (DEF) for the LOCA Event Tree by taking into account the uncertainties in the break area and the operator actuation time needed to cool down and de pressurize reactor coolant system by means of steam generator. Simulations are performed with SCAIS, a software tool which includes a dynamic coupling with MAAP thermal hydraulic code. The results show the capability of the ISA methodology to obtain the DEF taking into account the time uncertainty in human actions. (Author)

  1. Claims Handling Co-operation between Nuclear Insurance Pools in a Case of Transboundary Damage - Multilateral and Bilateral Agreements in Progress

    International Nuclear Information System (INIS)

    Zaruba, P.

    2008-01-01

    The paper is a short progress report on matters concerning the core reason for insurance of nuclear third party liability - registration, handling, organizing and settling of claims in case of a major nuclear incident, underlining claims handling co-operation between national nuclear insurance pools when damage to health or property becomes international. The contents of this paper is in close relation to information provided on this subject during the 6th International Conference in 2006. Commercial insurance companies have gained extensive experience with handling large scale claims (e.g. after floods and other natural disasters) and are capable in gathering and organizing a high number of professional loss surveyors and adjusters in a very short period of time. In case of nuclear insurance pools co-operation between members (commercial insurance companies) is an added value and can be used practically all over the country bringing into action the network of branches and offices of all the pool members. This advantage is also used in case of cross border claims when it is necessary to gather information and claims advises from a large number of subjects and from many countries, sometimes very far apart. The international network of nuclear insurance pools is an ideal tool for this task and can be mobilized practically at once. Operators of nuclear installations, especially nuclear power plants, do not have the possibility to put aside hundreds of workers to handle claims and are also usually not sufficiently equipped with the necessary know-how. The same goes for governments and government agencies which in many countries guarantee the payments of claims to victims. National nuclear insurance pools are on the other hand well equipped for this task which usually has to be in place for many years after a nuclear incident. Multilateral and bilateral agreements between national nuclear insurance pools and other institutions should be prepared and signed before any

  2. Investigating α-particle radiation damage in phyllosilicates using synchrotron microfocus-XRD/XAS: implications for geological disposal of nuclear waste

    Science.gov (United States)

    Bower, W. R.; Pearce, C. I.; Pimblott, S. M.; Haigh, S. J.; Mosselmans, J. F. W.; Pattrick, R. A. D.

    2014-12-01

    The response of mineral phases to the radiation fields that will be experienced in a geological disposal facility (GDF) for nuclear waste is poorly understood. Phyllosilicates are critical phases in a GDF with bentonite clay as the backfill of choice surrounding high level wastes in the engineered barrier, and clays and micas forming the most important reactive component of potential host rocks. It is essential that we understand changes in mineral properties and behaviour as a result of damage from both α and γ radiation over long timescales. Radiation damage has been demonstrated to affect the physical integrity and oxidation state1 of minerals which will also influence their ability to react with radionuclides. Using the University of Manchester's newly commissioned particle accelerator at the Dalton Cumbrian Facility, UK, model phyllosilicate minerals (e.g. biotite, chlorite) were irradiated with high energy (5MeV) alpha particles at controlled dose rates. This has been compared alongside radiation damage found in naturally formed 'radiohalos' - spherical areas of discolouration in minerals surrounding radioactive inclusions, resulting from alpha particle penetration, providing a natural analogue to study lattice damage under long term bombardment1,2. Both natural and artificially irradiated samples have been analysed using microfocus X-ray absorption spectroscopy and high resolution X-ray diffraction mapping on Beamline I18 at Diamond Light Source; samples were probed for redox changes and long/short range disorder. This was combined with lattice scale imaging of damage using HR-TEM (TitanTM Transmission Electron Microscope). The results show aberrations in lattice parameters as a result of irradiation, with multiple damage-induced 'domains' surrounded by amorphous regions. In the naturally damaged samples, neo-formed phyllosilicate phases are shown to be breakdown products of highly damaged regions. A clear reduction of the Fe(III) component has been

  3. Probabilistic residual life assessment of high temperature pipings in nuclear power plants against creep fatigue damage: final report

    International Nuclear Information System (INIS)

    Gupta, Sanjay

    2014-02-01

    Residual life assessment of components of nuclear power plants is essential for their operational safety, reliability and financial viability. The high risks involved in the event of failures in nuclear power plants have led to the development of design philosophies that incorporate extreme conservatism in design. The implications of such conservatism in design leads to more frequent maintenance operations than necessary

  4. The Convention on Supplementary Compensation for Nuclear Damage and participation by developing countries: A South African perspective

    International Nuclear Information System (INIS)

    Davies, David B.

    2014-01-01

    This article contends that it is essential that new entrant countries into the nuclear energy industry have comprehensive nuclear legislation; it is less clear, however, whether new entrant countries find it essential to join any of the various international nuclear liability conventions, as some countries have been slow or resistant to the idea. This article will take a closer look at the potential influencing factors driving membership or non-membership in the CSC by a developing country. First, however, is a discussion of the basic principles of international nuclear third party liability, the CSC itself, developing countries' current participation in the various international nuclear liability conventions and the advantages and disadvantages of the CSC. The author's views regarding participation by a developing country in the CSC will also be presented. (author)

  5. Investigation of a Novel NDE Method for Monitoring Thermomechanical Damage and Microstructure Evolution in Ferritic-Martensitic Steels for Generation IV Nuclear Energy Systems

    Energy Technology Data Exchange (ETDEWEB)

    Nagy, Peter

    2013-09-30

    The main goal of the proposed project is the development of validated nondestructive evaluation (NDE) techniques for in situ monitoring of ferritic-martensitic steels like Grade 91 9Cr-1Mo, which are candidate materials for Generation IV nuclear energy structural components operating at temperatures up to ~650{degree}C and for steam-generator tubing for sodium-cooled fast reactors. Full assessment of thermomechanical damage requires a clear separation between thermally activated microstructural evolution and creep damage caused by simultaneous mechanical stress. Creep damage can be classified as "negligible" creep without significant plastic strain and "ordinary" creep of the primary, secondary, and tertiary kind that is accompanied by significant plastic deformation and/or cavity nucleation and growth. Under negligible creep conditions of interest in this project, minimal or no plastic strain occurs, and the accumulation of creep damage does not significantly reduce the fatigue life of a structural component so that low-temperature design rules, such as the ASME Section III, Subsection NB, can be applied with confidence. The proposed research project will utilize a multifaceted approach in which the feasibility of electrical conductivity and thermo-electric monitoring methods is researched and coupled with detailed post-thermal/creep exposure characterization of microstructural changes and damage processes using state-of-the-art electron microscopy techniques, with the aim of establishing the most effective nondestructive materials evaluation technique for particular degradation modes in high-temperature alloys that are candidates for use in the Next Generation Nuclear Plant (NGNP) as well as providing the necessary mechanism-based underpinnings for relating the two. Only techniques suitable for practical application in situ will be considered. As the project evolves and results accumulate, we will also study the use of this technique for monitoring other GEN IV

  6. Protocols to Amend the Paris, Vienna and Brussels Supplementary Conventions and the Convention on Supplementary Compensation for Nuclear Damage: Status of their Implementation into National Legislation

    International Nuclear Information System (INIS)

    Schwartz, J.

    2006-01-01

    Over the last decade, a number of very significant developments have taken place in modernising the existing international nuclear liability regimes. The first major advancement was the adoption, in September 1997, of the Protocol to amend the 1963 Vienna Convention on Civil Liability for Nuclear Damage (VC Protocol) and of a new Convention on Supplementary Compensation for Nuclear Damage (CSC). This was followed, in February 2004, by the adoption of Protocols to amend both the 1960 Paris Convention on Third Party Liability in the Field of Nuclear Energy (PC Protocol) and the 1963 Brussels Convention Supplementary to the Paris Convention (BSC Protocol). The principle goal of all these new instruments is to provide a greater amount of compensation to a larger number of victims in respect of a broader scope of nuclear damage suffered as a result of a nuclear accident. The second, but still very important objective is the maintenance of compatibility between the revised Paris and Vienna Conventions to ensure the smooth functioning of the 1988 Joint Protocol Relating to the Application of the Vienna Convention (VC) and the Paris Convention (PC). In addition, the PC States wish to ensure that their newly revised Convention will not prevent a Contracting Party from joining the more global regime established by the CSC. However, it remains to be seen to what extent these new instruments will attract a sufficient number of adherents to make them truly effective. While the VC Protocol is already in force, it has not drawn wide support from the 1963 VC States or from countries with important nuclear generating capacity which have not yet joined that latter any Convention. In addition, notwithstanding its adoption almost 10 years ago, the CSC has not yet entered into force and it remains questionable whether it will ever attract the necessary number of adherents for that purpose, especially in light of its strict requirements in this regard. As for the PC and BSC Protocols to

  7. Nuclear DNA damage-triggered NLRP3 inflammasome activation promotes UVB-induced inflammatory responses in human keratinocytes

    International Nuclear Information System (INIS)

    Hasegawa, Tatsuya; Nakashima, Masaya; Suzuki, Yoshiharu

    2016-01-01

    Ultraviolet (UV) radiation in sunlight can result in DNA damage and an inflammatory reaction of the skin commonly known as sunburn, which in turn can lead to cutaneous tissue disorders. However, little has been known about how UV-induced DNA damage mediates the release of inflammatory mediators from keratinocytes. Here, we show that UVB radiation intensity-dependently increases NLRP3 gene expression and IL-1β production in human keratinocytes. Knockdown of NLRP3 with siRNA suppresses UVB-induced production of not only IL-1β, but also other inflammatory mediators, including IL-1α, IL-6, TNF-α, and PGE_2. In addition, inhibition of DNA damage repair by knockdown of XPA, which is a major component of the nucleotide excision repair system, causes accumulation of cyclobutane pyrimidine dimer (CPD) and activation of NLRP3 inflammasome. In vivo immunofluorescence analysis confirmed that NLRP3 expression is also elevated in UV-irradiated human epidermis. Overall, our findings indicate that UVB-induced DNA damage initiates NLRP3 inflammasome activation, leading to release of various inflammatory mediators from human keratinocytes. - Highlights: • UVB radiation induces NLRP3 inflammasome activation in human keratinocytes. • NLRP3 knockdown suppresses production of UVB-induced inflammatory mediators. • UVB-induced DNA damage triggers NLRP3 inflammasome activation. • NLRP3 expression in human epidermis is elevated in response to UV radiation.

  8. Nuclear DNA damage-triggered NLRP3 inflammasome activation promotes UVB-induced inflammatory responses in human keratinocytes

    Energy Technology Data Exchange (ETDEWEB)

    Hasegawa, Tatsuya, E-mail: tatsuya.hasegawa@to.shiseido.co.jp; Nakashima, Masaya; Suzuki, Yoshiharu

    2016-08-26

    Ultraviolet (UV) radiation in sunlight can result in DNA damage and an inflammatory reaction of the skin commonly known as sunburn, which in turn can lead to cutaneous tissue disorders. However, little has been known about how UV-induced DNA damage mediates the release of inflammatory mediators from keratinocytes. Here, we show that UVB radiation intensity-dependently increases NLRP3 gene expression and IL-1β production in human keratinocytes. Knockdown of NLRP3 with siRNA suppresses UVB-induced production of not only IL-1β, but also other inflammatory mediators, including IL-1α, IL-6, TNF-α, and PGE{sub 2}. In addition, inhibition of DNA damage repair by knockdown of XPA, which is a major component of the nucleotide excision repair system, causes accumulation of cyclobutane pyrimidine dimer (CPD) and activation of NLRP3 inflammasome. In vivo immunofluorescence analysis confirmed that NLRP3 expression is also elevated in UV-irradiated human epidermis. Overall, our findings indicate that UVB-induced DNA damage initiates NLRP3 inflammasome activation, leading to release of various inflammatory mediators from human keratinocytes. - Highlights: • UVB radiation induces NLRP3 inflammasome activation in human keratinocytes. • NLRP3 knockdown suppresses production of UVB-induced inflammatory mediators. • UVB-induced DNA damage triggers NLRP3 inflammasome activation. • NLRP3 expression in human epidermis is elevated in response to UV radiation.

  9. A bridge between two conventions on civil liability for nuclear damage: The Joint Protocol relating to the application of the Vienna Convention and the Paris Convention

    International Nuclear Information System (INIS)

    Busekist, Otto von

    2006-01-01

    The adoption of the Joint Protocol and its signature on 21 September 1988, at the closure of the diplomatic conference jointly convened in Vienna by the IAEA and the NEA, was hailed as landmark in efforts towards the establishment of a comprehensive civil nuclear liability regime. The importance of liability and compensation for transfrontier damage caused by a nuclear incident is indeed one of the lessons learned from the Chernobyl accident. The present article attempts to describe the history of the Joint Protocol during the many years it took to develop this link between the two conventions, to provide comment on its objectives and content, and to discuss some important questions related to its application

  10. A bridge between two Conventions on civil liability for nuclear damage: the Joint protocol Relating to the application of the Vienna Convention and the Paris Convention

    International Nuclear Information System (INIS)

    Busekist, O. von.

    1989-01-01

    The adoption of the Joint-Protocol and its signature on 21 September 1988, at the closure of the diplomatic conference jointly convened in Vienna by the IAEA and NEA, was hailed as a landmark in efforts towards the establishment of a comprehensive civil nuclear liability regime. The importance of liability and compensation for transfrontier damage caused by a nuclear incident is indeed one of the lessons learned from the Chernobyl accident. This article describes the history of the Joint Protocol during the many years it took to develop this link between the two Conventions, provides a comment on its objectives and content, and discusses some important questions related to its application. (NEA) [fr

  11. An Appraisal of Analytical Methods for Plutonium and their Applications to the Analysis of Nuclear Materials; Evaluation des Methodes Analytiques de Dosage du Plutonium et de Leur Application a l'Analyse des Matieres Nucleaires; Otsenka analiticheskikh metodov opredeleniya plutoniya i ikh primenenie dlya analiza yadernykh materialov; Metodos Analiticos de Determinacion del Plutonio y su Empleo en el Analisis de Materiales Nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Milner, G. W.C.; Phillips, G. [Atomic Energy Research Establishment, Harwell, Berks. (United Kingdom)

    1966-02-15

    respectifs de la dissolution dans des melanges d'acides mineraux courants et de la dissolution faisant appel a des procedes de fusion, avec des exemples a l'appui. Les auteurs decrivent aussi les procedes utilises et les resultats obtenus, pour l'analyse des alliages Pu-U, Pu-Ce-Co et Pu-U-Mo, des oxydes et carbures de Pu-U, et des cermets de carbure de Pu-U contenant Fe, Mo et Cr. Ces matieres sont l'aboutissement de recherches metallurgiques destinees a mettre au point des combustibles nucleaires. (author) [Spanish] Para determinar el contenido de plutonio de los materiales nucleares existen diversos metodos. Si se trata de cantidades del orden del miligramo se pueden emplear la espectrofotometria diferencial por el color del Pu (III), la gravimetria basada en el PuO2{sub ,} si recuento gamma y metodos de oxidorreduccion como las valoraciones potenciometricas o amperimetricas y la culombiometria de potencial controlado. Si se trata de microgramos son preferibles el recuento alfa, la dilucion isotopica o las tecnicas polarograficas. Teniendo en cuenta que unos metodos son mas adecuados que otros para ciertos tipos de muestra, el analista tiene que resolver un dificil problema de seleccion a fin de obtener ios mejores resultados posibles. Los autores exponen las ventajas y las limitaciones puestas de manifiesto por los anos de experiencia en la A.E.R.E. y formulan observaciones acerca de la exactitud y la precision de los metodos, su sensibilidad y otras cuestiones de especial interes. Como algunos de esos metodos exigen la separacion previa del plutonio, los autores estudian el empleo de las tecnicas de intercambio anionico y de cromatografia en fase inversa, y en particular su conveniencia para el analisis de muestras radiactivas. Examinan los muchos problemas que han surgido al analizar por estos metodos, aleaciones, productos ceramicos y cermets de plutonio en diversos sistemas que contenian uranio, torio, hierro, cromo, molibdeno, cerio y cobalto. La memoria trata

  12. Towards a global system of compensation for transboundary nuclear damage: reflexions on the interrelationship of civil and international state liability

    International Nuclear Information System (INIS)

    Handl, G.

    1993-01-01

    International state liability is an essential complementary element of any global and comprehensive nuclear compensation system. Civil liability alone will not be able to fully compensate victims of a nuclear accident and will therefore not fully internalize the costs of nuclear activities. To make it effective and politically acceptable, state liability must be fully integrated procedurally with any civil liability system as a last tier of compensation following a simple process for handling together both civil and state liability claims at the international level, with individuals being able to sue Installation States. 69 refs

  13. Medical treatment of radiation damages and medical emergency planning in case of nuclear power plant incidents and accidents

    International Nuclear Information System (INIS)

    Ohlenschlaeger, L.

    1981-03-01

    Medical measures in case of radiation damages are discussed on the basis of five potential categories of radiation incidents and accidents, respectively, viz. contaminations, incorporations, external local and general radiation over-exposures, contaminated wounds, and combinations of radiation damages and conventional injuries. Considerations are made for diagnostic and therapeutic initial measures especially in case of minor and moderate radiation accidents. The medical emergency planning is reviewed by means of definations used in the practical handling of incidents or accidents. The parameters are: extent of the incident or accident, number of persons involved, severity of radiation damage. Based on guiding symptoms the criteria for the classification into minor, moderate or severe radiation accidents are discussed. Reference is made to the Medical Radiation Protection Centers existing in the Federal Republic of Germany and the possibility of getting advices in case of radiation incidents and accidents. (orig.) [de

  14. Analisis Kinerja Local Area Network Menggunakan Router.

    OpenAIRE

    Hutahaean, Yosua

    2012-01-01

    Perangkat internetworking menawarkan komunikasi di antara segmen Local Area Network (LAN). Ada empat tipe utama perangkat internetworking ini: repeater, bridge, router, dan gateway. Perangkat ini dibedakan atas dasar system lapisan Open System Interconnection (OSI) yang digunakan, berfungsi sebagai media komunikasi dari LAN ke LAN. Pada Tugas Akhir ini penulis tertarik untuk membahas analisis kinerja Local Area Network (LAN) menggunakan Router yang menggunakan sistem antrian M/M/1 dimana j...

  15. Feasibility analysis in the expansion proposal of the nuclear power plant Laguna Verde: application of real options, binomial model; Analisis de viabilidad en la propuesta de expansion de la central nucleoelectrica Laguna Verde: aplicacion de opciones reales, modelo binomial

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez I, S.; Ortiz C, E.; Chavez M, C., E-mail: lunitza@gmail.com [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2011-11-15

    At the present time, is an unquestionable fact that the nuclear electrical energy is a topic of vital importance, no more because eliminates the dependence of the hydrocarbons and is friendly with the environment, but because is also a sure and reliable energy source, and represents a viable alternative before the claims in the growing demand of electricity in Mexico. Before this panorama, was intended several scenarios to elevate the capacity of electric generation of nuclear origin with a variable participation. One of the contemplated scenarios is represented by the expansion project of the nuclear power plant Laguna Verde through the addition of a third reactor that serves as detonator of an integral program that proposes the installation of more nuclear reactors in the country. Before this possible scenario, the Federal Commission of Electricity like responsible organism of supplying energy to the population should have tools that offer it the flexibility to be adapted to the possible changes that will be presented along the project and also gives a value to the risk to future. The methodology denominated Real Options, Binomial model was proposed as an evaluation tool that allows to quantify the value of the expansion proposal, demonstrating the feasibility of the project through a periodic visualization of their evolution, all with the objective of supplying a financial analysis that serves as base and justification before the evident apogee of the nuclear energy that will be presented in future years. (Author)

  16. Estimation of probability density functions of damage parameter for valve leakage detection in reciprocating pump used in nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jong Kyeom; Kim, Tae Yun; Kim, Hyun Su; Chai, Jang Bom; Lee, Jin Woo [Div. of Mechanical Engineering, Ajou University, Suwon (Korea, Republic of)

    2016-10-15

    This paper presents an advanced estimation method for obtaining the probability density functions of a damage parameter for valve leakage detection in a reciprocating pump. The estimation method is based on a comparison of model data which are simulated by using a mathematical model, and experimental data which are measured on the inside and outside of the reciprocating pump in operation. The mathematical model, which is simplified and extended on the basis of previous models, describes not only the normal state of the pump, but also its abnormal state caused by valve leakage. The pressure in the cylinder is expressed as a function of the crankshaft angle, and an additional volume flow rate due to the valve leakage is quantified by a damage parameter in the mathematical model. The change in the cylinder pressure profiles due to the suction valve leakage is noticeable in the compression and expansion modes of the pump. The damage parameter value over 300 cycles is calculated in two ways, considering advance or delay in the opening and closing angles of the discharge valves. The probability density functions of the damage parameter are compared for diagnosis and prognosis on the basis of the probabilistic features of valve leakage.

  17. Estimation of probability density functions of damage parameter for valve leakage detection in reciprocating pump used in nuclear power plants

    International Nuclear Information System (INIS)

    Lee, Jong Kyeom; Kim, Tae Yun; Kim, Hyun Su; Chai, Jang Bom; Lee, Jin Woo

    2016-01-01

    This paper presents an advanced estimation method for obtaining the probability density functions of a damage parameter for valve leakage detection in a reciprocating pump. The estimation method is based on a comparison of model data which are simulated by using a mathematical model, and experimental data which are measured on the inside and outside of the reciprocating pump in operation. The mathematical model, which is simplified and extended on the basis of previous models, describes not only the normal state of the pump, but also its abnormal state caused by valve leakage. The pressure in the cylinder is expressed as a function of the crankshaft angle, and an additional volume flow rate due to the valve leakage is quantified by a damage parameter in the mathematical model. The change in the cylinder pressure profiles due to the suction valve leakage is noticeable in the compression and expansion modes of the pump. The damage parameter value over 300 cycles is calculated in two ways, considering advance or delay in the opening and closing angles of the discharge valves. The probability density functions of the damage parameter are compared for diagnosis and prognosis on the basis of the probabilistic features of valve leakage

  18. Estimation of Probability Density Functions of Damage Parameter for Valve Leakage Detection in Reciprocating Pump Used in Nuclear Power Plants

    Directory of Open Access Journals (Sweden)

    Jong Kyeom Lee

    2016-10-01

    Full Text Available This paper presents an advanced estimation method for obtaining the probability density functions of a damage parameter for valve leakage detection in a reciprocating pump. The estimation method is based on a comparison of model data which are simulated by using a mathematical model, and experimental data which are measured on the inside and outside of the reciprocating pump in operation. The mathematical model, which is simplified and extended on the basis of previous models, describes not only the normal state of the pump, but also its abnormal state caused by valve leakage. The pressure in the cylinder is expressed as a function of the crankshaft angle, and an additional volume flow rate due to the valve leakage is quantified by a damage parameter in the mathematical model. The change in the cylinder pressure profiles due to the suction valve leakage is noticeable in the compression and expansion modes of the pump. The damage parameter value over 300 cycles is calculated in two ways, considering advance or delay in the opening and closing angles of the discharge valves. The probability density functions of the damage parameter are compared for diagnosis and prognosis on the basis of the probabilistic features of valve leakage.

  19. Repair pathways independent of the Fanconi anemia nuclear core complex play a predominant role in mitigating formaldehyde-induced DNA damage

    International Nuclear Information System (INIS)

    Noda, Taichi; Takahashi, Akihisa; Kondo, Natsuko; Mori, Eiichiro; Okamoto, Noritomo; Nakagawa, Yosuke; Ohnishi, Ken; Zdzienicka, Malgorzata Z.; Thompson, Larry H.; Helleday, Thomas; Asada, Hideo

    2011-01-01

    The role of the Fanconi anemia (FA) repair pathway for DNA damage induced by formaldehyde was examined in the work described here. The following cell types were used: mouse embryonic fibroblast cell lines FANCA -/- , FANCC -/- , FANCA -/- C -/- , FANCD2 -/- and their parental cells, the Chinese hamster cell lines FANCD1 mutant (mt), FANCGmt, their revertant cells, and the corresponding wild-type (wt) cells. Cell survival rates were determined with colony formation assays after formaldehyde treatment. DNA double strand breaks (DSBs) were detected with an immunocytochemical γH2AX-staining assay. Although the sensitivity of FANCA -/- , FANCC -/- and FANCA -/- C -/- cells to formaldehyde was comparable to that of proficient cells, FANCD1mt, FANCGmt and FANCD2 -/- cells were more sensitive to formaldehyde than the corresponding proficient cells. It was found that homologous recombination (HR) repair was induced by formaldehyde. In addition, γH2AX foci in FANCD1mt cells persisted for longer times than in FANCD1wt cells. These findings suggest that formaldehyde-induced DSBs are repaired by HR through the FA repair pathway which is independent of the FA nuclear core complex. -- Research highlights: → We examined to clarify the repair pathways of formaldehyde-induced DNA damage. Formaldehyde induces DNA double strand breaks (DSBs). → DSBs are repaired through the Fanconi anemia (FA) repair pathway. → This pathway is independent of the FA nuclear core complex. → We also found that homologous recombination repair was induced by formaldehyde.

  20. Ddx19 links mRNA nuclear export with progression of transcription and replication and suppresses genomic instability upon DNA damage in proliferating cells.

    Science.gov (United States)

    Hodroj, Dana; Serhal, Kamar; Maiorano, Domenico

    2017-09-03

    The DEAD-box Helicase 19 (Ddx19) gene codes for an RNA helicase involved in both mRNA (mRNA) export from the nucleus into the cytoplasm and in mRNA translation. In unperturbed cells, Ddx19 localizes in the cytoplasm and at the cytoplasmic face of the nuclear pore. Here we review recent findings related to an additional Ddx19 function in the nucleus in resolving RNA:DNA hybrids (R-loops) generated during collision between transcription and replication, and upon DNA damage. Activation of a DNA damage response pathway dependent upon the ATR kinase, a major regulator of replication fork progression, stimulates translocation of the Ddx19 protein from the cytoplasm into the nucleus. Only nuclear Ddx19 is competent to resolve R-loops, and down regulation of Ddx19 expression induces DNA double strand breaks only in proliferating cells. Overall these observations put forward Ddx19 as an important novel mediator of the crosstalk between transcription and replication.

  1. Damage of reactor recirculation pump of No.3 plant in Fukushima No.2 Nuclear Power Station, Tokyo Electric Power Co., Inc

    International Nuclear Information System (INIS)

    1990-01-01

    No.3 plant in Fukushima No.2 Nuclear Power Station is a BWR plant with the rated output of 1100 MW, and as for the damage of its reactor recirculation pump, the investigation of the cause and the examination of countermeasures are advanced by the special committee. It is presumed that the submerged bearing ring of this pump caused the fatigue fracture due to the insufficient penetration in the fillet-welded part. The ring broke into pieces, and the main disk of the impeller was broken by the wear due to the pieces. Further, the damage of washers and the falling-off of bolts occurred. The metallic particles generated by wear were about 30 kg, and it is presumed that several kg of them adhered to fuel. Hereafter, the investigation of the cause will be continued, and the countermeasures for preventing the recurrence are examined. On January 1, 1989, the vibration of the pump increased, and the alarm was issued. However, the operation was continued carefully. On January 6, the vibration increased again, and on January 7, the reactor was stopped. The third regular inspection was begun on the same day, and the damage of the pump was found. (K.I.)

  2. Damage caused to houses and equipment by underground nuclear explosions; Degats dus aux explosions nucleaires souterraines sur les habitations et les equipements

    Energy Technology Data Exchange (ETDEWEB)

    Delort, F; Guerrini, C [Commissariat a l' Energie Atomique, Bruyeres-le-Chatel (France). Centre d' Etudes

    1969-07-01

    A description is given of the damaged caused to various structures, buildings, houses, mechanical equipment and electrical equipment by underground nuclear explosions in granite. For each type of equipment or building are given the limiting distances for a given degree of damage. These distances have been related to a parameter characterizing the movement of the medium; it is thus possible to generalize the results obtained in granite, for different media. The problem of estimating the damage caused at a greater distance from the explosion is considered. (authors) [French] Les degats sur diverses structures, constructions, habitations, equipements mecaniques et materiels electriques provoques par des explosions nucleaires souterraines dans le granite sont decrits. On a indique pour chaque type de materiel ou de construction, les distances limites correspondant a un degre de gravite de dommage observe. Ces distances ont ete reliees a un parametre caracterisant le mouvement du milieu, permettant ainsi de generaliser les resultats obtenus dans le granite, a differents milieux. Le probleme de la prevision des degats en zone lointaine a ete aborde. (auteurs)

  3. Nuclear abnormalities in cells from nasal epithelium: a promising assay to evaluate DNA damage related to air pollution in infants

    Directory of Open Access Journals (Sweden)

    Michelle Mergener

    2014-12-01

    Full Text Available OBJECTIVES: This study intends to provide a quick, easy, and inexpensive way to assess nuclear abnormalities such as micronuclei and bud frequencies; binucleated, karyorrhectic, karyolytic, pycnotic, and condensed chromatin cells in nasal scrapings of infants, which are particularly important for conducting genotoxic studies related to the inhaled atmosphere in pediatric populations. METHODS: Nasal swab samples were collected from 40 infants under 12 months of age using a small cytobrush. 2,000 cells from each infant sample were analyzed and classified according to the frequency of nuclear abnormalities. RESULTS: Rates of nuclear abnormalities found agree with values reported in other studies of neonates and children. This study found 0.13% of cells with micronuclei; 1.20% karyorrhexis; 0.03% pyknosis; 10.85% karyolysis; 1.11% condensed chromatin; 0.54 binucleated cells; and 0.02% nuclear bud. Differences were not observed between genders or environmental passive smoking, nor was any age correlation found. CONCLUSION: The assay proposed here is suitable for assessing the frequency of nuclear abnormalities from nasal cells in infants.

  4. Analysis of a natural draught tower in the circulation seawater system of nuclear power plant of Laguna Verde; Analisis de una torre de tiro natural en el sistema de agua de circulacion de mar de la central nucleoelectrica Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F.; Vargas A, A. [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5, Veracruz (Mexico)], e-mail: francisco.tijerina@cfe.gob.mx

    2009-10-15

    The analysis of a natural draught tower in open circuit for the cooling system of seawater circulation on the nuclear power plant of Laguna Verde, it is based on conditions of 2027 MWt and 2317 MWt, where the flows of circulation water system hardly vary and whose purpose will be, to cool the seawater circulation. The circulation water system is used as heat drain in main condenser of turbo generator to condense the nuclear vapor. The annual average temperature in the seawater at present is of 26 C to the entrance to circulation water system and it is vary in accordance with the time of year. The mean temperature of leaving of circulation water system to the sea is of 41 C. Having a cooling tower to reduce the entrance temperature to the circulation water system, it improves the efficiency of thermal transfer in condenser, it improves the vacuum in condenser giving more operative margin to avoid condenser losses by air entrances and nuclear power plant shutdowns, as well as for to improve the efficiency of operative balance of nuclear power plant, also it prevents the impact in thermal transfer efficiency in condenser by the climatic change. (Author)

  5. Dynamic analysis of the condensate and of the feed water in the Laguna Verde nuclear power station; Analisis dinamico del sistema de condensado y agua de alimentacion de la nucleoelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Macedo Muth, Javier; Sandoval Pena, Ramon [Instituto de Investigaciones Electricas, Cuernavaca (Mexico)

    1988-12-31

    This article shows a non-lineal mathematical model for the condensate, and feed water systems and for feed water heater drains at the Laguna Verde Nuclear Power Station for its simulation in real time. The model allows the calculation of flows and pressures in all the piping system and equipment that integrate the systems. It was obtained by using the force unbalance in the fluid concept and is capable of reproducing its dynamic behavior through variations induced by the different operation modes and more common failures. The final model objective is to form part of the Laguna Verde simulator that will be used for operator training of this Nuclear Power Plant. [Espanol] En este articulo se muestra un modelo matematico no lineal de los sistemas de condensado, agua de alimentacion y drenes de calentadores de la central nuclear de Laguna Verde para su simulacion en tiempo real. El modelo permite calcular los flujos y las presiones en toda la red de tuberias y equipos que integran los sistemas. Se obtuvo utilizando el concepto de desbalance de fuerzas en el fluido, y es capaz de reproducir su comportamiento dinamico ante variaciones inducidas por los diversos modos de operacion y fallas mas comunes. El objetivo final del modelo es formar parte del simulador de Laguna Verde que se empleara para el adiestramiento de los operadores de dicha central nuclear.

  6. Fanconi anemia proteins localize to chromatin and the nuclear matrix in a DNA damage- and cell cycle-regulated manner.

    Science.gov (United States)

    Qiao, F; Moss, A; Kupfer, G M

    2001-06-29

    Fanconi anemia (FA) is a genetic disease characterized by congenital defects, bone marrow failure, and cancer susceptibility. Cells from patients with FA exhibit genomic instability and hypersensitivity to DNA cross linking agents such as mitomycin C. Despite the identification of seven complementation groups and the cloning of six genes, the function of the encoded gene products remains elusive. The FancA (Fanconi anemia complementation group A), FancC, and FancG proteins have been detected within a nuclear complex, but no change in level, binding, or localization has been reported as a result of drug treatment or cell cycle. We show that in immunofluorescence studies, FancA appears as a non-nucleolar nuclear protein that is excluded from condensed, mitotic chromosomes. Biochemical fractionation reveals that the FA proteins are found in nuclear matrix and chromatin and that treatment with mitomycin C results in increase of the FA proteins in nuclear matrix and chromatin fractions. This induction occurs in wild-type cells and mutant FA-D (Fanconi complementation group D) cells but not in mutant FA-A cells. Immunoprecipitation of FancA protein in chromatin demonstrates the coprecipitation of FancA, FancC, and FancG, showing that the FA proteins move together as a complex. Also, fractionation of mitotic cells confirms the lack of FA proteins in chromatin or the nuclear matrix. Furthermore, phosphorylation of FancG was found to be temporally correlated with exit of the FA complex from chromosomes at mitosis. Taken together, these findings suggest a role for FA proteins in chromatin and nuclear matrix.

  7. ''Safety rules of fatigue damage for nuclear facilities pressurized equipment at the sizing and the operation stage''

    International Nuclear Information System (INIS)

    Grandemange, J.M.; Faidy, C.

    2001-01-01

    This paper presents the method applied in the nuclear industry in the domain of the fatigue risk safety. It recalls the fatigue curves origins and presents the technical requirements implemented during the design and the construction. It also presents the follow-up of transients in service and the periodical examinations. (A.L.B.)

  8. Analysis of the preliminary trajectory of emergency venting of the nuclear power plant of Laguna Verde using RELAP5; Analisis de la trayectoria preliminar del venteo de emergencia de la Central Laguna Verde mediante RELAP5

    Energy Technology Data Exchange (ETDEWEB)

    Cecenas F, M.; Jimenez S, R.; Ovando C, R. [Instituto Nacional de Electricidad y Energias Limpias, Reforma No. 113, Col. Palmira, 42490 Cuernavaca, Morelos (Mexico); Tijerina S, F.; Tapia M, R. N., E-mail: mcf@iie.org.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km. 7.5, 94271 Veracruz (Mexico)

    2016-09-15

    For a commercial nuclear plant, the availability of a vent line to the atmosphere is an improvement to achieve the prevention and mitigation of the consequences of a severe accident. The importance of this system received greater attention after the Fukushima accident in 2011. Subsequently, in 2012 and 2013, the United States Nuclear Regulatory Commission issued documents stating that the venting must be able to dislodge 1% of the rated thermal power of the core without over pressurizing the primary container. To analyze the venting of the nuclear power plant of Laguna Verde, the line and the primary container are modeled using the thermo-hydraulic code RELAP5, simulating a release of 1% of the nominal licensed power to the container in the form of saturated steam. The vent has no problem to evacuate the energy and manages to keep the container without exceeding its design limit, and the highest percentage of thermal power that can channel the vent to the outside is approximately 3%. A sensitivity analysis increasing the diameter of the line to 14 inches allows increasing in 10% the percentage of power that can be vented to the outside without problem for the containment. (Author)

  9. Neutron activation analysis and activity in the vessel steel of a BWR reactor for their study without radiological risks in microscopy and spectrometry; Analisis de activacion neutronica y actividad en el acero de la vasija de un reactor nuclear tipo BWR para su estudio sin riesgos radiologicos en microscopia y espectrometria

    Energy Technology Data Exchange (ETDEWEB)

    Moranchel, M.; Garcia B, A. [IPN, Escuela Superior de Fisica y Matematicas, Departamento de Fisica, Unidad Profesional Adolfo Lopez Mateos, Zacatenco, 07738 Mexico D. F. (Mexico); Longoria G, L. C., E-mail: mmoranchel@ipn.mx [IAEA, Department of Technical Cooperation, Division for Latin America, Room B1109 Wagramerstrasse 5, PO Box 100, A-1400, Vienna (Austria)

    2012-07-01

    The vessel material of nuclear reactors is subject to irradiation damage induced by the bombardment of neutrons coming from the reactor core. Neutrons are classified as fast and thermal, which produce different effects. Fast neutrons cause damage to the material by dislocation or displacement of atoms in the crystal structure, while the effect of thermal neutrons is a nuclear transmutation that can significantly change the properties of the material. The type and intensity of damage is based on the characteristics of the material, the flow of neutrons and the modes of neutrons interaction with the atomic structures of the material, among others. This work, alluding to nuclear transmutation, makes an analysis of neutron activation of all isotopes in a steel boiling water nuclear reactor (BWR) vessel. An analytical expression is obtained in order to model activity of steel, on the basis of the weight percentage of its atomic components. Its activity is theoretically estimated in a witness sample of the same material as that of the vessel, placed within the nuclear reactor since the beginning of its commercial operation in April 1995, up to August 2010. It was theoretically determined that the witness sample, with a 0.56 g mass (1 x 1 x 0.07 cm{sup 3} dimensions or equivalent) does not present a radiological risks during the stage of preparation, observation and analysis of it in electron microscopy and X-ray diffraction equipment s. The theoretical results were checked experimentally by measuring the activity of the sample by means of gamma spectrometry, measurement of the exposure levels around the sample, as well as the induced level to whole body and limbs, using thermo-luminescent dosimetry (TLD). As a result of the theoretical analysis, new chemical elements are predicted, as a result of the activation phenomena and radioactive decay, whose presence can be a fundamental factor of change in the properties of the vessel. This work is a preamble to the

  10. The usefulness of the nuclear cardiology in the cellular implant in patients with severe myocardial damage; La utilidad de la cardiologia nuclear en el implante celular en pacientes con dano miocardico severo

    Energy Technology Data Exchange (ETDEWEB)

    Omelas A, M.; Arguero S, R.; Garrido G, M.H.; Rodriguez C, A.; Careaga, G.; Castano G, R.; Nambo, M.J.; Pascual P, J.; Ortega R, A.; Gaxiola A, A.; Magana S, J.A.; Estrada A, H.; Equipo de Tecnicos en Medicina Nuclear [Centro Medico Nacional Siglo XXI IMSS Hospital de Cardiologia-Servicio de Medicina Nuclear Mexico DF (Mexico)

    2005-07-01

    The recent therapeutic advances as the cellular implant as well as those different protocols of image acquisition in the field of the Nuclear Cardiology its have allowed that the patient with severe myocardial damage and without some possibility of revascularization is benefited with these advances. Doubtless the Tl-201 par excellence has an important paper for standardize the more appropriate therapeutic behavior for the heart attack patient; reason by this investigation protocol was developed. The objective of the study was to identify the heart attack regions without viable tissue with SPECT in patient with important myocardial damage without some possibility of traditional revascularization; for the 'Stem cell' cellular implantation therapy. The methodology it was carried out by a study of myocardial perfusion in 10 patients with important myocardial damage previous cellular implants, with PICANUC/ SPECT methodology and using a software (Emory Tool Box) for the image processing validated by the University of Emory Atlanta GA; and using as tracer the Tl - 201 to identify the heart attack regions without presence of viable tissue with an analysis model of 17 segments standardized for the left ventricle; qualifying this way the myocardial perfusion in: 0 (normal), 1 (light), 2 (moderate), 3 (severe), 4 (absent) and x (bad technique). The conclusions were that the SPECT study with PICANUC methodology with Tl-201 is safe and effective for the precise localization for the cellular implantation via direct intra myocardial. (Author)

  11. Analysis of the noise of the jet pumps of the Unit 2 of the Laguna Verde nuclear power plant; Analisis de ruido de las bombas de chorro de la Unidad 2 de la Central Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Castillo D, R.; Ortiz V, J.; Ruiz E, J.A. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico); Calleros M, G. [CFE, Central Nucleoelectrica de Laguna Verde, Alto Lucero, Veracruz (Mexico)]. E-mail: rcd@nuclear.inin-mx

    2004-07-01

    The use of the analysis of noise for the detection of badly functioning of the components of a BWR it is a powerful tool in the determination of abnormal conditions of operation, during the life of a nuclear plant of power. From the eighties, some nuclear reactors have presented problems related with the jet pumps and the knots of the recirculation. The Regulatory Commission of the United States, in the I E bulletin 80-07, recommended to carry out a periodic supervision of the pressure drop of the jet pumps, to prevent structural failures. In this work, methods of analysis of noise are used for the detection of abnormal conditions of operation of the jet pumps of a BWR. Signals are analysed to low and high frequency of pressure drop with the NOISE software that is in development. The obtained results show the behavior of the jet pumps of jet 6 and 11 before and after a partial blockade in their throats where the pump 6 return to their condition of previous operation and the pump 11 present a new fall of pressure, inside the limit them permissible of operation. The methodology of the analysis of noise demonstrated to be an useful tool for the badly functioning detection, and you could apply to create a database to supervise the dynamic behavior of the jet pumps of an BWR. (Author)

  12. Study by electronic structure calculations of the radiation damage in the UO2 nuclear fuel: behaviour of the point defects and fission gases

    International Nuclear Information System (INIS)

    Vathonne, Emerson

    2014-01-01

    Uranium dioxide (UO 2 ) is worldwide the most widely used fuel in nuclear plants in the world and in particular in pressurized water reactors (PWR). In-pile the fission of uranium nuclei creates fission products and point defects in the fuel. The understanding of the evolution of these radiation damages requires a multi-scale modelling approach of the nuclear fuel, from the scale of the pellet to the atomic scale. We used an electronic structure calculation method based on the density functional theory (DFT) to model radiation damage in UO 2 at the atomic scale. A Hubbard-type Coulomb interaction term is added to the standard DFT formalism to take into account the strong correlations of the 5f electrons in UO 2 . This method is used to study point defects with various charge states and the incorporation and diffusion of krypton in uranium dioxide. This study allowed us to obtain essential data for higher scale models but also to interpret experimental results. In parallel of this study, three ways to improve the state of the art of electronic structure calculations of UO 2 have been explored: the consideration of the spin-orbit coupling neglected in current point defect calculations, the application of functionals allowing one to take into account the non-local interactions such as van der Waals interactions important for rare gases and the use of the Dynamical Mean Field Theory combined to the DFT method in order to take into account the dynamical effects in the 5f electron correlations. (author) [fr

  13. Repair pathways independent of the Fanconi anemia nuclear core complex play a predominant role in mitigating formaldehyde-induced DNA damage

    Energy Technology Data Exchange (ETDEWEB)

    Noda, Taichi [Department of Biology, School of Medicine, Nara Medical University, 840 Shijo-cho, Kashihara, Nara 634-8521 (Japan); Department of Dermatology, School of Medicine, Nara Medical University, 840 Shijo-cho, Kashihara, Nara 634-8521 (Japan); Takahashi, Akihisa [Department of Biology, School of Medicine, Nara Medical University, 840 Shijo-cho, Kashihara, Nara 634-8521 (Japan); Kondo, Natsuko [Particle Radiation Oncology Research Center, Research Reactor Institute, Kyoto University, Kumatori-cho, Sennan-gun, Osaka 590-0494 (Japan); Mori, Eiichiro [Department of Biology, School of Medicine, Nara Medical University, 840 Shijo-cho, Kashihara, Nara 634-8521 (Japan); Okamoto, Noritomo [Department of Otorhinolaryngology, School of Medicine, Nara Medical University, 840 Shijo-cho, Kashihara, Nara 634-8521 (Japan); Nakagawa, Yosuke [Department of Oral and Maxillofacial Surgery, School of Medicine, Nara Medical University, 840 Shijo-cho, Kashihara, Nara 634-8521 (Japan); Ohnishi, Ken [Department of Biology, Ibaraki Prefectual University of Health Sciences, 4669-2 Ami, Ami-mati, Inasiki-gun, Ibaraki 300-0394 (Japan); Zdzienicka, Malgorzata Z. [Department of Molecular Cell Genetics, Collegium Medicum in Bydgoszcz, Nicolaus-Copernicus-University in Torun, ul. Sklodowskiej-Curie 9, 85-094 Bydgoszcz (Poland); Thompson, Larry H. [Biosciences and Biotechnology Division, L452, Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94551-0808 (United States); Helleday, Thomas [Gray Institute for Radiation Oncology and Biology, University of Oxford, Old Road Campus Research Building, Off Roosevelt Drive, Oxford, OX3 7DQ (United Kingdom); Department of Genetics, Microbiology and Toxicology Stockholm University, SE-106 91 Stockholm (Sweden); Asada, Hideo [Department of Dermatology, School of Medicine, Nara Medical University, 840 Shijo-cho, Kashihara, Nara 634-8521 (Japan); and others

    2011-01-07

    The role of the Fanconi anemia (FA) repair pathway for DNA damage induced by formaldehyde was examined in the work described here. The following cell types were used: mouse embryonic fibroblast cell lines FANCA{sup -/-}, FANCC{sup -/-}, FANCA{sup -/-}C{sup -/-}, FANCD2{sup -/-} and their parental cells, the Chinese hamster cell lines FANCD1 mutant (mt), FANCGmt, their revertant cells, and the corresponding wild-type (wt) cells. Cell survival rates were determined with colony formation assays after formaldehyde treatment. DNA double strand breaks (DSBs) were detected with an immunocytochemical {gamma}H2AX-staining assay. Although the sensitivity of FANCA{sup -/-}, FANCC{sup -/-} and FANCA{sup -/-}C{sup -/-} cells to formaldehyde was comparable to that of proficient cells, FANCD1mt, FANCGmt and FANCD2{sup -/-} cells were more sensitive to formaldehyde than the corresponding proficient cells. It was found that homologous recombination (HR) repair was induced by formaldehyde. In addition, {gamma}H2AX foci in FANCD1mt cells persisted for longer times than in FANCD1wt cells. These findings suggest that formaldehyde-induced DSBs are repaired by HR through the FA repair pathway which is independent of the FA nuclear core complex. -- Research highlights: {yields} We examined to clarify the repair pathways of formaldehyde-induced DNA damage. Formaldehyde induces DNA double strand breaks (DSBs). {yields} DSBs are repaired through the Fanconi anemia (FA) repair pathway. {yields} This pathway is independent of the FA nuclear core complex. {yields} We also found that homologous recombination repair was induced by formaldehyde.

  14. Genetic association analysis of 13 nuclear-encoded mitochondrial candidate genes with type II diabetes mellitus: The DAMAGE study

    DEFF Research Database (Denmark)

    Reiling, Erwin; van Vliet-Ostaptchouk, Jana V; van 't Riet, Esther

    2009-01-01

    ). After a meta-analysis, only one SNP in SIRT4 (rs2522138) remained significant (P=0.01). Extending the second stage with samples from the Danish Steno Study (n=1220 participants) resulted in a common odds ratio (OR) of 0.92 (0.85-1.00), P=0.06. Moreover, in a large meta-analysis of three genome......Mitochondria play an important role in many processes, like glucose metabolism, fatty acid oxidation and ATP synthesis. In this study, we aimed to identify association of common polymorphisms in nuclear-encoded genes involved in mitochondrial protein synthesis and biogenesis with type II diabetes...

  15. Protective Role of Nuclear Factor E2-Related Factor 2 against Acute Oxidative Stress-Induced Pancreatic β-Cell Damage

    Directory of Open Access Journals (Sweden)

    Jingqi Fu

    2015-01-01

    Full Text Available Oxidative stress is implicated in the pathogenesis of pancreatic β-cell dysfunction that occurs in both type 1 and type 2 diabetes. Nuclear factor E2-related factor 2 (NRF2 is a master regulator in the cellular adaptive response to oxidative stress. The present study found that MIN6 β-cells with stable knockdown of Nrf2 (Nrf2-KD and islets isolated from Nrf2-knockout mice expressed substantially reduced levels of antioxidant enzymes in response to a variety of stressors. In scramble MIN6 cells or wild-type islets, acute exposure to oxidative stressors, including hydrogen peroxide (H2O2 and S-nitroso-N-acetylpenicillamine, resulted in cell damage as determined by decrease in cell viability, reduced ATP content, morphology changes of islets, and/or alterations of apoptotic biomarkers in a concentration- and/or time-dependent manner. In contrast, silencing of Nrf2 sensitized MIN6 cells or islets to the damage. In addition, pretreatment of MIN6 β-cells with NRF2 activators, including CDDO-Im, dimethyl fumarate (DMF, and tert-butylhydroquinone (tBHQ, protected the cells from high levels of H2O2-induced cell damage. Given that reactive oxygen species (ROS are involved in regulating glucose-stimulated insulin secretion (GSIS and persistent activation of NRF2 blunts glucose-triggered ROS signaling and GSIS, the present study highlights the distinct roles that NRF2 may play in pancreatic β-cell dysfunction that occurs in different stages of diabetes.

  16. Probabilistic modelling of the damage of geological barriers of the nuclear waste deep storage - ENDOSTON project, final report

    International Nuclear Information System (INIS)

    2010-01-01

    As the corrosion of metallic casings of radioactive waste storage packages releases hydrogen under pressure, and as the overpressure disturbs the stress fields, the authors report the development of methodologies and numerical simulation tools aimed at a better understanding of the mechanisms of development and propagation of crack networks in the geological barrier due to this overpressure. They present a probabilistic model of the formation of crack networks in rocks, with the probabilistic post-processing of a finite element calculation. They describe the modelling of crack propagation and damage in quasi-brittle materials. They present the ENDO-HETEROGENE model for the formation and propagation of cracks in heterogeneous media, describe the integration of the model into the Aster code, and report the model validation (calculation of the stress intensity factor, grid dependence). They finally report a test case of the ENDO-HETEROGENE model

  17. Whole thorax irradiation of non-human primates induces persistent nuclear damage and gene expression changes in peripheral blood cells.

    Directory of Open Access Journals (Sweden)

    Shanaz A Ghandhi

    Full Text Available We investigated the cytogenetic and gene expression responses of peripheral blood cells of non-human primates (NHP, Macaca mulatta that were whole-thorax irradiated with a single dose of 10 Gy. In this model, partial irradiation of NHPs in the thoracic region (Whole Thorax Lung Irradiation, WTLI allows the study of late radiation-induced lung injury, while avoiding acute radiation syndromes related to hematopoietic and gastrointestinal injury. A transient drop in circulating lymphocytes and platelets was seen by 9 days, followed by elevations in respiratory rate, circulating neutrophils, lymphocytes, and monocytes at 60-100 days, corresponding to computed tomography (CT and histologic evidence of pneumonitis, and elective euthanasia of four animals. To evaluate long-term DNA damage in NHP peripheral blood lymphocytes after 10 Gy WTLI, we used the cytokinesis-block micronucleus (CBMN assay to measure chromosomal aberrations as post-mitotic micronuclei in blood samples collected up to 8 months after irradiation. Regression analysis showed significant induction of micronuclei in NHP blood cells that persisted with a gradual decline over the 8-month study period, suggesting long-term DNA damage in blood lymphocytes after WTLI. We also report transcriptomic changes in blood up to 30 days after WTLI. We isolated total RNA from peripheral blood at 3 days before and then at 2, 5 and 30 days after irradiation. We identified 1187 transcripts that were significantly changed across the 30-day time course. From changes in gene expression, we identified biological processes related to immune responses, which persisted across the 30-day study. Response to oxygen-containing compounds and bacteria were implicated by gene-expression changes at the earliest day 2 and latest, day 30 time-points. Gene expression changes suggest a persistent altered state of the immune system, specifically response to infection, for at least a month after WTLI.

  18. Whole thorax irradiation of non-human primates induces persistent nuclear damage and gene expression changes in peripheral blood cells.

    Science.gov (United States)

    Ghandhi, Shanaz A; Turner, Helen C; Shuryak, Igor; Dugan, Gregory O; Bourland, J Daniel; Olson, John D; Tooze, Janet A; Morton, Shad R; Batinic-Haberle, Ines; Cline, J Mark; Amundson, Sally A

    2018-01-01

    We investigated the cytogenetic and gene expression responses of peripheral blood cells of non-human primates (NHP, Macaca mulatta) that were whole-thorax irradiated with a single dose of 10 Gy. In this model, partial irradiation of NHPs in the thoracic region (Whole Thorax Lung Irradiation, WTLI) allows the study of late radiation-induced lung injury, while avoiding acute radiation syndromes related to hematopoietic and gastrointestinal injury. A transient drop in circulating lymphocytes and platelets was seen by 9 days, followed by elevations in respiratory rate, circulating neutrophils, lymphocytes, and monocytes at 60-100 days, corresponding to computed tomography (CT) and histologic evidence of pneumonitis, and elective euthanasia of four animals. To evaluate long-term DNA damage in NHP peripheral blood lymphocytes after 10 Gy WTLI, we used the cytokinesis-block micronucleus (CBMN) assay to measure chromosomal aberrations as post-mitotic micronuclei in blood samples collected up to 8 months after irradiation. Regression analysis showed significant induction of micronuclei in NHP blood cells that persisted with a gradual decline over the 8-month study period, suggesting long-term DNA damage in blood lymphocytes after WTLI. We also report transcriptomic changes in blood up to 30 days after WTLI. We isolated total RNA from peripheral blood at 3 days before and then at 2, 5 and 30 days after irradiation. We identified 1187 transcripts that were significantly changed across the 30-day time course. From changes in gene expression, we identified biological processes related to immune responses, which persisted across the 30-day study. Response to oxygen-containing compounds and bacteria were implicated by gene-expression changes at the earliest day 2 and latest, day 30 time-points. Gene expression changes suggest a persistent altered state of the immune system, specifically response to infection, for at least a month after WTLI.

  19. Irradiation damage

    Energy Technology Data Exchange (ETDEWEB)

    Howe, L.M

    2000-07-01

    There is considerable interest in irradiation effects in intermetallic compounds from both the applied and fundamental aspects. Initially, this interest was associated mainly with nuclear reactor programs but it now extends to the fields of ion-beam modification of metals, behaviour of amorphous materials, ion-beam processing of electronic materials, and ion-beam simulations of various kinds. The field of irradiation damage in intermetallic compounds is rapidly expanding, and no attempt will be made in this chapter to cover all of the various aspects. Instead, attention will be focused on some specific areas and, hopefully, through these, some insight will be given into the physical processes involved, the present state of our knowledge, and the challenge of obtaining more comprehensive understanding in the future. The specific areas that will be covered are: point defects in intermetallic compounds; irradiation-enhanced ordering and irradiation-induced disordering of ordered alloys; irradiation-induced amorphization.

  20. Irradiation damage

    International Nuclear Information System (INIS)

    Howe, L.M.

    2000-01-01

    There is considerable interest in irradiation effects in intermetallic compounds from both the applied and fundamental aspects. Initially, this interest was associated mainly with nuclear reactor programs but it now extends to the fields of ion-beam modification of metals, behaviour of amorphous materials, ion-beam processing of electronic materials, and ion-beam simulations of various kinds. The field of irradiation damage in intermetallic compounds is rapidly expanding, and no attempt will be made in this chapter to cover all of the various aspects. Instead, attention will be focused on some specific areas and, hopefully, through these, some insight will be given into the physical processes involved, the present state of our knowledge, and the challenge of obtaining more comprehensive understanding in the future. The specific areas that will be covered are: point defects in intermetallic compounds; irradiation-enhanced ordering and irradiation-induced disordering of ordered alloys; irradiation-induced amorphization

  1. Damage dosimetry and embrittlement monitoring of nuclear pressure vessels in real time by magnetic properties measurement. Final report

    International Nuclear Information System (INIS)

    Ougouag, A.M.; Stubbins, J.F.; Williams, J.F.; Shong, Wei-Ja.

    1995-04-01

    This program developed a nondestructive technique for gauging the progress of embrittlement of nuclear pressure vessel steels (PVS) by means of monitoring radiation-induced changes in magnetic properties. The technique was developed by running a series of experiments in reactor on typical nuclear pressure vessel steels and weldment material. Following irradiation, changes in magnetic properties were measured and correlated with irradiation dose and with mechanical properties changes, where possible. The changes in magnetic properties were unique to the irradiation environment, and were much larger than those produce by thermal aging in the absence of irradiation. Special techniques for magnetic properties change measurement were developed and complimented by more standard magnetic properties measurement techniques including SQUID measurements. The results of the experiments revealed that magnetic properties were very sensitive to irradiation. Changes in microstructurally-related magnetic properties of as much as 40% were noted after irradiation exposure of as little as 10 17 n/cm 2 (E > 0.1 MeV). The magnetic properties changes plateaued out after doses of around as 10 18 n/cm 2 (E > 0.1 MeV). It is unclear whether further changes would be noted at higher doses which would also be useful for tracking the embrittlement phenomenon. This is recommended for further study. The work supported here resulted in several publications in the open scientific literature

  2. Biological Sexing of a 4000-Year-Old Egyptian Mummy Head to Assess the Potential of Nuclear DNA Recovery from the Most Damaged and Limited Forensic Specimens.

    Science.gov (United States)

    Loreille, Odile; Ratnayake, Shashikala; Bazinet, Adam L; Stockwell, Timothy B; Sommer, Daniel D; Rohland, Nadin; Mallick, Swapan; Johnson, Philip L F; Skoglund, Pontus; Onorato, Anthony J; Bergman, Nicholas H; Reich, David; Irwin, Jodi A

    2018-03-01

    High throughput sequencing (HTS) has been used for a number of years in the field of paleogenomics to facilitate the recovery of small DNA fragments from ancient specimens. Recently, these techniques have also been applied in forensics, where they have been used for the recovery of mitochondrial DNA sequences from samples where traditional PCR-based assays fail because of the very short length of endogenous DNA molecules. Here, we describe the biological sexing of a ~4000-year-old Egyptian mummy using shotgun sequencing and two established methods of biological sex determination (R X and R Y ), by way of mitochondrial genome analysis as a means of sequence data authentication. This particular case of historical interest increases the potential utility of HTS techniques for forensic purposes by demonstrating that data from the more discriminatory nuclear genome can be recovered from the most damaged specimens, even in cases where mitochondrial DNA cannot be recovered with current PCR-based forensic technologies. Although additional work remains to be done before nuclear DNA recovered via these methods can be used routinely in operational casework for individual identification purposes, these results indicate substantial promise for the retrieval of probative individually identifying DNA data from the most limited and degraded forensic specimens.

  3. Biological Sexing of a 4000-Year-Old Egyptian Mummy Head to Assess the Potential of Nuclear DNA Recovery from the Most Damaged and Limited Forensic Specimens

    Directory of Open Access Journals (Sweden)

    Odile Loreille

    2018-03-01

    Full Text Available High throughput sequencing (HTS has been used for a number of years in the field of paleogenomics to facilitate the recovery of small DNA fragments from ancient specimens. Recently, these techniques have also been applied in forensics, where they have been used for the recovery of mitochondrial DNA sequences from samples where traditional PCR-based assays fail because of the very short length of endogenous DNA molecules. Here, we describe the biological sexing of a ~4000-year-old Egyptian mummy using shotgun sequencing and two established methods of biological sex determination (RX and RY, by way of mitochondrial genome analysis as a means of sequence data authentication. This particular case of historical interest increases the potential utility of HTS techniques for forensic purposes by demonstrating that data from the more discriminatory nuclear genome can be recovered from the most damaged specimens, even in cases where mitochondrial DNA cannot be recovered with current PCR-based forensic technologies. Although additional work remains to be done before nuclear DNA recovered via these methods can be used routinely in operational casework for individual identification purposes, these results indicate substantial promise for the retrieval of probative individually identifying DNA data from the most limited and degraded forensic specimens.

  4. ANALISIS PERIKANAN HUHATE DI PERAIRAN LARANTUKA, FLORES

    Directory of Open Access Journals (Sweden)

    Mohamad Adha Akbar

    2016-11-01

    Full Text Available Informasi mengenai beberapa aspek perikanan huhate sangat diperlukan sebagai bahan untuk perencanaan pengelolaan perikanan yang berkelanjutan. Penelitian ini dilakukan di Larantuka, Flores Timur pada tahun 2014 dengan tujuan untuk menganalisis perikanan huhate sebagai salah satu tulang punggung perikanan TCT. Kegiatan penelitian diprioritaskan pada analisis unit alat tangkap, daerah penangkapan, komposisi hasil tangkapan dan estimasi Total Faktor Produktivitas (TFP perikanan huhate. Basis data pengukuran adalah himpunan  data pendaratan dan observasi lapang. Hasil penelitian menunjukan bahwa karakteristik armada terdiri dari kapal yang terbuat dari fibreglass dengan kisaran bobot kapal 6 - 30 GT. Daerah penangkapan di sekitar perairan Laut Sawu dan Laut Flores. Hasil tangkapan utama didominansi oleh cakalang (Katsuwonus pelamis sebanyak 82%, juwana tuna (Thunnus spp. 17% dan tongkol (Auxis spp. 1% serta hasil tangkapan ikutan lemadang (Coryphaena hippurus dan marlin (Makaira spp. < 1%. Hasil analisis tangkapan per unit upaya (CPUE memberikan nilai rata-rata sebesar 1,1 ton/trip (0,4-1,7 ton/trip dengan nilai tertinggi terjadi pada Februari, sedangkan terendah terjadi pada Januari. Hasil penelitian menunjukkan terdapat hubungan yang signifikan antara tren bulanan CPUE dan nilai TFP.

  5. ANALISIS PENGELOLAAN LINGKUNGAN PERMUKIMAN DI KABUPATEN SOPPENG

    Directory of Open Access Journals (Sweden)

    Bakhrani Rauf

    2016-08-01

    Full Text Available Penelitian ini  bertujuan untuk mendeskripsikan pengelolaan lingkungan permukiman di Kabupaten Soppeng pada aspek: (1 penyediaan dan penanganan lahan terbuka hijau (open space; (2 penyediaan dan penanganan drainase; (3  penanganan sampah; (4 penyediaan dan penanganan pembuangan veses (septic tank. Jenis penelitian ini adalah penelitian kuantitatif dengan pendekatan survei.  Sampel wailayah penelitian ini adalah satu RW di ibu kota kabupaten dan satu RW di desa yang dipilih dengan metode purpossive sampling,  yaitu RW yang sudah maju di ibu kota kabupaten dan RW yang tertinggal di desa. Responden sebanyak 50 kepala keluarga yakni masing-masing 25 kepala keuarga di setiap RW, dipilih dengan  systematic random sampling.  Teknik pengumpulan data yang dilakukan adalah melakukan observasi langsung dan dilengkapi dengan wawancara terhadap responden. Analisis yang digunakan adalah analisis deskriptif. Hasil penelitian menunjukkan bahwa pengelolaan lingkungan permukiman di Kabupaten Soppeng pada aspek: (1 ketersediaan dan penanganan lahan terbuka hijau (open space ditemukan belum memadai; (2 ketersediaan drainase (air kotor dan air hujan ditemukan belum memadai; (3 Penanganan sampahbelum memadai; dan (4 penanganan veses dan penyediaan septic tankbelum memadai.

  6. Liver damages and nuclear abnormalities in erythrocytes of Atherinella brasiliensis (Actynopterigii, Atherinopsidade from two beaches in Southeast of Brazil

    Directory of Open Access Journals (Sweden)

    Welingtom S. Fernandez

    2011-06-01

    Full Text Available There are few environmental studies using biomarkers for the species Atherinella brasiliensis in Brazil. In the present work, the presence of hepatic histopathological lesions and nuclear abnormalities in erythrocytes were investigated in A. brasiliensis from Lamberto, a beach under influence of domestic wastes and marine activities. For comparison, fish were also sampled in Puruba, a non-polluted beach, located in the northeastern of São Paulo State. The frequency of lesions found in liver was in higher numbers in individuals from Lamberto than Puruba beach. The most critical injuries observed in A. brasiliensis were the presence of necrotic areas, leucocytes infiltration and piknotic nucleus. A high occurrence of cells with vacuolization was also observed. The hepatic lesion index of the fish from Lamberto beach showed significant high values (Iorg=13 when compared with fish from Puruba beach (Iorg=7 suggesting the influence of the several human activities in the studied site. Notched and blebed nucleous were observed in this study, and significant differences were found between the studied sites. However, these differences did not reflect the total nuclear alterations.Existem poucos estudos no Brasil usando biomarcadores em Atherinella brasiliensis. No presente trabalho foram investigadas a presença de lesões histopatológicas hepáticas e as alterações nucleares em eritrócitos de A. brasiliensis amostrados na praia do Lamberto, local submetido à influência de resíduos domésticos e atividades humanas. Para comparação, indivíduos da espécie foram também amostrados na praia de Puruba, local não impactado, localizado no noroeste do estado de São Paulo. Peixes provenientes da praia do Lamberto apresentaram lesões hepáticas em número maior do que aqueles da praia de Puruba. Áreas necróticas, infiltração de leucócitos e núcleos picnóticos foram os danos de maior importância observados em A. brasiliensis, apesar de uma

  7. IDENTIFIKASI MISKONSEPSI SISWA SMP PADA KONSEP FOTOSINTESIS MELALUI ANALISIS GAMBAR

    Directory of Open Access Journals (Sweden)

    Devi Ariandini

    2014-01-01

    Full Text Available Tujuan dari penelitian ini adalah untuk mengidentifikasi miskonsepsi siswa dengan analisis menggambar. Tiga puluh empat siswa di kelas 8 di sekolah menengah pertama digunakan sebagai subyek dalam penelitian ini. Teknik sampel menggunakan teknik purposive sampling. Data yang diperlukan untuk penelitian ini dikumpulkan melalui kuesioner, menggambar analisis rubrik, dan wawancara. Identifikasi Kesalahpahaman ditentukan dengan menggambar siswa berdasarkan menggambar kriteria klasifikasi oleh Kose (2008. Siswa diperintahkan untuk menarik tentang konsep fotosintesis setelah proses pembelajaran. Gambar siswa dianalisis dengan rubrik dan setelah itu mereka diwawancarai. Hasil penelitian menunjukkan tidak semua tingkat kriteria menggambar dari tingkat 1 sampai 5 diidentifikasi. Dari hasil analisa, gambar paling banyak ditemukan adalah pada tingkat 4. Gambar pada tingkat 4 dikategorikan sebagai gambar lengkap konsep fotosintesis dan tidak ada kesalahpahaman ditemukan. Berdasarkan gambar mereka, ada siswa 2,9% diidentifikasi yang diselenggarakan kesalahpahaman. Ada perbedaan jumlah siswa yang diadakan kesalahpahaman antara gambar hasil analisis dan hasil wawancara. Dari hasil wawancara, ada siswa 35,2% dimiliki kesalahpahaman, lebih dari menggambar hasil analisis. Ini berarti bahwa identifikasi kesalahpahaman melalui analisis gambar tidak efektif. Kesalahpahaman siswa yang paling sering terjadi pada konsep fotosintesis adalah tempat berlangsungnya fotosintesis. Faktor yang membuat kesalahpahaman siswa yaitu karena siswa itu sendiri dan lingkungannya. Kata Kunci: fotosintesis, kesalahpahaman, konsep, menggambar analisis

  8. Fusion Energy: Contextual Analysis of the Information Panels Developed by the Scientific Community versus Citizen Discourse; Fusion Nuclear: Analisis Contextual de Paneles Informativos Elaborados por la Comunidad Cientifica versus Discurso Ciudadano

    Energy Technology Data Exchange (ETDEWEB)

    Ferri Anglada, S.; Cornejo Alvarez, J. M.

    2014-02-01

    The report presents an exploratory study on the impact of scientific dissemination, particularly a comparative analysis of two discourses on fusion energy as an alternative energy future. The report introduces a comparative analysis of the institutional discourse, as portrayed by the scientific jargon used in a European travelling exhibition on nuclear fusion Fusion Expo, and the social discourse, as illustrated by a citizen deliberation on this very same exhibition. Through textual analysis, the scientific discourse as deployed in the informative panels at the Fusion Expo is compared with the citizen discourse as developed in the discussions within the citizen groups. The ConText software was applied for such analysis. The purpose is to analyze how visitors assimilate, capture and understand highly technical information. Results suggest that, in despite of convergence points, the two discourses present certain differences, showing diverse levels of communication. The scientific discourse shows a great profusion of formalisms and technicalities of scientific jargon. The citizen discourse shows abundance of words associated with daily life and the more practical aspects (economy, efficiency), concerning institutional and evaluative references. In sum, the study shows that although there are a few common communicative spaces, there are still very few turning points. These data indicate that although exhibitions can be a good tool to disseminate advances in fusion energy in informal learning contexts, public feedback is a powerful tool for improving the quality of social dialogue. (Author)

  9. Grain boundary sweeping and liquefaction-induced fission product behavior in nuclear fuel under severe-core damage accident conditions

    International Nuclear Information System (INIS)

    Rest, J.

    1984-05-01

    The theoretical FASTGRASS-VFP model has been used in the interpretation of fission gas, iodine, tellurium, and cesium release from: (1) irradiated high-burnup LWR fuel in a flowing steam atmosphere during high-temperature, in-cell heating tests performed at Oak Ridge National Laboratory; and (2) trace-irradiated and high-burnup LWR fuel during severe-fuel-damage (SFD) tests performed in the PBF reactor in Idaho. A theory of grain boundary sweeping of gas bubbles, gas bubble behavior during fuel liquefaction (destruction of grain boundaries due to formation of a U-rich melt phase), and U-Zr eutectic melting has been included within the FASTGRASS-VFP formalism. Results of the analyses demonstrate that intragranular fission product behavior during both types of tests can be interpreted in terms of a grain-growth/grain-boundary-sweeping mechanism that enhances the flow of fission products from within the grains to the grain boundaries. Whereas fuel liquefaction leads to an enhanced release of fission products in trace-irradiated fuel, the occurrence of fuel liquefaction in high-burnup fuel can degrade fission product release. This phenomenon is due in part to reduced gas-bubble mobilities in a viscous medium as compared to vapor transport, and in part to a degradation of grain growth rates and the subsequent decrease in grain-boundary sweeping of intragranular fission products into the liquefied lamina. The analysis shows that total UO 2 dissolution due to eutectic melting leads to increased release for both trace-irradiated and high-burnup fuel. The FASTGRASS-VFP predictions, measured release rates from the above tests, and previously published release rates are compared and differences between fission product behavior in trace-irradiated and in high-burnup fuel are highlighted

  10. Analisis Tingkat Kepentingan Dan Kinerja Layanan Automated Teller Machine (Atm) Bank Mandiri

    OpenAIRE

    Setiawati, Lenny; Sugiharto, Toto

    2008-01-01

    Penelitian ini ditujukan untuk menganalisis tingkat kepentingan dan kinerja layananATM Bank Mandiri. Analisis Servqual yang terdiri atas dimensi tangible, realibility,responsiveness, assurance,dan empathy digunakan untuk menganalisis kinerjalayanan ATM. Sementara itu, Customer Satisfaction Index dan ImportancePerformance Analysis yang terdiri atas analisis kuadran dan analisis kesenjangandigunakan untuk menginvestigasi kepuasan pelanggan dan untuk mengidentifikasikandimensi layanan yang kiner...

  11. Analysis of internal events for the Unit 1 of the Laguna Verde nuclear power station; Analisis de eventos internos para la Unidad 1 de la Central Nucleolelectrica de Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Huerta B, A.; Aguilar T, O.; Nunez C, A.; Lopez M, R. [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

    1993-07-01

    This volume presents the results of the starter event analysis and the event tree analysis for the Unit 1 of the Laguna Verde nuclear power station. The starter event analysis includes the identification of all those internal events which cause a disturbance to the normal operation of the power station and require mitigation. Those called external events stay beyond the reach of this study. For the analysis of the Laguna Verde power station eight transient categories were identified, three categories of loss of coolant accidents (LOCA) inside the container, a LOCA out of the primary container, as well as the vessel break. The event trees analysis involves the development of the possible accident sequences for each category of starter events. Events trees by systems for the different types of LOCA and for all the transients were constructed. It was constructed the event tree for the total loss of alternating current, which represents an extension of the event tree for the loss of external power transient. Also the event tree by systems for the anticipated transients without scram was developed (ATWS). The events trees for the accident sequences includes the sequences evaluation with vulnerable nucleus, that is to say those sequences in which it is had an adequate cooling of nucleus but the remoting systems of residual heat had failed. In order to model adequately the previous, headings were added to the event tree for developing the sequences until the point where be solved the nucleus state. This process includes: the determination of the failure pressure of the primary container, the evaluation of the environment generated in the reactor building as result of the container failure or cracked of itself, the determination of the localization of the components in the reactor building and the construction of boolean expressions to estimate the failure of the subordinated components to an severe environment. (Author)

  12. An integrated approach to the probabilistic assessments of aircraft strikes and structural mode of damages to nuclear power plants

    International Nuclear Information System (INIS)

    Godbout, P.; Brais, A.

    1975-01-01

    The possibilities of an aircraft striking a Canadian nuclear power plant in the vicinity of an airport and of inducing structural failure modes have been evaluated. This evaluation, together with other studies, may enhance decisions in the development of general criteria for the siting of reactors near airports. The study made use, for assessment, of the probabilistic approach and made judicious applications of the finite Canadian, French, German, American and English resources that were available. The tools, techniques and methods used for achieving the above, form what may be called an integrated approach. This method of approach requires that the study be made in six consecutive steps as follows: the qualitative evaluation of having an aircraft strike on a site situated near an airport with the use of the logic model technique; the statistical data gathering on aircraft movements and accidents; evaluating the probability distribution and calculating the basic event probabilities; evaluating the probability of an aircraft strike and the application of the sensitivity approach; generating the probability density distribution versus strike impact energy, that is, the evaluation of the energy envelope; and the probabilistic evaluation of structural failure mode inducements

  13. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  14. ANALISIS VARIABEL KEUANGAN YANG MEMPENGARUHI KEBIJAKAN DEVIDEN

    Directory of Open Access Journals (Sweden)

    Sumiadji -

    2012-03-01

    Full Text Available Penelitian ini dilakukan untuk menguji pengaruh variabel keuangan yang terdiri dari: rasio pro-fitabilitas (return on assets, likuiditas (cash ratio, rasio hutang (debt to equity ratio, market value (earnings per share, dan perputaran total aset (total assets turnover terhadap kebijakan dividen yang diproksikan dengan dividend payout ratio (DPR pada perusahaan manufaktur yang terdaftar di Bursa Efek Indonesia tahun 2004-2008. Prosedur pemilihan sampel penelitian menggunakan purposive sampling sehingga menghasilkan 8 perusahaan yang memenuhi kriteria sampel. Data sekunder dikumpulkan dengan teknik dokumentasi bersumber dari Indonesian Capital Market Directory (ICMD, laporan keuangan, dan hasil Rapat Umum Pemegang Saham (RUPS. Teknik analisis yang digunakan dalam penelitian ini adalah analisis regresi linear berganda. Hasil penelitian ini adalah secara simultan variabel ROA, CR, DER, EPS dan TATO berpengaruh terhadap DPR. Secara parsial variabel yang mempengaruhi DPR adalah CR, EPS dan TATO. Varabel lainnya, yaitu ROA dan DER ditemukan tidak berpengaruh terhadap DPR. This research was conducted to examine the influence of the financial variables which consists of: return on assets (ROA, cash ratio (CR, debt to equity ratio (DER, earnings per share (EPS, and total asset turnover (TATO to the dividend policy that indicated by the dividend payout ratio (DPR of listed manufacturing company in Indonesia Stock Exchange  2004 to 2008. The sample selection procedure used was a purposive sampling so that it produced eight companies that met the sample criteria. Se-condary data was collected by the documentation technique were obtained from the Indonesian Capital Market Directory (ICMD, financial statements, and the results of the Annual General Meeting of Shareholders. The analysis technique used was multiple linear regression analysis. The research found that five variables of kind of ROA, CR, DER, EPS dan TATO simultaneously influence to dividend

  15. Proliferating Cell Nuclear Antigen-dependent Rapid Recruitment of Cdt1 and CRL4Cdt2 at DNA-damaged Sites after UV Irradiation in HeLa Cells*

    Science.gov (United States)

    Ishii, Takashi; Shiomi, Yasushi; Takami, Toshihiro; Murakami, Yusuke; Ohnishi, Naho; Nishitani, Hideo

    2010-01-01

    The licensing factor Cdt1 is degraded by CRL4Cdt2 ubiquitin ligase dependent on proliferating cell nuclear antigen (PCNA) during S phase and when DNA damage is induced in G1 phase. Association of both Cdt2 and PCNA with chromatin was observed in S phase and after UV irradiation. Here we used a micropore UV irradiation assay to examine Cdt2 accumulation at cyclobutane pyrimidine dimer-containing DNA-damaged sites in the process of Cdt1 degradation in HeLa cells. Cdt2, present in the nucleus throughout the cell cycle, accumulated rapidly at damaged DNA sites during G1 phase. The recruitment of Cdt2 is dependent on prior PCNA chromatin binding because Cdt2 association was prevented when PCNA was silenced. Cdt1 was also recruited to damaged sites soon after UV irradiation through its PIP-box. As Cdt1 was degraded, the Cdt2 signal at damaged sites was reduced, but PCNA, cyclobutane pyrimidine dimer, and XPA (xeroderma pigmentosum, complementation group A) signals remained at the same levels. These findings suggest that Cdt1 degradation following UV irradiation occurs rapidly at damaged sites due to PCNA chromatin loading and the recruitment of Cdt1 and CRL4Cdt2, before DNA damage repair is completed. PMID:20929861

  16. Improved estimates of separation distances to prevent unacceptable damage to nuclear power plant structures from hydrogen detonation for gaseous hydrogen storage. Technical report

    International Nuclear Information System (INIS)

    1994-05-01

    This report provides new estimates of separation distances for nuclear power plant gaseous hydrogen storage facilities. Unacceptable damage to plant structures from hydrogen detonations will be prevented by having hydrogen storage facilities meet separation distance criteria recommended in this report. The revised standoff distances are based on improved calculations on hydrogen gas cloud detonations and structural analysis of reinforced concrete structures. Also, the results presented in this study do not depend upon equivalencing a hydrogen detonation to an equivalent TNT detonation. The static and stagnation pressures, wave velocity, and the shock wave impulse delivered to wall surfaces were computed for several different size hydrogen explosions. Separation distance equations were developed and were used to compute the minimum separation distance for six different wall cases and for seven detonating volumes (from 1.59 to 79.67 lbm of hydrogen). These improved calculation results were compared to previous calculations. The ratio between the separation distance predicted in this report versus that predicted for hydrogen detonation in previous calculations varies from 0 to approximately 4. Thus, the separation distances results from the previous calculations can be either overconservative or unconservative depending upon the set of hydrogen detonation parameters that are used. Consequently, it is concluded that the hydrogen-to-TNT detonation equivalency utilized in previous calculations should no longer be used

  17. ANALISIS VARIABILITAS CURAH HUJAN DAN SUHU DI BALI

    Directory of Open Access Journals (Sweden)

    Ogi Setiawan

    2017-01-01

    Full Text Available Indonesia sebagai negara kepulauan yang terdiri dari pulau-pulau besar dan kecil menjadi sangat rentan terhadap dampak perubahan iklim. Salah satu pulau yang juga rentan terhadap perubahan iklim adalah pulau Bali. Dampak potensial adanya perubahan iklim adalah perubahan pola hujan, peningkatan suhuudaradankenaikanpermukaanlaut. Sektoryangakanmenerimadampakperubahaniklimdengan serius adalah sektor kehutanan dan pertanian. Untuk mendukung upaya mitigasi dan adaptasi maka diperlukan informasi perubahan iklim yang terjadi. Penelitian ini bertujuan untuk mengetahui variabilitas iklim di Bali. Metode yang digunakan adalah analisis kecenderungan curah hujan, analisis perubahan suhu udara, analisis perubahan tipe iklim dan analisis pergeseran bulan basah, lembab dan kering. Data hujan yang digunakan adalah data hujan dari GPCC (1961-1998 dan BMKG Bali (19992008, sedangkan data suhu berasal dari BMKG Bali (2004-2008. Hasil analisis menunjukkan bahwa di pulau Bali secara umum sudah mengalami perubahan iklim. Tipe iklim berdasarkan Schmidt-Ferguson mengalami perubahan dari relatif basah menjadi agak kering. Suhu udara rata-rata bulanan serta curah hujan bulanan dan tahunan memiliki kecenderungan yang semakin meningkat. Bulan basah dan bulan kering telah mengalami pergeseran dan perubahan jumlahnya. Dampak perubahan iklim terhadap ekosistem hutan di Bali belum diketahui dengan pasti, namun terdapat beberapa implikasi perubahan iklim terhadap sektor kehutanan diantaranya kebakaran hutan dan perubahan jadwal penanaman.

  18. Kajian Eksperimental Parameter Modal Bangunan Dua Lantai dengan Metode Modal Analisis

    Directory of Open Access Journals (Sweden)

    Islahuddin Islahuddin

    2016-12-01

    Full Text Available Abstrak: Pengukuran getaran merupakan kegiatan yang umum dilakukan dalam perawatan prediktif. Perawatan prediktifbiasanya menggunakan pengukuran sinyal getaran untuk mendeteksi kerusakan yang terjadi pada mesin. Sinyalgetaran yang terukur tersebut, kemudian ditransformasikan dalam bentuk grafik fungsi respon frekuensi (FRF.Selanjutnya FRF diolah sedemikian rupasehingga diperoleh modus getar struktur. Dari modus getar yang diperoleh,maka dapat dianalisa kemungkinan kerusakan yang terjadi pada mesin dengan melihat besarnya amplitudo getarannya.Penelitian ini bertujuan untuk menganalisa karakteristik dinamik dari sistem getaran yang terjadi pada model strukturbangunan dua lantai. Pengujian dilakukan denganmemberikan gaya eksitasi menggunakan impact hammer.Akselerometer digunakan mengukur sinyal getaran yang terjadi pada struktur. Posisi penempatan akselerometerdilakukan bervariasi untuk delapan titik pengujian yang berbeda. Sedangkan posisi pemberian gaya eksitasi tetap untuksemua titik pengujian. Pada penelitian ini menggunakan metode modal analisis eksperimen untuk mengetahuikarakteristik dinamik dari model struktur bangunan dua lantai. Teknik modal analisis ini digunakan untuk mendapatkanparameter modal seperti frekuensi, rasio redaman, dan modus getar. Hasil yang diperoleh dari penelitian inimenunjukkan bahwafrekuensi pribadipertama pada amplitudo maksimum mempunyai nilai yang sama, yaitu 2,313 Hz.Sedangkan untuk frekuensi pribadi kedua pada amplitudo maksimumnya terdapat perbedaan, yaitu pada titik pengujian3 dan 7. Hal ini dapat disebabkan oleh pemberian gaya eksitasi yang tidak sama dengan titik-titik pengujian yang lain.Kata kunci: Karakteristik dinamik, analisis modal eksperimen, frekuensi pribadi, FRF Abstract: Measuring vibration is an activity which is generally carried out in a predictive maintenance. In maintaining, vibratesignal measurement is usually used for machine damage detection. The signal measurement is then being

  19. ANALISIS SKENARIO KEGAGALAN SISTEM UNTUK MENENTUKAN PROBABILITAS KECELAKAAN PARAH AP1000

    Directory of Open Access Journals (Sweden)

    D.T. Sony Tjahyani

    2014-03-01

    Full Text Available Kejadian Fukushima telah menunjukkan bahwa kecelakaan parah dapat terjadi, maka dari itu sangatlah penting untuk menganalisis tingkat keselamatan pada reaktor daya. Berdasarkan rekomendasi expert mission IAEA setelah kejadian Fukushima, perlu dilakukan upaya untuk meminimalisasi terjadinya kecelakaan parah yaitu dengan melakukan proses pendinginan yang maksimal. Dalam konsep keselamatan fasilitas nuklir, khususnya reaktor daya telah diterapkan konsep keselamatan berlapis (Defence in Depth, DiD. Konsep keselamatan tersebut terdiri atas 5 level pertahanan yang bertujuan mencegah dan mengurangi lepasan produk fisi ke masyarakat dan lingkungan pada saat reaktor daya mengalami kecelakaan. Dalam reaktor telah didesain sistem atau tindakan yang mempunyai fungsi untuk mengatasi setiap level tersebut. Tujuan dari analisis ini adalah menentukan probabilitas kecelakaan parah dengan melakukan skenario kegagalan sistem dalam proses pendinginan di reaktor. Sebagai obyek analisis adalah reaktor daya AP1000, karena jenis reaktor ini sedang banyak dibangun saat ini. Skenario dilakukan dengan mengasumsikan beberapa kombinasi kegagalan sistem yang termasuk dalam DiD level 2 dan 3. Kegagalan sistem kemudian dianalisis dengan menggunakan analisis pohon kegagalan berdasarkan perangkat lunak SAPHIRE ver. 6.76. Dari analisis didapatkan probabilitas gagal dari kelompok sistem DiD level 2 dan 3 pada AP1000 masih di bawah batas kriteria dari IAEA yaitu lebih kecil dari 10-2, serta probabilitas kecelakaan parah didapatkan sebesar 6,17 x 10-10. Berdasarkan analisis ini disimpulkan bahwa AP1000 mempunyai tingkat keselamatan yang cukup tinggi, karena melalui skenario kegagalan sistem didapatkan probabilitas kecelakaan parah yang sangat kecil.   ABSTRACT Fukushima accident has shown that severe accident could be occurred, therefore it is important to analyze safety level of nuclear power plants. Based on the recommendations of IAEA expert mission after the Fukushima accident

  20. Kembalikan Lagu Anak-anak Indonesia: Sebuah Analisis Struktur Musik

    Directory of Open Access Journals (Sweden)

    Ardipal - -

    2015-12-01

    Full Text Available ABSTRACT It appears there are two opposing poles of art music once intertwined within Indonesian society. That is music as art development in certain environments and music as commercial art. In terms of commercial music, almost two decades this song children disappear in the mass media. Was replaced by the song of adults. This certainly influenced the development of psychological, physical, and mental children. Theoretically, this problem this can be seen from the production of music through approach (1 konfik (hegemony and (2 the interpretation / meaning. This study aimed to compare the musical structure of children’s songs and musical structures adults. Data taken from children’s songs and pop songs adults. The method of analysis is focused on the features songs based on the structure of the music and effects. Is a key instrument in the researcher’s own research and auxiliary instruments in the form of codification guide data. Then describe the elements contained in some of the songs of children and adults. To maintain the validity of the data, performed data triangulation activity. Activity data analysis starts from the stage of selecting and codify the data, analyze the data according to the music features of each, and draw conclusions as well as the verification stage. From the data tracks taken as a sample, it appears that the pattern of rhythmic, melodic, intervals, tempo, tone range is not worthy to be sung by children. Coercion of children to imitate the song can be fatal as damage to the vocal cords, jaw muscle cramps. Finally, it is suggested that participants of art, and also Likewise art network infrastructure, must be able to have the same view and strong in the development of the art of music in Indonesia, especially for a children’s song. Keywords: children song, patriotic song, adult song, music structure. ABSTRAK Terlihat ada dua kutub seni musik yang bertentangan  sekaligus berjalin di dalam masyarakat Indonesia

  1. Korea act on compensation for nuclear damage (as amended on 16 January 2001). Norway act on radiation protection and use of radiation (12 May 2000). Poland atomic energy act (29 November 2000)

    International Nuclear Information System (INIS)

    2001-01-01

    This volume reprints the English and French translation of three nuclear laws. The first law concerns Korea and its purpose is to protect victims and to contribute to the sound development of the nuclear industry by establishing matters relating to compensation in the event of nuclear damage arising during the operation of a nuclear reactor. The second law concerns Norway and its purpose is to prevent the harmful effects of radiation on human health and to contribute to the protection of the environment. It applies to any production, import, export, transport, transfer, possession, installation, use, handling and waste management of radiation sources. It applies also to human activities which causes increased levels of naturally-occurring ionizing radiation in the environment, and to planning and emergency preparedness against incidents and accidents. The last law is the atomic energy act of Poland. It defines the activities related to the peaceful use of atomic energy, involving real and potential exposures to ionizing radiation emitted by artificial radioactive sources, nuclear materials, devices generating ionizing radiation, radioactive waste and spent fuel. It defines also duties of the head of the organisational entity conducting these activities, the authorities competent in the area of nuclear safety and radiological protection, and the principles of third party liability for nuclear damage. The act also establishes financial penalties for the violation of nuclear regulations and the rules for imposing such penalties. It applies also to practices conducted in conditions of exposure to natural ionizing radiation enhanced by human activity. Finally, it defines the principles of radioactive contamination monitoring and establishes rules governing activities undertaken in the event of a radiological emergency as well as in chronic exposure conditions in the aftermath of a radiological emergency or a past practice

  2. Deficiency in the nuclear factor E2-related factor 2 renders pancreatic β-cells vulnerable to arsenic-induced cell damage

    International Nuclear Information System (INIS)

    Yang, Bei; Fu, Jingqi; Zheng, Hongzhi; Xue, Peng; Yarborough, Kathy; Woods, Courtney G.; Hou, Yongyong; Zhang, Qiang; Andersen, Melvin E.; Pi, Jingbo

    2012-01-01

    Chronic human exposure to inorganic arsenic (iAs), a potent environmental oxidative stressor, is associated with increased prevalence of type 2 diabetes, where impairment of pancreatic β-cell function is a key pathogenic factor. Nuclear factor E2-related factor 2 (Nrf2) is a central transcription factor regulating cellular adaptive response to oxidative stress. However, persistent activation of Nrf2 in response to chronic oxidative stress, including inorganic arsenite (iAs 3+ ) exposure, blunts glucose-triggered reactive oxygen species (ROS) signaling and impairs glucose-stimulated insulin secretion (GSIS). In the current study, we found that MIN6 pancreatic β-cells with stable knockdown of Nrf2 (Nrf2-KD) by lentiviral shRNA and pancreatic islets isolated from Nrf2-knockout (Nrf2−/−) mice exhibited reduced expression of several antioxidant and detoxification enzymes in response to acute iAs 3+ exposure. As a result, Nrf2-KD MIN6 cells and Nrf2−/− islets were more susceptible to iAs 3+ and monomethylarsonous acid (MMA 3+ )-induced cell damage, as measured by decreased cell viability, augmented apoptosis and morphological change. Pretreatment of MIN6 cells with Nrf2 activator tert-butylhydroquinone protected the cells from iAs 3+ -induced cell damage in an Nrf2-dependent fashion. In contrast, antioxidant N‐acetyl cysteine protected Nrf2-KD MIN6 cells against acute cytotoxicity of iAs 3+ . The present study demonstrates that Nrf2-mediated antioxidant response is critical in the pancreatic β-cell defense mechanism against acute cytotoxicity by arsenic. The findings here, combined with our previous results on the inhibitory effect of antioxidants on ROS signaling and GSIS, suggest that Nrf2 plays paradoxical roles in pancreatic β-cell dysfunction induced by environmental arsenic exposure. -- Highlights: ► Lack of Nrf2 reduced expression of antioxidant genes induced by iAs 3+ in β-cells. ► Deficiency of Nrf2 in β-cells sensitized to iAs 3+ and MMA 3

  3. Deficiency in the nuclear factor E2-related factor 2 renders pancreatic β-cells vulnerable to arsenic-induced cell damage

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Bei [Institute for Chemical Safety Sciences, The Hamner Institutes for Health Sciences, 6 Davis Drive, Research Triangle Park, NC 27709 (United States); Department of Histology and Embryology, College of Basic Medical Sciences, China Medical University, Shenyang 110001 (China); Fu, Jingqi; Zheng, Hongzhi; Xue, Peng; Yarborough, Kathy; Woods, Courtney G.; Hou, Yongyong; Zhang, Qiang; Andersen, Melvin E. [Institute for Chemical Safety Sciences, The Hamner Institutes for Health Sciences, 6 Davis Drive, Research Triangle Park, NC 27709 (United States); Pi, Jingbo, E-mail: jpi@thehamner.org [Institute for Chemical Safety Sciences, The Hamner Institutes for Health Sciences, 6 Davis Drive, Research Triangle Park, NC 27709 (United States)

    2012-11-01

    Chronic human exposure to inorganic arsenic (iAs), a potent environmental oxidative stressor, is associated with increased prevalence of type 2 diabetes, where impairment of pancreatic β-cell function is a key pathogenic factor. Nuclear factor E2-related factor 2 (Nrf2) is a central transcription factor regulating cellular adaptive response to oxidative stress. However, persistent activation of Nrf2 in response to chronic oxidative stress, including inorganic arsenite (iAs{sup 3+}) exposure, blunts glucose-triggered reactive oxygen species (ROS) signaling and impairs glucose-stimulated insulin secretion (GSIS). In the current study, we found that MIN6 pancreatic β-cells with stable knockdown of Nrf2 (Nrf2-KD) by lentiviral shRNA and pancreatic islets isolated from Nrf2-knockout (Nrf2−/−) mice exhibited reduced expression of several antioxidant and detoxification enzymes in response to acute iAs{sup 3+} exposure. As a result, Nrf2-KD MIN6 cells and Nrf2−/− islets were more susceptible to iAs{sup 3+} and monomethylarsonous acid (MMA{sup 3+})-induced cell damage, as measured by decreased cell viability, augmented apoptosis and morphological change. Pretreatment of MIN6 cells with Nrf2 activator tert-butylhydroquinone protected the cells from iAs{sup 3+}-induced cell damage in an Nrf2-dependent fashion. In contrast, antioxidant N‐acetyl cysteine protected Nrf2-KD MIN6 cells against acute cytotoxicity of iAs{sup 3+}. The present study demonstrates that Nrf2-mediated antioxidant response is critical in the pancreatic β-cell defense mechanism against acute cytotoxicity by arsenic. The findings here, combined with our previous results on the inhibitory effect of antioxidants on ROS signaling and GSIS, suggest that Nrf2 plays paradoxical roles in pancreatic β-cell dysfunction induced by environmental arsenic exposure. -- Highlights: ► Lack of Nrf2 reduced expression of antioxidant genes induced by iAs{sup 3+} in β-cells. ► Deficiency of Nrf2 in

  4. Report realized on behalf of the Commission of the Foreign Affairs on the law project, adopted by the Senate, authorizing the approbation of the agreement between the French Republic Government and the Russian Federation Government relative to the civil liability concerning the nuclear damages occurring from the providing of goods devoted to nuclear installations in Russian Federation and coming from the French Republic

    International Nuclear Information System (INIS)

    Andre, R.

    2003-01-01

    In the framework of the civil liability concerning the nuclear damages occurring from the providing of goods devoted to the russian installations, this document presents the international cooperation between the France and the russian institutes and administrations. The objective of this document is to supply a juridical framework concerning the goods realized in Russia by France. The cooperation field with Russia is wide. Nevertheless, it concerns in first part, the 190 nuclear submarine dismantling. (A.L.B.)

  5. ANALISIS SPASIAL KEJADIAN DEMAM BERDARAH DENGUE BERDASARKAN KEPADATAN PENDUDUK

    Directory of Open Access Journals (Sweden)

    Agcrista Permata Kusuma

    2016-01-01

    Full Text Available Abstrak Puskesmas Kedungmundu merupakan wilayah endemis DBD dengan kasus yang tinggi. Diperlukan upaya dalam menentukan kebijakan strategi pengendalian vektor secara efektif dan efisien. Analisis spasial dalam SIG dapat digunakan untuk mengetahui pola penyebaran dan daerah potensi penularan DBD. Jenis penelitian ini adalah penelitian deskriptif analitik menggunakan pendekatan cross sectional. Teknik pengambilan sampel menggunakan sampel wilayah memperhatikan proporsi sampel dengan jumlah sampel 146 responden. Pengambilan titik koordinat menggunakan GPS. Analisis data menggunakan analisis univariat dan analisis spasial. Hasil perhitungan statistik spasial ANN diperoleh nilai Z-score = -11,054 terdapat pola spasial kasus DBD di wilayah kerja Puskesmas Kedungmundu. Nilai ANN = 0,52 < 1, artinya pola penyebaran kejadian DBD yang terjadi adalah berkerumun. Kesimpulan dalam penelitian ini sebaran kasus DBD memiliki keterkaitan secara spasial dengan kepadatan penduduk. Abstract Kedungmundu PHC is an endemich region with a high case. Be required to determine policy of vector control strategies effectively and efficiently. Spatial analsys in GIS can be used to determine the pattern of distribution and areas of DHF potential transmission. The type this research was analysis descriptive with cross sectional approach. The sampling technique used a sample area of attention to the proportion of the sample with 146 respondents of total sample. Capturing the coordinates used GPS. Data analisys used univariat and spatial analisys. Result of ANN obtained a Z-score= -11,054, there was a spatial pattern of dengue cases in Kedungmundu PHC. ANN value = 0,52 < 1, it meant that the pattern of DHF distribution was clustered. The conclution of this research was DHF distribution cases has spatial correlation with density population.

  6. ANALISIS GEN HAEMAGGLUTININ PADA VIRUS CAMPAK LIAR

    Directory of Open Access Journals (Sweden)

    Subangkit Subangkit

    2015-05-01

    Full Text Available AbstrakPenyakit Campak disebabkan oleh virus campak yang termasuk genus Morbilivirus dan Family Paramyxoviridae. Penyakit campak masih menjadi masalah kesehatan karena masih ditemukan Kejadian Luar Biasa (KLB di Indonesia. Salah satu penyebab terjadinya KLB tersebut diduga sebagaiakibat perbedaan antigenesitas antara strain vaksin yang digunakan dengan strain virus campak liar yang beredar di Indonesia. Penelitian ini bertujuan mendapatkan gambaran tentang karakteristik genetik gen Haemagglutinin virus campak liar yang ada di Indonesia. Spesimen yang digunakan sebanyak 27 isolat virus penyebab KLB dari 17 propinsi selama periode tahun 2003-2010. Isolat virus dilakukan pemeriksaan secara RT-PCR dan sekuensing dengan metode Sanger. Hasil sekuensing dianalisis dengan menggunakan perangkat lunak Bioedit 7.0 dan MEGA 4.0. Hasil penelitian didapatkan perbedaan 10 asam amino antara virus campak strain vaksin CAM-70 dan virus campak liar pada posisi D416N; K424T; V451M; N455T; V466I; I473T; F476L; Y481S atau Y481N; H495N; G505D. Kesimpulan penelitian ini adalah terdapat perbedaan karakteristik genetik antara virus campak liar di Indonesia berbeda dengan strain virus vaksin CAM-70.Kata kunci : Campak, Analisis Molekuler, Hemagglutinin, CD46AbstractMeasles is caused by virus belonging to the genus Morbilivirus and Family Paramyxoviridae. Measles is still a public health problem because outbreak of measles still found in Indonesia. Outbreak is suspected as a result of differences in antigenicity between vaccine strains used with wild-type measles virus strains circulating in Indonesia. This study aims to get genetic characteristics of wild-type measles virus haemagglutinin gene in Indonesia. The specimens were used 27 viral isolates from 17 provinces period 2003-2010. Viral isolates examined by RT-PCR and sequencing with Sanger method. Sequencing analysis were conducted using Bioedit 7.0 and MEGA 4.0 software. The results showed 10 amino acid differences

  7. Analisis Kelayakan Finansial Usaha Budidaya Bambu

    Directory of Open Access Journals (Sweden)

    Husnul Khotimah

    2015-12-01

    Full Text Available Budidaya bambu diperlukan untuk menambah populasi bambu yang cenderung berkurang yang disebabkan oleh beralihnya fungsi lahan yang digunakan untuk pemukiman atau diganti dengan komoditi tanaman lain yang dianggap lebih menguntungkan. Sementara itu kebutuhan bahan baku bambu terus meningkat sejalan dengan pertumbuhan penduduk dan perkembangan kemajuan ilmu pengetahuan. Budidaya bambu bermanfaat selain untuk menjaga ketersediaan suplai juga untuk meningkatkan kualitas bambu untuk memenuhi permintaan pasar. Tulisan ini mengkaji analisis finansial dari penanaman bambu. Kajian finansial dibutuhkan untuk menunjukkan bahwa upaya penanaman atau budidaya bambu ini layak atau tidak secara finansial untuk dilakukan. Data yang digunakan adalah data hasil penelitian di perusahaan perkebunan bambu PT XYZ di Lampung. Hasil penelitian menunjukkan bahwa nilai NPV (Rp 36.644.364,08 lebih besar dari nol, Net B/C (2,56 lebih besar dari satu, IRR (11 % lebih besar dari suku bunga 6 %, serta payback period pada tahun ke-9 umur proyek 15 tahun. Berdasarkan kriteria indikator kelayakan finansial dapat disimpulkan bahwa usaha budidaya bambu layak secara finansial untuk diusahakan. Katakunci: Hasil Hutan Bukan Kayu (HHBK, budidaya bambu, studi kelayakan, analisis finansial   Financial analysis and feasibity study of bamboo cultivation  Abstract Bamboo cultivation is necessary to increase the population of bamboo clumps. The bamboo clumps tend to decrease due to the shift of used lands for residential or replaced by other crop comodities, which are considered more profitable. On the other hand, the need of bamboo for raw materials remain increase in line with population growth and the development of science. The important of the bamboo cultivation are to maintain the availability of its supply and to improve the quality of bamboo, which meet the market demands. This paper examined financial analysis of bamboo cultivation. Financial study was necessary to show whether

  8. Analisis Korelasi Kanonik Hubungan Perilaku Pemimpin dan Motivasi Kerja Karyawan

    Directory of Open Access Journals (Sweden)

    I Gusti Ayu Made Srinadi

    2014-06-01

    Full Text Available Kualitas pemimpin merupakan penentu keberhasilan organisasi yang dipimpin. Hubungan antara pemimpin dengan karyawannya merupakan hubungan saling ketergantungan yang umumnya tidak seimbang. Dalam proses interaksi yang terjadi antara pemimpin dan karyawan, berlangsung proses saling memengaruhi. Penelitian ini bertujuan untuk mencari hubungan perilaku pemimpin terhadap motivasi kerja karyawan dengan menggunakan analisis korelasi kanonik. Pengujian dengan menggunakan analisis korelasi kanonik menunjukkan bahwa perilaku pemimpin dengan motivasi karyawan memiliki keeratan hubungan dengan nilai korelasi kanonik sebesar 0,9058533. Faktor perilaku pemimpin yang paling tinggi berkorelasi dengan motivasi kerja karyawan di McDonald’s Kuta Beach adalah faktor kemampuan mengarahkan dan menghadapi karyawan dengan nilai korelasi yaitu sebesar 0,7619707.

  9. Analisis Korelasi Kanonik Hubungan Perilaku Pemimpin dan Motivasi Kerja Karyawan

    Directory of Open Access Journals (Sweden)

    I Gusti Ayu Made Srinadi

    2015-04-01

    Full Text Available Kualitas pemimpin merupakan penentu keberhasilan organisasi yang dipimpin. Hubungan antara pemimpin dengan karyawannya merupakan hubungan saling ketergantungan yang umumnya tidak seimbang. Dalam proses interaksi yang terjadi antara pemimpin dan karyawan, berlangsung proses saling memengaruhi. Penelitian ini bertujuan untuk mencari hubungan perilaku pemimpin terhadap motivasi kerja karyawan dengan menggunakan analisis korelasi kanonik. Pengujian dengan menggunakan analisis korelasi kanonik menunjukkan bahwa perilaku pemimpin dengan motivasi karyawan memiliki keeratan hubungan dengan nilai korelasi kanonik sebesar 0,9058533. Faktor perilaku pemimpin yang paling tinggi berkorelasi dengan motivasi kerja karyawan di McDonald’s Kuta Beach adalah faktor kemampuan mengarahkan dan menghadapi karyawan dengan nilai korelasi yaitu sebesar 0,7619707.

  10. Analisis Aliran Daya Berbasis Injeksi Arus dalam Bentuk Vektor

    Directory of Open Access Journals (Sweden)

    Ahmad Wira Satriawan

    2017-11-01

    Full Text Available Tulisan ini memaparkan hasil penelitian yang telah dilakukan untuk membandingkan metode analisis aliran daya berbasis injeksi arus dalam bentuk vektor dengan format polar dan rektangular. Penelitian ini dilakukan untuk memperoleh metode analisa aliran daya dengan perhitungan yang lebih cepat dan akurat, serta iterasi yang lebih sedikit. Metode iterasi Newton Raphson diadopsi dalam penelitian ini dan bahasa pemrograman Python serta library komputasinya digunakan. Analisis terhadap karakteristik konvergensi dari kedua format dilakukan pada IEEE 14-bus Test System. Dari penelitian ini diperoleh hasil bahwa format rektangular lebih unggul dibandingkan format polar untuk kasus yang diteliti.

  11. Nedd4 family interacting protein 1 (Ndfip1) is required for ubiquitination and nuclear trafficking of BRCA1-associated ATM activator 1 (BRAT1) during the DNA damage response.

    Science.gov (United States)

    Low, Ley-Hian; Chow, Yuh-Lit; Li, Yijia; Goh, Choo-Peng; Putz, Ulrich; Silke, John; Ouchi, Toru; Howitt, Jason; Tan, Seong-Seng

    2015-03-13

    During injury, cells are vulnerable to apoptosis from a variety of stress conditions including DNA damage causing double-stranded breaks. Without repair, these breaks lead to aberrations in DNA replication and transcription, leading to apoptosis. A major response to DNA damage is provided by the protein kinase ATM (ataxia telangiectasia mutated) that is capable of commanding a plethora of signaling networks for DNA repair, cell cycle arrest, and even apoptosis. A key element in the DNA damage response is the mobilization of activating proteins into the cell nucleus to repair damaged DNA. BRAT1 is one of these proteins, and it functions as an activator of ATM by maintaining its phosphorylated status while also keeping other phosphatases at bay. However, it is unknown how BRAT1 is trafficked into the cell nucleus to maintain ATM phosphorylation. Here we demonstrate that Ndfip1-mediated ubiquitination of BRAT1 leads to BRAT1 trafficking into the cell nucleus. Without Ndfip1, BRAT1 failed to translocate to the nucleus. Under genotoxic stress, cells showed increased expression of both Ndfip1 and phosphorylated ATM. Following brain injury, neurons show increased expression of Ndfip1 and nuclear translocation of BRAT1. These results point to Ndfip1 as a sensor protein during cell injury and Ndfip1 up-regulation as a cue for BRAT1 ubiquitination by Nedd4 E3 ligases, followed by nuclear translocation of BRAT1. © 2015 by The American Society for Biochemistry and Molecular Biology, Inc.

  12. ANALISIS FAKTOR KEHADIRAN DOSEN DI UNIVERSITAS X

    Directory of Open Access Journals (Sweden)

    Annisa Mulia Rani

    2016-10-01

    Full Text Available Aspek kualitas pekerjaan berkaitan langsung dengan waktu yang khusus digunakan dosen untuk mengembangkan kemampuan. Maka untuk merealisasikan kualitas dosen yang terbaik , pihak manajemen khusunya dekan membuat peraturan untuk kehadiran dosen adalah minimal 25 jam/minggu. Dengan peraturan ini diharapkan dosen dapat melaksanakan beban kerja dosen sebaik-baiknya. Peraturan ini tertulis dan tertuang pada SK Dekan No 20/2006 pada kampus X. Dengan Menggunakan Analisis faktor mencoba menemukan hubungan atar sejumlah variable-variabel yang awalnya saling independen satu dengan yang lain dimana variable penyebab kekurangan jam dosen datang/minggu adalah keluaraga, manajemen, hubungan social, fasilitas pengajaran, jarak/lokasi, kompensasi transport. Berdasarkan uji Bartley test dan Measure sample of adequate yang pertama maka dengan nilai sig 0.04 dan msa 0.540 . Dengan menggunakan metode principal component analysis maka pembentukan factor hanya ada 1 componen karena nilai eigen value yang mempunyai nilai diatas 1. Faktor pembentuk baru yaitu manajemen, kompensasi dan jarak menjadi satu component.

  13. Analisis Gameplay Game Genre Virtual Pet

    Directory of Open Access Journals (Sweden)

    Abi Senoprabowo

    2015-02-01

    Full Text Available Game adalah struktur interaktif yang membuat pemain berjuang menuju sebuah tujuan. Game dapat memberikan emosi dan mood, menghubungkan dengan orang latihan, sarana latihan, serta dapat memberikan edukasi. Salah satu game yang berkembang saat ini adalah game bergenre Virtual pet. Game virtual pet merupakan game simulasi memelihara sesuatu. Virtual pet memiliki gameplay yang menarik dan menyenangkan yang membuat pemain seolah-olah benar-benar memiliki binatang peliharaan mereka sendiri. Virtual pet dianggap oleh sebagian besar penggunanya dapat memberikan kegembiraan serta rasa kasih sayang karena tingkat interaksinya yang baik. Banyak pengembang game pemula yang mengembangkan genre ini sebagai game yang mereka buat karena kemudahaan dan tingkat penggunanya yang banyak. Akan tetapi banyak dari pengembang game pemula tidak memperhatikan tingkat keberlanjutan game virtual pet yang mereka buat sehingga membuat pemain cepat bosan. Pada penelitian ini, analisis game bergenre virtual pet yang sudah sukses dibuat seperti Zombigotchi, Tamagotchi Unicorn, dan Bird Land, diharapkan dapat membantu para pengembang game pemula agar mengetahui cara merancang dan mengembangkan game virtual pet dengan baik. Kata Kunci: game, gameplay, virtual pet

  14. ANALISIS MODEL KEPUASAN TERHADAP PEMBELIAN ULANG

    Directory of Open Access Journals (Sweden)

    Naili Farida

    2014-09-01

    Full Text Available Tujuan penelitian ini yaitu untuk menguji pengaruh brand equity, nilai pelanggan dan lifestyle yang dimediasi kepuasan konsumen terhadap pembelian ulang produk gadget di Kota Semarang. Responden dalam penelitian ini adalah seluruh konsumen yang telah melakukan pembelian produk gadget merek Samsung, sebanyak 120 orang. Teknik sampling yang digunakan yaitu purposive sampling. Teknik analisis yang digunakan yaitu Partial Least Square (PLS. Hasil penelitian menunjukkan bahwa terdapat pengaruh brand equity terhadap kepuasan, namun dalam konteks lifestyle dan nilai pelanggan tidak ada pengaruh terhadap kepuasan. Sedangkan kepuasan menunjukkan adanya pengaruh terhadap pembelian ulang. Diharapkan dari hasil penelitian ini mampu meningkatkan pembelian ulang melalui brand equity, lifestyle dan nilai pelanggan dalam konteks kepuasan. The objective of the research was to test the influence of brand equity, customer value and lifestyle which were mediated by consumer satisfaction toward re-purchasing of gadget products in Semarang. The respondents of the study were all consumers who have purchased Samsung gadget products. It was a purposive sampling study with 120 respondents. The data were analyzed by Partial Least Square (PLS. The result of the study showed that there was an influence of brand equity toward satisfaction, but in the lifestyle context and customer value did not give any influence toward satisfaction. Whereas; the satisfaction gave influence toward re-purchase. It is expected that this study can increase the repurchasethrough brand equity, lifestyle and customer values in the satisfaction context.

  15. The chromosome damage induced by x-ray radiation doses. Comparison between dicentric chromosomes, micronuclei and Sister Chromatid Exchanges analyses. Valoracion de dao cromosomico originado por una dosis de rayos X. Comparacion de los analisis de cromosomas dicentricos, micronucleos e intercambios entre cromatidas hermanas

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez, J.L.; Losada, C.; Losada, G.; Veiras, C. (Centro Oncologico de Galicia. La Corua (Spain)); Goyanes, V.J. (Hospital ' ' Teresa Herrera' ' . La Corua (Spain))

    1993-01-01

    Exposure to ionizing radiations is a well-known source of chromosome damage. Here we present a comparison among three different methodologies employed to recognize cytogenetic damage, after an acute exposure of human lymphocytes to 3 Gy of X-rays (100kVp). Scoring of dicentric chromosomes, present in first mitosis ''in vitro'', was the method of preference as dicentrics increased 937.5 times with respect to background. Micronucleus scoring in binucleated-cytokinesis blocked cells showed an increase of 32.5 times, while it was only of 1.46 times when Sister Chromatid Exchanges (SCEs) were analyzed. The estimated probability of an acentric fragment becoming a micronucleus was around 0.25. Intercellular distribution of dicentrics agree with Poisson, while micronucleus were overdispersed. When analyzed at second cycle after damage induction, the dicentrics yield as well as the level of cells with unstable cromosome aberrations, decreased around a half. Finally, SCEs level was similar in cells with or without unstable structural chromosome aberrations. (Author)

  16. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The first text deals with a new circular concerning the collect of the medicine radioactive wastes, containing radium. This campaign wants to incite people to let go their radioactive wastes (needles, tubes) in order to suppress any danger. The second text presents a decree of the 31 december 1999, relative to the limitations of noise and external risks resulting from the nuclear facilities exploitation: noise, atmospheric pollution, water pollution, wastes management and fire prevention. (A.L.B.)

  17. Earthquake damage to underground facilities

    International Nuclear Information System (INIS)

    Pratt, H.R.; Hustrulid, W.A.; Stephenson, D.E.

    1978-11-01

    The potential seismic risk for an underground nuclear waste repository will be one of the considerations in evaluating its ultimate location. However, the risk to subsurface facilities cannot be judged by applying intensity ratings derived from the surface effects of an earthquake. A literature review and analysis were performed to document the damage and non-damage due to earthquakes to underground facilities. Damage from earthquakes to tunnels, s, and wells and damage (rock bursts) from mining operations were investigated. Damage from documented nuclear events was also included in the study where applicable. There are very few data on damage in the subsurface due to earthquakes. This fact itself attests to the lessened effect of earthquakes in the subsurface because mines exist in areas where strong earthquakes have done extensive surface damage. More damage is reported in shallow tunnels near the surface than in deep mines. In mines and tunnels, large displacements occur primarily along pre-existing faults and fractures or at the surface entrance to these facilities.Data indicate vertical structures such as wells and shafts are less susceptible to damage than surface facilities. More analysis is required before seismic criteria can be formulated for the siting of a nuclear waste repository

  18. Estimated airborne release of plutonium from Atomics International's Nuclear Materials Development Facility in the Santa Susana site, California, as a result of postulated damage from severe wind and earthquake hazard

    International Nuclear Information System (INIS)

    Mishima, J.; Ayer, J.E.

    1981-09-01

    The potential mass of airborne releases of plutonium (source term) that could result from wind and seismic damage is estimated for the Atomics International Company's Nuclear Materials Development Facility (NMDF) at the Santa Susana site in California. The postulated source terms will be useful as the basis for estimating the potential dose to the maximum exposed individual by inhalation and to the total population living within a prescribed radius of the site. The respirable fraction of airborne particles is thus the principal concern. The estimated source terms are based on the damage ratio, and the potential airborne releases if all enclosures suffer particular levels of damage. In an attempt to provide a realistic range of potential source terms that include most of the normal processing conditions, a best estimate bounded by upper and lower limits is provided. The range of source terms is calculated by combining a high best estimate and a low damage ratio, based on a fraction of enclosures suffering crush or perforation, with the airborne release from enclosures based upon an upper limit, average, and lower limit inventory of dispersible materials at risk. Two throughput levels are considered. The factors used to evaluate the fractional airborne release of materials and the exchange rates between enclosed and exterior atmospheres are discussed. The postulated damage and source terms are discussed for wind and earthquake hazard scenarios in order of their increasing severity

  19. ANALISIS KONTRIBUSI PAJAK HOTEL TERHADAP PENDAPATAN ASLI DAERAH KABUPATEN NUNUKAN

    OpenAIRE

    -, MULIATI

    2014-01-01

    2014 Analisis Kontribusi Pajak Hotel terhadap Pendapatan Asli Daerah Kabupaten Nunukan Analysis of The Contributions Tax on Hotel Againts Regional Renenue Nunukan District Muliati Haerial M. Christian Mangiwa Penelitian ini bertujuan untuk mengetahui seberapa besar kontribusi pajak hotel terhadap pendapatan asli daerah, mengetahui sistem pengawasan, dan potensi yang ada untuk meningkatkan pajak hotel, mengetahui sistem dan prosedur...

  20. Analisis Sektor/Sub Sektor Unggulan di Kabupaten Bungo

    Directory of Open Access Journals (Sweden)

    Gafur Gafur

    2016-03-01

    Full Text Available Abstract. This study aimed to analyze the leading sectors in Bungo. The method used is Location Quotient (LQ, Dynamic Location Quotient (DLQ, specialization index, Growth Ratio Model (MRP. Based on analysis of LQ and DLQ, there are only two basis sectors at present and in the future, namely the construction sector and trade, hotels and restaurants. Based on the analysis of Specialization Index, in Bungo Regency has a concentration of the economy in the agricultural sector and the manufacturing sector. Based on MRP analysis also showed that prominent sector growth at the level of Bungo and Jambi Province, namely electricity, gas and water supply; the building sector; and trade, hotels and restaurants. Keywords : Location Quotient (LQ, Dinamic Location Quotient (DLQ, Specialization Index, Growth Ratio Model   Abstrak. Penelitian ini bertujuan untuk menganalisis sektor unggulan di Kabupaten Bungo. Metode yang digunakan adalah analisis Location Quotient (LQ, Dinamic Location Quotient (DLQ, indeks spesialisasi, Model Rasio Pertumbuhan (MRP. Berdasarkan analisis LQ dan DLQ,  hanya ada 2 sektor yang menjadi sektor basis pada saat ini dan pada masa yang akan datang yaitu sektor bangunan dan sektor perdagangan, hotel dan restoran. Berdasarkan analisis Indeks Spesialisasi, di Kabupaten Bungo telah terjadi konsentrasi ekonomi pada sektor pertanian dan sektor industri pengolahan. Berdasarkan analisis MRP juga dapat diketahui bahwa sektor yang menonjol pertumbuhannya pada tingkat Kabupaten Bungo dan Provinsi Jambi yaitu sektor listrik, gas dan air bersih; sektor bangunan; serta sektor perdagangan, hotel dan restoran. Kata Kunci : Location Quotient (LQ, Dinamic Location Quotient (DLQ, indeks spesialisasi, Model Rasio Pertumbuhan

  1. Seguro Nuclear

    International Nuclear Information System (INIS)

    Oliveira, S.C.C. de.

    1978-04-01

    A description of the constitutive elements of insurance and its features in the field of law, and special legislation about the matter are given. The relationship between the liability of the nuclear power plant operator and the international conventions about civil liability on nuclear damage is discussed. Some considerations on damage reparing in the United States, Germany, France and Spain are presented. (A.L.S.L.) [pt

  2. ANALISIS KINERJA DENGAN MENGGUNAKAN PENDEKATAN RASIO CAMEL

    Directory of Open Access Journals (Sweden)

    Sri Murdiati

    2015-06-01

    Full Text Available Tujuan penelitian ini adalah untuk menganalisis tingkat kesehatan bank dilihat dari kategori CAMEL. Metode penelitian yang digunakan adalah studi kasus di PD BPR BKK Banjarharjo.Dalam menguji hipotesis digunakan alat analisis CAMEL. Hasil penelitian ini yaitu modal pada 2008 sampai 2010 termasuk dalam kriteria sehat. ROA meningkat 2008 sampai 2010 dengan kriteria sehat bagi biaya operasional yang dikeluarkan oleh pendapatan operasional yang seimbang. Rasio Kas tahun 2008 sampai 2010 termasuk dalam kriteria sehat berarti bank memiliki kemampuan untuk mengelola asset yang digunakan untuk membayar kewajiban. LDR mengalami tren yang signifikan selama tahun 2008 sampai 2010 sehingga dana yang diterima bank untuk meningkatkan baik tabungan, deposito berjangka, modal inti, yang berarti kemampuan bank untuk meningkatkan penyaluran kredit, IRR menunjukan nilai positif dalam menghadapi resiko pasar.Pengembangan tingkat kesehatan pada tahun 2008 sampai 2010 untuk komponen Capital, Assets, Laba dan Likuiditas meningkat. The goal of this research is to analyze the healtiness of banks seen from CAMEL category. The research applied a case study in PD BPR BKK Banjarharjo. The hypotheses tested using CAMEL analysis tools. The result of the study is that the modal used 2008 until 2010 is consideredin a healthy criteria. The increasing ROA in 2008 until 2010 is considered healthy criteria for operational expenses incurred by the operating income. Such condition meant that the banks are able to manage the assets which are used to pay the obligations. The significant increasing of LDR over the years 2008 until 2010 makes the received funds by the bank to increase the savings deposits, time deposits and the core capital. As the recunts, the banks are able to increase credit disstribution. More over, the IRR showed a positive values in the face of market risks and the development of healthy levels in 2008 until 2010 for the components of Capital, Assets, Earnings and

  3. Vienna convention on civil liability for nuclear damage and optional protocol concerning the compulsory settlement of disputes. Status lists as of 12 September 2000. Signature, ratification, accession, or succession. Declarations/reservations made upon expressing consent to be bound and objections thereto. Declarations/reservations made upon signature

    International Nuclear Information System (INIS)

    2000-01-01

    The document provides the status list to the Protocol to Amend the Vienna Convention on Civil Liability for Nuclear Damage and optional protocol concerning the compulsory settlement of disputes as of 12 September 2000

  4. Radiation-induced damage of membranes

    International Nuclear Information System (INIS)

    Yonei, Shuji

    1977-01-01

    An outline of membranous structure was stated, and radiation-induced damage of membranes were surveyed. By irradiation, permeability of membranes, especially passive transportation mechanism, was damaged, and glycoprotein in the surface layers of cells and the surface layer structures were changed. The intramembranous damage was induced by decrease of electrophoresis of nuclear mambranes and a quantitative change of cytochrome P450 of microsomal membranes of the liver, and peroxidation of membranous lipid and SH substitute damage of membranous protein were mentioned as the mechanism of membranous damage. Recovery of membranous damage depends on radiation dose and temperature, and membranous damage participates largely in proliferation death. (tsunoda, M.)

  5. Optimization of investment economic in PCI using the methodology of benefits design in analysis of the spread of fires with FDS (Fire Dynamics Simulator) in areas of nuclear fire; Optimizacion de la inversion economica en PCI mediante la metodologia de diseo prestaional en el analisis de la propagacion de incendios con FDS (Fire Dynnamics Simulator) en areas de fuego de centrales nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Salellas, J.

    2015-07-01

    Fire simulation analysis allows knowing the evolution and spread fire in areas of interest within a NPP such as control room, cable room and multi zone comportment among others. fires are a main concern regarding safety analysis of NPP. IDOM has the capability to carry out fire simulations, taken in to account smoke control, fire spread, toxicity levels, ventilation and all physical phenomena. As a result, appropriate fire protection measures can be assessed in each scenario. CFD tools applied to fire simulations can determine with higher resolution all damages caused during the fire. Furthermore, such tools can reduce costs due to a lower impact of design modifications. (Author)

  6. Development of a dynamical model of a nuclear processes simulator for analysis and training in classroom based in the RELAP/SCDAP codes; Desarrollo del modulo dinamico del simulador de procesos nucleares para analisis y entrenamiento en aula basado en los codigos RELAP/SCDAP

    Energy Technology Data Exchange (ETDEWEB)

    Salazar C, J.H.; Ramos P, J.C.; Salazar S, E.; Chavez M, C. [UNAM, Fac. de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, DEPFI Campus Morelos, Cuernavaca (Mexico)]. e-mail: cchavez2@cableonline.com.mx

    2003-07-01

    The present work illustrates the application of the concept of a simulator for analysis, design, instruction and training in a classroom environment associated to a nuclear power station. Emphasis is made on the methodology used to incorporate the best estimate codes RELAP/SCDAP to a prototype under development at the Nuclear Reactor Engineering Analysis Laboratory (NREAL). This methodology is based on a modular structure where multiple processes can be executed in an independent way and where the generated information is stored in shared memory segments and distributed by means of communication routines developed in the C programming language. The utility of the system is demonstrated using highly interactive graphics (mimic diagrams, pictorials and tendency graphs) for the simultaneous dynamic visualization of the most significant variables of a typical transient event (feed water controller failure in a BWR). A fundamental part of the system is its advanced graphic interface. This interface, of the type of direct manipulation, reproduces instruments and controls whose functionality is similar to those found in the current replica simulator for the Laguna Verde Nuclear Power Station. Finally the evaluation process is described. The general behavior of the main variables for the selected transitory event is interpreted, corroborating that they follow the same tendency that those reported for a BWR. The obtained results allow to conclude that the developed system works satisfactorily and that the use of al 1 x 1 real time visualization tools offers important advantages regarding other traditional methods of analysis. (Author)

  7. Analysis of the micro-structural damages by neutronic irradiation of the steel of reactor vessels of the nuclear power plant of Laguna Verde. Characterization of the design steel

    International Nuclear Information System (INIS)

    Moranchel y Rodriguez, M.; Garcia B, A.; Longoria G, L. C.

    2010-09-01

    The vessel of a nuclear reactor is one of the safety barriers more important in the design, construction and operation of the reactor. If the vessel results affected to the grade of to have fracture and/or cracks it is very probable the conclusion of their useful life in order to guarantee the nuclear safety and the radiological protection of the exposure occupational personnel, of the public and the environment avoiding the exposition to radioactive sources. The materials of the vessel of a nuclear reactor are exposed continually to the neutronic irradiation that generates the same nuclear reactor. The neutrons that impact to the vessel have the sufficient energy to penetrate certain depth in function of the energy of the incident neutron until reaching the repose or to be absorbed by some nucleus. In the course of their penetration, the neutrons interact with the nuclei, atoms, molecules and with the same crystalline nets of the vessel material producing vacuums, interstitial, precipitate and segregations among other defects that can modify the mechanical properties of the steel. The steel A533-B is the material with which is manufactured the vessel of the nuclear reactors of nuclear power plant of Laguna Verde, is an alloy that, among other components, it contains atoms of Ni that if they are segregated by the neutrons impact this would favor to the cracking of the same vessel. This work is part of an investigation to analyze the micro-structural damages of the reactor vessels of the nuclear power plant of Laguna Verde due to the neutronic irradiation which is exposed in a continuous way. We will show the characterization of the design steel of the vessel, what offers a comprehension about their chemical composition, the superficial topography and the crystalline nets of the steel A533-B. It will also allow analyze the existence of precipitates, segregates, the type of crystalline net and the distances inter-plains of the design steel of the vessel. (Author)

  8. Project of law authorizing the approval of the agreement between the government of the French republic and the government of the Russian federation relative to the civil liability by way of nuclear damage owing to the supply of materials from the French republic devoted to nuclear facilities in the Russian federation

    International Nuclear Information System (INIS)

    Raffarin, J.P.; Villepin, D. de

    2002-01-01

    An agreement between France and Russia was signed on June 20, 2000 about the civil liability of Russia because of the supply of French material devoted to Russian nuclear facilities. This agreement was necessary because Russia do not belong to any of the two big international civil liability systems relative to nuclear energy, i.e. the Paris convention from July 29, 1960 (in the OECD framework) and the Vienna convention from May 21, 1963 (in the IAEA framework). This agreement offers a protection to the French nuclear suppliers against any damage claims in the case of a nuclear accident occurring on the Russian federation territory. This project of law aims at approving this agreement. (J.S.)

  9. Royal Order of 13 May 1980 fixing the maximum amount of liability of the operator for damage caused by a nuclear incident

    International Nuclear Information System (INIS)

    1980-01-01

    The purpose of this Order is to raise the maximum liability of the nuclear operator to one milliard Belgium francs per nuclear incident. This measure was taken with a view to keeping the operator's maximum liability at least at a constant value. (NEA) [fr

  10. Analisis Pembiayaan Kesehatan Keluarga Penderita Talasemia

    Directory of Open Access Journals (Sweden)

    Arif Kurniawan

    2013-04-01

    Full Text Available Pembiayaan kesehatan sekitar 146 (60% penderita talasemia di Banyumas, tahun 2011 ditanggung rumah tangga dalam bentuk pembayaran langsung (out of pocket payment. Penelitian ini bertujuan untuk menganalisis ability to pay, willingness to pay, dan need assessment pembiayaan kesehatan penderita talasemia di Kabupaten Banyumas. Jenis penelitian ini adalah observasional analitik dengan rancangan studi kasus. Penelitian ini menggunakan desain studi cross sectional dengan teknik pengambilan sampel simple random sampling. Jumlah sampel penelitian 30 responden yang mempunyai anggota keluarga penderita talasemia di Kabupaten Banyumas. Hasil penelitian menunjukkan keluarga penderita talasemia mempunyai ability to pay rata-rata adalah Rp34.448,8/bulan dan rata-rata willingness to pay pengobatan talasemia adalah Rp133.833,3/ bulan. Pola pembiayaan kesehatan talasemia di Kabupaten Banyumas menggunakan 93,3% Jaminan Kesehatan Masyarakat (Jamkesmas, 3,3% biaya sendiri, dan 3,3% asuransi kesehatan. Sebelum mendapatkan Jamkesmas, 90,0% responden membayar dengan out of pocket, berhutang, berhemat pada kebutuhan nonkesehatan, dan menjual perhiasan/sawah. Kebutuhan pelayanan kesehatan yang diharapkan keluarga penderita talasemia adalah konsultasi talasemia dan desain khusus ruang perawatan anak. Kebutuhan pembiayaan kesehatan keluarga penderita talasemia adalah uang transportasi ke rumah sakit sebagai bentuk biaya tidak langsung. Health financing of majority thalassemia patients, around 146 people (60% in Banyumas year 2011 is assured by Households in direct payments to health care providers (out-of-pocket payment. This study aimed to analyze the ability to pay, willingness to pay, and need assessment of health financing thalassemia in Banyumas. This research an analytic observation- Analisis Pembiayaan Kesehatan Keluarga Penderita Talasemia Health Financing Analysis of Thalassemia Patient Family Arif Kurniawan, Arih Diyaning Intiasari al with case study design

  11. Nuclear survivin and its relationship to DNA damage repair genes in non-small cell lung cancer investigated using tissue array.

    Directory of Open Access Journals (Sweden)

    Songliu Hu

    Full Text Available To investigate the predictive role and association of nuclear survivin and the DNA double-strand breaks repair genes in non-small cell lung cancer (NSCLC: DNA-dependent protein kinase catalytic subunit (DNA-PKcs, Ku heterodimeric regulatory complex 70-KD subunit (Ku70 and ataxia-telangiectasia mutated (ATM.The protein expression of nuclear survivin, DNA-PKcs, Ku70 and ATM were investigated using immunohistochemistry in tumors from 256 patients with surgically resected NSCLC. Furthermore, we analyzed the correlation between the expression of nuclear survivin, DNA-PKcs, Ku70 and ATM. Univariate and multivariate analyses were performed to determine the prognostic factors that inuenced the overall survival and disease-free survival of NSCLC.The expression of nuclear survivin, DNA-PKcs, Ku70 and ATM was significantly higher in tumor tissues than in normal tissues. By dichotomizing the specimens as expressing low or high levels of nuclear survivin, nuclear survivin correlated significantly with the pathologic stage (P = 0.009 and lymph node status (P = 0.004. The nuclear survivin levels were an independent prognostic factor for both the overall survival and the disease-free survival in univariate and multivariate analyses. Patients with low Ku70 and DNA-PKcs expression had a greater benefit from radiotherapy than patients with high expression of Ku70 (P = 0.012 and DNA-PKcs (P = 0.02. Nuclear survivin expression positively correlated with DNA-PKcs (P<0.001 and Ku70 expression (P<0.001.Nuclear survivin may be a prognostic factor for overall survival in patients with resected stage I-IIIA NSCLC. DNA-PKcs and Ku70 could predict the effect of radiotherapy in patients with NSCLC. Nuclear survivin may also stimulates DNA double-strand breaks repair by its interaction with DNA-PKcs and Ku70.

  12. Nuclear Installations Act 1965

    International Nuclear Information System (INIS)

    1965-01-01

    This Act governs all activities related to nuclear installations in the United Kingdom. It provides for the licensing procedure for nuclear installations, the duties of licensees, the competent authorities and carriers of nuclear material in respect of nuclear occurrences, as well as for the system of third party liability and compensation for nuclear damage. The Act repeals the Nuclear Installations (Licensing and Insurance) Act 1959 and the Nuclear Installations (Amendment Act) 1965 except for its Section 17(2). (NEA) [fr

  13. Estimated airborne release of plutonium from the 102 Building at the General Electric Vallecitos Nuclear Center, Vallecitos, California, as a result of postulated damage from severe wind and earthquake hazard

    International Nuclear Information System (INIS)

    Mishima, J.; Ayer, J.E.; Hays, I.D.

    1980-12-01

    This report estimates the potential airborne releases of plutonium as a consequence of various severities of earthquake and wind hazard postulated for the 102 Building at the General Electric Vallecitos Nuclear Center in California. The releases are based on damage scenarios developed by other specialists. The hazard severities presented range up to a nominal velocity of 230 mph for wind hazard and are in excess of 0.8 g linear acceleration for earthquakes. The consequences of thrust faulting are considered. The approaches and factors used to estimate the releases are discussed. Release estimates range from 0.003 to 3 g Pu

  14. Analisis Komoditi Unggulan Subsektor Tanaman Pangan di Sumatera Utara Tahun 2010 – 2014

    OpenAIRE

    Sinaga, Terry Praganda

    2016-01-01

    Tujuan penelitian ini adalah untuk mengetahui perkembangan produksi komoditi tanaman pangan selama periode tersebut sehingga dapat menganalisis komoditi subsektor tanaman pangan yang menjadi unggulan di Sumatera Utara. Komoditi unggulan tersebut juga dijabarkan untuk setiap kabupatem/kota yang ada di Sumatera Utara. Metode yang digunakan yaitu secara Convenience Sampling, dan metode analisis data dengan menggunakan analisis Location Quotient. Hasil penelitian menyimpulkan ba...

  15. ANALISIS KINERJA KEUANGAN PERUSAHAAN PT. ASURANSI JIWASRAYA (PERSERO) CABANG SULAWESI SELATAN

    OpenAIRE

    ARIANTY, ASTRI

    2012-01-01

    ANALISIS KINERJA KEUANGAN PERUSAHAAN PT. ASURANSI JIWASRAYA (PERSERO) CABANG SULAWESI SELATAN COMPANY FINANCIAL PERFORMANCE ANALYSIS PT. INSURANCE JIWASRAYA (LIMITED) SOUTH BRANCH SULAWESI Astri Arianty Prof. Dr. H. Muhammad Ali, SE., M.S Drs. Armayah Sida, M.Si Analisis terhadap kinerja keuangan perusahaan sangat penting dilakukan untuk mengetahui sejauh mana tingkat pencapaian yang telah diperoleh perusahaan sebagaimana tujuan perusahaan dalam menjalankan proses produk...

  16. Preliminary risk analysis of an Hydrogen production plant using the reformed process of methane with vapor coupled to a high temperature nuclear reactor; Analisis preliminar de riesgo de una planta de produccion de hidrogeno utilizando el proceso de reformado de metano con vapor acoplada a un reactor nuclear de alta temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Flores y Flores, A. [Facultad de Ingenieria, UNAM, 04510 Mexico D.F. (Mexico)]. E-mail: alain_fyf@yahoo.com; Nelson E, P.F.; Francois L, J.L. [Facultad de Ingenieria, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, UNAM, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)

    2004-07-01

    It is necessary to identify the different types of dangers, as well as their causes, probabilities and consequences of the same ones, inside plants, industries and any process to classify the risks. This work is focused in particular to a study using the technical HAZOP (Hazard and Operability) for a plant of reformed of methane with vapor coupled to a nuclear reactor of the type HTTR (High Temperature Test Reactor), which is designed to be built in Japan. In particular in this study the interaction is analyzed between the nuclear reactor and the plant of reformed of methane with vapor. After knowing the possible causes of risk one it is built chart of results of HAZOP to have a better vision of the consequences of this faults toward the buildings and constructions, to people and the influence of the fault on each plant; for what there are proposed solutions to mitigate these consequences or to avoid them. The work is divided in three sections: a brief introduction about the technique of HAZOP; some important aspects of the plant of reformed of methane with vapor; and the construction of the chart of results of HAZOP. (Author)

  17. Identifiksi Sebaran Litologi berdasarkan Analisis Data Resistivitas di Gunung Wungkal

    OpenAIRE

    Nurul Dzakiya; MGS. Dwiki Nugraha; Nenden L. Sidik; Trias Galena

    2017-01-01

    Analisis data untuk mengidentifikasi sebaran litologi yang memiliki potensi bahan galian industri di Daerah Gunung Wungkal Yogyakarta dengan menggunakan metode resistivitas dan survei geologi permukaan telah dilakukan. Hasil korelasi kedua data tersebut menunjukkan sebaran litologi merupakan pelapukan intrusi batuan beku yang kemudian menghasilkan material lempung (6,0-10 m), lempung pasiran (11-30 m) dan lapukan batuan diorit (30-55 m) yang berada di kedalaman berbeda. Ketebalan batuan di pe...

  18. Analisis Sikap Konsumen terhadap Produk Fashion Lokal dan Impor

    OpenAIRE

    Setiawan, Evelyn

    2014-01-01

    Abstrak: Analisis Sikap Konsumen Terhadap Produk Fashion Lokal dan Impor. Penelitian ini bertujuan untuk menganalisis sikap konsumen terhadap produk fashion lokal dan impor yang akan berpengaruh terhadap keputusan konsumsi. Sampel yang akan digunakan dalam penelitian ini adalah 1.000 mahasiswa dari 10 perguruan tinggi swasta terbesar di Surabaya. Pengambilan data dilakukan dengan metode kuesioner. Hasil pengujian statistik menunjukkan bahwa sebagian besar mahasiswa di Surabaya merasa bangga d...

  19. Uso de Analisis de Covarianza (ANCOVA en investigacion cientifica.

    Directory of Open Access Journals (Sweden)

    Badii, M.H.

    2008-01-01

    Full Text Available The basics of the ANalisis of COVAriance (ANCOVA are given. The objectives and the application of ANCOVA are laid out. Techniques for the estimation of contrasts and for the control and reduction of the degree of error are discussed. The application of a simple ANCOVA using real data is highlighted. The application of this technique in fixing the auxiliary variable in experimentation is emphasized.

  20. Analisis Pemasaran Ayam Ras Pedaging di Pasar Tradisional Kota Medan

    OpenAIRE

    Fachri, Yusrizal

    2017-01-01

    130306044 YUSRIZAL FACHRI, 2017. “Analisis Pemasaran Ayam Ras Pedaging di Pasar Tradisional Kota Medan”. Dibimbing oleh ARMYN HAKIM DAULAY dan NEVY DIANA HANAFI. Penelitian ini bertujuan untuk mengidentifikasi karakteristik lembaga pemasaran, bentuk saluran, fungsi pemasaran, dan menganalisis nilai tambah di lembaga-lembaga pemasaran ayam ras pedaging di pasar tradisional Kota Medan pada April sampai Mei 2017. Penelitian ini menggunakan data primer yang didapatkan dari observasi dan waw...

  1. Metode Pengumpulan dan Analisis Data : Lang Kah Vital Proses Penelitian

    OpenAIRE

    Suprapto, Agus .

    2005-01-01

    The process of data collection and. analysis is one of chains in scientific method that should be done in a research. This part later on will determine the right method in searching and analyzing a way in solving a problem. The data collected should be the ones which are relevant which the essence of research problems, so that the next interpreted data will eventually be concluded as valid. keywords: Pengumpulan data, analisis data,dan metode ilmiah

  2. Influence of mineralogy and moisture content on plasticity and induced anisotropic damage of a clay-stone: application to nuclear waste disposals

    International Nuclear Information System (INIS)

    Chiarelli, A.S.; Sibai, M.; Karami, M.; Ledesert, B.; Hoteit, N.

    2000-01-01

    The influence of mineralogy and moisture content on mechanical behaviour of a clay-stone rock is studied by the way of uniaxial and triaxial compression tests and microscopic observations. Some parameters characteristic of phenomena like plasticity and induced anisotropic damage are discussed as a function of these two factors. Rock behaviour becomes more brittle when calcite content grows or when clay or moisture content decreases. At the micro-level, plasticity is induced by slip of clay sheets and induced anisotropic damage appears by growth of oriented microcracks at the interface between grains and matrix. (authors)

  3. Analysis of Ling'ao nuclear power station unit 1 exciter No.11 bearing white metal damage and its operating temperature abnormally high

    International Nuclear Information System (INIS)

    Jia Kaili

    2005-01-01

    On the base of analyzing the type of exciter No.11 bearing white metal damage, the root cause and its solution are found. No damage was found on bearing white metal in the later time. On the base of analyzing the structure of the generator end bracket, it is pointed out that when the generator frame is full of pressed gas, the end bracket will deform, that result in the load on No.11 bearing increase, as a result causes the bearing temperature high. A proposal to this problem is presented. (author)

  4. ANALISIS PENGARUH KINERJA LINGKUNGAN TERHADAP KINERJA INDUSTRI KECIL

    Directory of Open Access Journals (Sweden)

    Sukirman -

    2012-03-01

    Full Text Available Tujuan penelitian adalah mengidentifikasi, menganalisis praktik pengelolaan lingkungan pada sentra industri kecil dibandingkan best practices dalam upaya meningkatkan kinerja lingkungan di Kabupaten Pati. Kajian difokuskan pada pengelolaan lingkungan secara efektif dengan melibatkan variabel inisiatif lingkungan, keterlibatan karyawan, dan integrasi dengan supplier. Populasinya adalah seluruh perusahaan Industri Kecil di Kabupaten Pati. Sampel berjumlah 97 perusahaan. Teknik sampling menggunakan kluster sampling, dengan sampel pada sentra industri kecil di Kabupaten Pati.  Analisis menggunakan analisis deskriptif dan analisis komparatif. Hasil penelitian menunjukkan praktik pengelolaan lingkungan pada sentra industri kecil di Kabupaten Pati belum dilaksanakan secara optimal. Sementara itu, variabel integrasi supplier berpengaruh langsung terhadap kinerja perusahaan.The purpose of this study is to identify and to analyze an environmental management practice which is compared to the best practices in order to improve environmental performance in the industrial centers in Pati District. This study focuses on managing the environment effectively by involving environmental initiative variables, employee involvement, and integration of suppliers. Population in this study was all small industrial enterprises in Pati regency which has 97 companies as data samples. Data were collected by using cluster sampling techniques, and samples were taken from small industrial centers in the District of Pati. Data were analyzed by using descriptive and comparative methods. Results of this study showed that environmental management practices in small industrial centers had not been implemented optimally. Meanwhile, supplier integration variables influenced directly toward corporate performance.

  5. Microfinanza: analisi d’impatto di un programma in India

    Directory of Open Access Journals (Sweden)

    Tommaso Rondinella

    2005-03-01

    Full Text Available L’analisi d’impatto dei programmi di microfinanza è uno strumento utile sia per migliorare i servizi offerti sia per garantire ai donatori che il denaro concesso sia utilizzato per programmi efficaci nell’alleviare la povertà. Il presente lavoro è costituito da due parti: la prima è dedicata all’analisi d’impatto, la seconda all’analisi empirica sul campo. L’indagine è stata condotta attraverso l’utilizzo di uno strumento in grado di dare una indicazione chiara dei cambiamenti avvenuti nelle condizioni di vita dei beneficiari e con il pregio di essere applicabile a costi molto ridotti. I risultati ottenuti mostrano in che misura l’accesso al credito cambi le condizioni di vita dei più poveri inducendo consistenti aumenti del reddito familiare, dei risparmi, della diversificazione delle attività produttive e del consumo di cibo. Inoltre si osserva, all’interno dei nuclei familiari, un miglioramento della condizione femminile chiaramente dipendente dalla partecipazione al programma di microcredito

  6. ANALISIS CLUSTER K-MEANS DALAM PENGELOMPOKAN KEMAMPUAN MAHASISWA

    Directory of Open Access Journals (Sweden)

    B. Poerwanto

    2016-12-01

    Full Text Available Abstract. Cluster Analysis, K-Means Algorithm, Student Classification. This study aims to classify students based on learning outcomes for subject the basic of statistics (DDS, which is measured based on attendance, task, midterm (UTS, and final exams (UAS to further used to evaluate learning for subjects that require analysis of quantitative . This study uses k-means cluster analysis to classify the students into three groups based on learning outcomes. After grouped, there are 3 people in the low category, 27 in the medium category and over 70% in the high category.Abstrak. Analisis Cluster K-Means dalam Pengelompokan Kemampuan Mahasiswa. Pene-litian ini bertujuan untuk mengelompokkan mahasiswa berdasarkan hasil belajar mata kuliah dasar-dasar statistika (DDS yang diukur berdasarkan variabel nilai kehadiran, tugas, ujian tengah semester (UTS, dan ujian akhir semester (UAS untuk selanjutnya digunakan untuk mengevaluasi pembelajaran untuk mata kuliah yang membutuhkan kemampuan analisis kuantititatif yang baik. Penelitian ini menggunakan analisis cluster k-means dalam mengelompokkan mahasiswa ke dalam tiga kelompok berdasarkan hasil belajarnya. Seteleh dikelompokkan, terdapat 3 orang yang masuk pada kategori rendah, 27 orang pada kategori sedang dan lebih dari 70% pada kategori tinggi.Kata Kunci: Cluster Analysis, K-Means Algoritma, Klasifikasi Mahasiswa, Universitas Cokroaminoto Palopo

  7. Estetika Tari Minang dalam Kesenian Randai Analisis Tekstual-Kontekstual

    Directory of Open Access Journals (Sweden)

    Sri Rustiyanti

    2013-03-01

    Full Text Available ABSTRACT   This paper reveals textual and contextual Randai, among other things, an analysis of Gerak Ga­ lombang Randai, an analysis of the character of Anak Randai, and at the end of the study series, to reveal the values contained in Randai as a cultural reality, which in principle is an inseparable part of the existence of Minangkabau community as the cultural support. The variety of motion used in Gerak Galombang Randai is not only a decoration of the motion beauty (tangible, but it also can be translated, as well as a symbol or emblem that has educational meanings (intangible, and can be an example of the daily life of the indigenous Minangkabau society.   Keywords: Minang Dance aesthetic, Randai, textual­contextual analysis     ABSTRAK   Tulisan ini mengungkap teksual dan kontekstual Randai, di antaranya, analisis terhadap gerak galombang Randai, analisis karakter tokoh anak Randai, dan sebagai akhir dari rang- kaian penelitian ini, mengungkapkan nilai-nilai yang terdapat pada Randai sebagai realitas budaya, yang pada prinsipnya merupakan bagian yang tak dapat dipisahkan dari eksistensi masyarakat Minangkabau sebagai penyangga kebudayaan. Ragam gerak yang digunakan dalam gerak galombang Randai itu kiranya tidak hanya sekedar hiasan keindahan gerak be- laka (tangibel, namun ia dapat diterjemahkan, sekaligus merupakan simbol atau lambang yang bermakna  mendidik (intangibel, dan dapat   menjadi teladan dalam kehidupan se- hari-hari dalam masyarakat adat di Minangkabau.   Kata Kunci: estetika Tari Minang, Randai, analisis tekstual-kontekstual

  8. Analisis Termal High Pressure Feedwater Heater di PLTU PT. XYZ

    Directory of Open Access Journals (Sweden)

    Maria Ulfa Damayanti

    2017-01-01

    Full Text Available Abstrak- PT. XYZ mengoperasikan tiga unit Pembangkit Listrik Tenaga Uap (PLTU unit 3, 7 dan 8 berkapasitas 2.030 MegaWatt. Pada PLTU Paiton unit 7 dan 8 terdapat delapan buah feedwater heater yaitu empat buah Low Pressure Water Heater (LPWH, tiga buah High Pressure Water Heater (HPWH, dan sebuah dearator. Pada PLTU Paiton unit 7 dan 8 terdapat kerusakan pada HPWH 6 yang menyebabkan penurunan efisiensi dari siklus secara keseluruhan. Penurunan efisiensi dapat terjadi karena temperatur feedwater sebelum masuk ke boiler terlalu rendah, sehingga kalor yang dibutuhkan oleh boiler untuk memanaskan feedwater meningkat. Oleh karena itu konsumsi batubara akan meningkat dan menyebabkan terjadi kenaikan biaya operasional harian dalam sistem pembangkit. Dari data Divisi Produksi PT. XYZ Unit 7 dan 8 diperoleh spesifikasi HPWH 6, 7, dan 8 dan propertis fluida dalam HPWH 6, 7, dan 8. Data tersebut digunakan sebagai dasar analisis termal yang meliputi performa masing-masing HPH. Tahap selanjutnya dalam analisis termal adalah memvariasikan beban 25%, 50%, 75%, 100%, dan 105%. Tahap terakhir analisis adalah menghitung performa dengan variasi sumbatan (plug 5%, 10%, 15%, dan 20% sesuai dengan variasi beban. Hasil yang didapatkan dari penelitian tugas akhir ini adalah nilai effectiveness tertinggi tercapai pada pembebanan 100% serta menghasilkan pressure drop tertinggi pada pembebanan 105%, nilai effectiveness terbesar serta nilai pressure drop terkecil terjadi pada zona Condensing, serta sumbatan (plugging pada HPH akan menyebabkan penurunan nilai effectiveness dan kenaikan pressure drop sisi tube.

  9. Radiation damage

    CERN Document Server

    Heijne, Erik H M; CERN. Geneva

    1998-01-01

    a) Radiation damage in organic materials. This series of lectures will give an overview of radiation effects on materials and components frequently used in accelerator engineering and experiments. Basic degradation phenomena will be presented for organic materials with comprehensive damage threshold doses for commonly used rubbers, thermoplastics, thermosets and composite materials. Some indications will be given for glass, scintillators and optical fibres. b) Radiation effects in semiconductor materials and devices. The major part of the time will be devoted to treat radiation effects in semiconductor sensors and the associated electronics, in particular displacement damage, interface and single event phenomena. Evaluation methods and practical aspects will be shown. Strategies will be developed for the survival of the materials under the expected environmental conditions of the LHC machine and detectors. I will describe profound revolution in our understanding of black holes and their relation to quantum me...

  10. Nuclear fear revisited

    Science.gov (United States)

    Crease, Robert P.

    2010-10-01

    In 1988 the science historian Spencer Weart published a groundbreaking book called Nuclear Fear: A History of Images, which examined visions of radiation damage and nuclear disaster in newspapers, television, film, literature, advertisements and popular culture.

  11. Nuclear power. BGH ruling of 16.1.1997 (Az: III ZR 117/95) relating to the action for damages in the matter of the shut-down Muehlheim-Kaerl-Kaerlich Reactor

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    The German Federal High Court (BGH) non-appealably rejected part of the claims for damages of the owner/operator of the Muehlheim-Kaerlich nuclear power station asserted in an action against the Federal State of Rhineland-Palatinate and remanded the case to the lower court for clarification of the remaining claims. The plant operator claimed compensation for damage incurred in the wake of the annulment of the first partial permit issued for the nuclear power plant in 1975 and declared to be void for reasons of non-compliance with the licensing provisions of section 7, sub-section 2 AtG (Atomic Energy Act), and breach of official duty of civil servants of the licensing authority of Rhineland-Palatinate. Due to this decision of the Federal Administrative Court, the plant was shut down in 1988. The claims asserted by the operator relate among other items to compensation for construction, operation and shut-down operation costs. (orig./CB) [de

  12. Radiation Damage and Dimensional Changes

    International Nuclear Information System (INIS)

    El-Barbary, A.A.; Lebda, H.I.; Kamel, M.A.

    2009-01-01

    The dimensional changes have been modeled in order to be accommodated in the reactor design. This study has major implications for the interpretation of damage in carbon based nuclear fission and fusion plant materials. Radiation damage of graphite leads to self-interstitials and vacancies defects. The aggregation of these defects causes dimensional changes. Vacancies aggregate into lines and disks which heal and contract the basal planes. Interstitials aggregate into interlayer disks which expand the dimension

  13. Apportioning liability for transborder damage

    International Nuclear Information System (INIS)

    Krause-Ablass, W.D.

    1988-01-01

    The author analyses the different legal systems applicable to transfrontier nuclear damage. Using examples, he describes the mechanisms enabling a victim of such damage to identify the competent court and the relevant law, according to whether the provisions of the Paris or the Vienna Convention come into play or whether the rules of private international law, incorporated in the various national laws are applicable (NEA) [fr

  14. Statistical analysis in the design of nuclear fuel cells and training of a neural network to predict safety parameters for reactors BWR; Analisis estadistico en el diseno de celdas de combustible nuclear y entrenamiento de una red neuronal para predecir parametros de seguridad para reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Jauregui Ch, V.

    2013-07-01

    In this work the obtained results for a statistical analysis are shown, with the purpose of studying the performance of the fuel lattice, taking into account the frequency of the pins that were used. For this objective, different statistical distributions were used; one approximately to normal, another type X{sup 2} but in an inverse form and a random distribution. Also, the prediction of some parameters of the nuclear reactor in a fuel reload was made through a neuronal network, which was trained. The statistical analysis was made using the parameters of the fuel lattice, which was generated through three heuristic techniques: Ant Colony Optimization System, Neuronal Networks and a hybrid among Scatter Search and Path Re linking. The behavior of the local power peak factor was revised in the fuel lattice with the use of different frequencies of enrichment uranium pines, using the three techniques mentioned before, in the same way the infinite multiplication factor of neutrons was analyzed (k..), to determine within what range this factor in the reactor is. Taking into account all the information, which was obtained through the statistical analysis, a neuronal network was trained; that will help to predict the behavior of some parameters of the nuclear reactor, considering a fixed fuel reload with their respective control rods pattern. In the same way, the quality of the training was evaluated using different fuel lattices. The neuronal network learned to predict the next parameters: Shutdown Margin (SDM), the pin burn peaks for two different fuel batches, Thermal Limits and the Effective Neutron Multiplication Factor (k{sup eff}). The results show that the fuel lattices in which the frequency, which the inverted form of the X{sup 2} distribution, was used revealed the best values of local power peak factor. Additionally it is shown that the performance of a fuel lattice could be enhanced controlling the frequency of the uranium enrichment rods and the variety of

  15. Tort Damages

    NARCIS (Netherlands)

    L.T. Visscher (Louis)

    2008-01-01

    textabstractAbstract: In this Chapter, I provide an overview of Law and Economics literature regarding tort damages. Where necessary, attention is also spent to rules of tort liability. Both types of rules provide behavioral incentives to both injurers and victims, with respect to their level of

  16. Nuclear Law: A Key Against Nuclear Terrorism

    International Nuclear Information System (INIS)

    Cardozo, P.

    2004-01-01

    The role of the legal instruments in the war against nuclear terrorism. Control of radioactive sources. Elements of Nuclear Law: Definition: it is the body of special legislation that regulates the pacific uses of nuclear energy and the conduct of the persons engaged in activities related to fissionable materials and ionizing radiation . Objective: to provide a legal framework in order to protect individuals , property and the environment against the harmful effects of the use of nuclear energy and ionising radiation. Principles of nuclear energy legislation: safety principle, exclusively operator responsibility, authorization, independence of the regulatory body, inspections and enforcement, nuclear damage compensation, international cooperation. National regulatory infrastructure. Establishment of special law in Emergency Preparedness for nuclear or radiological disaster. IAEA Conventions. Transportation of nuclear material. IAEA regulations on radioactive material. Compensation for nuclear damage. Nuclear safety, security and terrorism. International and domestic instruments. Anti terrorism acts. International agreements on Safety Cooperation. (Author)

  17. There is possible damages on the nuclear power plants (NPP) of so-frontiers states and operations of the forces of the civil defense (cd) in these situations

    International Nuclear Information System (INIS)

    Ocaqov, H.O.

    2002-01-01

    Full text: According to our forecasts if any type of accident occurs at the nuclear power plant located on the territory of Armenian Republic the radioactive pollution will spread over the territory of Azerbaijan. The injection of radioactive substances and formation of a polluted zone on the significant area including some parts of the territory of Nakhichevan Republic, Nagorny Karabakh, Kelbajar and Kedabek regions are possible. In extraordinary situations occurred due to radiation accidents or under detection of a radioactive pollution the restriction of subsequent irradiation of the population is accomplished by protective measures. These measures are connected to the breakdown of normal live ability of the population, economic and social functioning of the territory i.e. it is an interference causing not only economic and ecological damage but also having adverse influence on the population. A decrease of risk to a possible low level (optimization) is carried out due to the following two circumstances: A time it of risk of a potential irradiation from all possible sources of radiation is regulated and for each source the boundary of risk is established; Under a decrease of potential radiation risk there is the minimum level of risk, below which a risk is considered as negligible and further decrease of risk is inexpedient. Under the accident control and under a realization of urgent reestablishment works it is recommended not to admit an equivalent dose (ED) of radiation more than approximately 500 mSv except for actions on rescue of life or on prevention of further development of the accident and the irradiation of large number of people. Assumed increase of radiation is admitted only for men older than 30 years only on voluntary written approval and preliminary informing them about possible doses of radiation at accident liquidation and about a risk for their health. The persons attracted for realization of emergency and saving work, are considered on the

  18. DNA damage in neurodegenerative diseases

    Energy Technology Data Exchange (ETDEWEB)

    Coppedè, Fabio, E-mail: fabio.coppede@med.unipi.it; Migliore, Lucia, E-mail: lucia.migliore@med.unipi.it

    2015-06-15

    Highlights: • Oxidative DNA damage is one of the earliest detectable events in the neurodegenerative process. • The mitochondrial DNA is more vulnerable to oxidative attack than the nuclear DNA. • Cytogenetic damage has been largely documented in Alzheimer's disease patients. • The question of whether DNA damage is cause or consequence of neurodegeneration is still open. • Increasing evidence links DNA damage and repair with epigenetic phenomena. - Abstract: Following the observation of increased oxidative DNA damage in nuclear and mitochondrial DNA extracted from post-mortem brain regions of patients affected by neurodegenerative diseases, the last years of the previous century and the first decade of the present one have been largely dedicated to the search of markers of DNA damage in neuronal samples and peripheral tissues of patients in early, intermediate or late stages of neurodegeneration. Those studies allowed to demonstrate that oxidative DNA damage is one of the earliest detectable events in neurodegeneration, but also revealed cytogenetic damage in neurodegenerative conditions, such as for example a tendency towards chromosome 21 malsegregation in Alzheimer's disease. As it happens for many neurodegenerative risk factors the question of whether DNA damage is cause or consequence of the neurodegenerative process is still open, and probably both is true. The research interest in markers of oxidative stress was shifted, in recent years, towards the search of epigenetic biomarkers of neurodegenerative disorders, following the accumulating evidence of a substantial contribution of epigenetic mechanisms to learning, memory processes, behavioural disorders and neurodegeneration. Increasing evidence is however linking DNA damage and repair with epigenetic phenomena, thereby opening the way to a very attractive and timely research topic in neurodegenerative diseases. We will address those issues in the context of Alzheimer's disease

  19. DNA damage in neurodegenerative diseases

    International Nuclear Information System (INIS)

    Coppedè, Fabio; Migliore, Lucia

    2015-01-01

    Highlights: • Oxidative DNA damage is one of the earliest detectable events in the neurodegenerative process. • The mitochondrial DNA is more vulnerable to oxidative attack than the nuclear DNA. • Cytogenetic damage has been largely documented in Alzheimer's disease patients. • The question of whether DNA damage is cause or consequence of neurodegeneration is still open. • Increasing evidence links DNA damage and repair with epigenetic phenomena. - Abstract: Following the observation of increased oxidative DNA damage in nuclear and mitochondrial DNA extracted from post-mortem brain regions of patients affected by neurodegenerative diseases, the last years of the previous century and the first decade of the present one have been largely dedicated to the search of markers of DNA damage in neuronal samples and peripheral tissues of patients in early, intermediate or late stages of neurodegeneration. Those studies allowed to demonstrate that oxidative DNA damage is one of the earliest detectable events in neurodegeneration, but also revealed cytogenetic damage in neurodegenerative conditions, such as for example a tendency towards chromosome 21 malsegregation in Alzheimer's disease. As it happens for many neurodegenerative risk factors the question of whether DNA damage is cause or consequence of the neurodegenerative process is still open, and probably both is true. The research interest in markers of oxidative stress was shifted, in recent years, towards the search of epigenetic biomarkers of neurodegenerative disorders, following the accumulating evidence of a substantial contribution of epigenetic mechanisms to learning, memory processes, behavioural disorders and neurodegeneration. Increasing evidence is however linking DNA damage and repair with epigenetic phenomena, thereby opening the way to a very attractive and timely research topic in neurodegenerative diseases. We will address those issues in the context of Alzheimer's disease

  20. ANALISIS PENERAPAN 8 STANDAR NASIONAL PENDIDIKAN PADA SMP NEGERI 2 DOLOPO KABUPATEN MADIUN

    Directory of Open Access Journals (Sweden)

    Luki Eko Cahyono

    2015-10-01

    Penelitian ini menggunakan desain penelitian Deskriptif Kualitatif. Jenis penelitian adalah studi kasus. Data yang digunakan adalah data Primer. Teknik pengumpulan data yang digunakan adalah wawancara dan dokumentasi. Teknik keabsahan data adalah Triangulasi Sumber dan teknik analisis data yang digunakan adalah pendekatan Strengths, Weakness, Opportunities, dan Threats (Analisis SWOT. Kesimpulan penelitian ini adalah (1 Hasil analisis Strenght (Kekuatan adalah sekolah sudah merencanakan, melaksanakan dan mengevaluasi sebagian besar indikator dalam pemenuhan Standar Nasional Pendidikan sehingga meningkatkan mutu pendidikan sekolah. (2 Hasil analisis Weakness (kelemahan adalah keterbatasan anggaran dana dan sumber daya manusia baik peserta didik, pendidik, maupun tenaga kependidikan dalam pemenuhan seluruh unsur Standar Nasional Pendidikan. (3 Hasil analisis Opportunities (peluang adalah Pemberian workshop dan pelatihan kepada pendidik dan tenaga kependidikan meningkatkan kualitas pendidikan sekolah, dan perencanaan, pelaksanaan pembiayaan serta evaluasi penganggaran yang baik memberikan dampak positif terhadap semua unsur operasional sekolah maupun sarana prasarana sekolah. (4 Hasil analisis Threats (Tantangan adalah perencanaan, sosialisasi, pelaksanaan dan evaluasi serta tindak lanjut yang tidak dijalankan dengan manajemen yang baik dalam upaya pemenuhan Standar Nasional Pendidikan akan menghambat peningkatan kualitas pendidikan sekolah. (5 Hasil penerapan Standar Nasional Pendidikan pada SMP Negeri 2 Dolopo menggunakan analisis SWOT menunjukkan bahwa Kekuatan lebih besar daripada Kelemahan dan Peluang lebih besar dari Ancaman, yang berarti Standar Nasional Pendidikan telah terpenuhi dan menghasilkan Akreditasi Sekolah nilai A.

  1. Dynamics of radiation damage and repair processes in coniferous stands in a 10-km region of the Chernobyl nuclear power station

    International Nuclear Information System (INIS)

    Kozubov, G.M.; Taskaev, A.I.

    1995-01-01

    Properties of morphogenesis, growth dynamics, anatomy and ultrastructure of wood and needle, reproductive processes in coniferous plants were studied under different level of radiation effect in the 10-km zone in 1986-1992. It was established that the full drying of pine forests began under absorbed dose 80-100 Gy/year. Threshold doses, after which repair processes were possible, reached to 10-12 Gy/year for Picea abies and 50 Gy/year for Pinus sylvestris. Three maine stages are revealed in dynamics of radiation damage and repair processes in studied conifers and their morphological and functional characteristic is presented. 14 refs., 3 figs., 2 tabs

  2. Induction of DNA damage in γ-irradiated nuclei stripped of nuclear protein classes: differential modulation of double-strand break and DNA-protein crosslink formation

    International Nuclear Information System (INIS)

    Xue, L.-Y.; Friedman, L.R.; Oleinick, N.L.; Chiu, S.-M.

    1994-01-01

    The influence of chromatin proteins on the induction of DNA double-strand breaks (dsb) and DNA-protein crosslinks (dpc) by γ-radiation was investigated. Low molecular weight non-histone proteins and classes of histones were extracted with increasing concentrations of NaC1, whereas nuclear matrix proteins were not extractable even by 2.0 M NACl. The yield of dsb increased with progressive removal of proteins from chromatin. The data support our previous conclusion that nuclear matrix protein rather than the majority of the histones are the predominant substrates for dpc production, although the involvement of a subset of tightly bound histones (H3 and H4) has not been excluded. This finding demonstrates that chromatin proteins can differentially modify the yield of two types of radiation-induced DNA lesions. (author)

  3. Radiation damage of structural materials

    CERN Document Server

    Koutsky, Jaroslav

    1994-01-01

    Maintaining the integrity of nuclear power plants is critical in the prevention or control of severe accidents. This monograph deals with both basic groups of structural materials used in the design of light-water nuclear reactors, making the primary safety barriers of NPPs. Emphasis is placed on materials used in VVER-type nuclear reactors: Cr-Mo-V and Cr-Ni-Mo-V steel for RPV and Zr-Nb alloys for fuel element cladding. The book is divided into 7 main chapters, with the exception of the opening one and the chapter providing a phenomenological background for the subject of radiation damage. Ch

  4. Analisis Penerimaan PAD Pada Dinas Perikanan dan Peternakan Kabupaten Tebo

    Directory of Open Access Journals (Sweden)

    Eko Purnarianto

    2016-06-01

    Full Text Available Abstract. This study aims to analyze potential, efficiency, effectivity and contribution of PAD admission at Department of Fishery and Animal Husbandry in Tebo Regencyincluding the strategy establishment to increase its revenue.The analysis used is a potential formula, efficiency ratio, effectivity ratio, contributions ratio and SWOT analysis.The results shows that the potential revenue of retribution slaughterhouse (RPH, the potential sales of livestock, and potential sales fishery product are beyond the current target. The efficiency level of retribution slaughterhouse (RPH and sales of fishery product is poor, but the sales of livestock is very efficient. Effectivity level of livestock and fishery product sales are low, whileretribution slaughterhouses(RPH is not effective regarded to its potential  but in the contrary for its target. Contribution of PAD admission of Fishery and Animal Husbandry Department is very low regarded Tebo Regency PAD. The result of SWOT analysis of retribution slaughter house (RPH admission using WO (Weakness-Opportunity strategy, livestock sales using SO (Strength-Oppurtunity strategy, and fishery product sales using ST (strength-threat strategy. Keywords: Retribution SlaughterHouse (RPH, Sales of Fishery, Livestock Sales, SWOT Analysis   Abstrak. Penelitian ini bertujuan untuk menganalisis potensi, efisiensi, efektivitas dan kontribusi penerimaan PAD pada Dinas Perikanan dan Peternakan Kabupaten Teboserta menetapkan strategi untuk peningkatan penerimaan PAD. Analisis yang digunakan adalah rumus potensi, rasio efisiensi, rasio efektivitas, rasio kontribusi dan analisis SWOT.Hasil penelitian menunjukkan bahwa potensi penerimaan retribusi rumah potong hewan (RPH, potensi penjualan hasil peternakan, potensi  penjualan hasil perikanan lebih besar dari target yang telah ditetapkan. Tingkat efisiensi retribusi RPH dan penjualan hasil perikanan tidak efisien, penjualan hasil peternakan sangat efisien. Tingkat

  5. Identifiksi Sebaran Litologi berdasarkan Analisis Data Resistivitas di Gunung Wungkal

    Directory of Open Access Journals (Sweden)

    Nurul Dzakiya

    2017-05-01

    Full Text Available Analisis data untuk mengidentifikasi sebaran litologi yang memiliki potensi bahan galian industri di Daerah Gunung Wungkal Yogyakarta dengan menggunakan metode resistivitas dan survei geologi permukaan telah dilakukan. Hasil korelasi kedua data tersebut menunjukkan sebaran litologi merupakan pelapukan intrusi batuan beku yang kemudian menghasilkan material lempung (6,0-10 m, lempung pasiran (11-30 m dan lapukan batuan diorit (30-55 m yang berada di kedalaman berbeda. Ketebalan batuan di permukaan sekitar 225-231 meter berdasarkan penampang peta geologi dengan arah sebaran dari Barat Laut hingga Tenggara. Proses pelapukan dan alterasi di daerah ini intensif (alterasi argilik dengan jenis morfologi perbukitan intrusi terdenudasi dan dataran Alluvial.

  6. ANALISIS KEAMANAN DATA PADA BLOCK CIPHER ALGORITMA KRIPTOGRAFI RSA

    Directory of Open Access Journals (Sweden)

    Fadhillah Azmi

    2017-01-01

    Full Text Available Komunikasi adalah proses dasar dari pertukaran informasi. Efektifitas komunikasikomputer secara umum adalah melalui internet atau beberapa saluran komunikasi lainnya.Tujuan utama tulisan ini adalah berdasarkan pada analisis hasil yang diberikan Weinermengatakan bahwa jika private key d digunakan dalam algoritma kriptografi RSA kurang darin292, maka sistem tersebut kurang aman. Di sini penulis menganalisa pada hasil yang diberikanoleh Weiner dan mencoba untuk meningkatkan range dari private key d sampai n0.5. Karena nadalah perkalian p dan q, yang mana bilangan relative prima. Sehingga mempengaruhi kinerjaenkripsi algoritma yang lebih aman.

  7. Analisis Derau dalam Perancangan Rangkaian Terintegrasi Op-Amp

    Directory of Open Access Journals (Sweden)

    Siti Sendari

    2009-02-01

    Full Text Available Perancangan IC Op-Amp, memerlukan spesifikasi-spesifikasi yang meliputi parameter proses dan parameter perancangan. Dalam menentukan parameter perancangan, derau merupakan suatu hal yang tidak bisa ditinggalkan, karena derau dapat menentukan keandalan perancangan. Untuk menganalisis derau pada IC Op-Amp langkah pertama yang harus diketahui adalah sumber-sumber derau, setelah itu dilakukan analisis derau baik secara teoritis maupun secara simulasi untuk mengetahui derau yang mungkin terjadi dalam perancangan IC, apakah sudah sesuai dengan spesifikasi yang ditentukan atau tidak. Untuk simulasi derau dapat dilakukan dengan program Spice.

  8. Evaluation methods for corrosion damage of components in cooling systems of nuclear power plants by coupling analysis of corrosion and flow dynamics (1). Major targets and development strategies of the evaluation methods

    International Nuclear Information System (INIS)

    Naitoh, Masanori; Uchida, Shunsuke; Koshizuka, Seiichi; Ninokata, Hisashi; Hiranuma, Naoki; Dosaki, Koji; Nishida, Koji; Akiyama, Minoru; Saitoh, Hiroaki

    2008-01-01

    Problems in major components and structural materials in nuclear power plants have often been caused by flow induced vibration and corrosion and their overlapping effects. In order to establish safe and reliable plant operation, future problems for structural materials should be predicted based on combined analyses of flow dynamics and corrosion and they should be mitigated before becoming serious issues for plant operation. Three approaches have been prepared for predicting future problems in structural materials: 1. Computer program packages for predicting future corrosion fatigue on structural materials, 2. Computer program packages for predicting future corrosion damage on structural materials, and 3. Computer program packages for predicting wall thinning caused by flow accelerated corrosion. General features of evaluation methods and their computer packages, technical innovations required for their development, and application plans for the developed approaches for plant operation are introduced in this paper. (author)

  9. Romanian Nuclear Liability Legislation

    International Nuclear Information System (INIS)

    Banu, R.

    2006-01-01

    The regime of civil liability for nuclear damages in the Romanian legislation is defined especially by the Law no. 703/2001 on civil liability for nuclear damage, as well as the Government Decision no. 894/2003 for the approval of the Norms for the enforcement of Law no. 703/2001. These two documents constitute the legal framework that regulates the third party civil liability for nuclear damages. The paper is proposing to present the main elements of the relatively recent legal framework, namely: the principles content in the international acts on civil liability for nuclear damages, the subject to whom such law applies, the regime of civil liability for nuclear damages in Romania and provisions regarding the terrorist acts.(author)

  10. Nuclear risk

    International Nuclear Information System (INIS)

    Mulkers, G.

    1988-01-01

    This file includes data on risks insured by the nuclear insurance pool in Belgium and on the Chernobyl accident covering injury, economic damage and compensation for the latter. Also included are the texts of the IAEA Conventions on Early Notification and on Assistance in Case of a Nuclear Accident as well as that of a Convention on long-distance transfrontier atmospheric pollution signed in Geneva [fr

  11. American nuclear insurers

    International Nuclear Information System (INIS)

    Oliveira, R.A.

    1988-01-01

    Nuclear liability insurance covers liability for damages directly caused by the nuclear energy hazard. This coverage includes offsite bodily injury and property damage sustained by members of the general public, and bodily injury to onsite third party personnel. Recent nuclear liability claims allege bodily injury and property damage resulting from releases or radioactive materials to the environmental and occupational radiation worker exposures. Routine reactor operations involving radioactive waste have the potential to result in such claims. The nuclear insurance Pools believe that one way such claims can be minimized is through the implementation of an effective radioactive waste management program

  12. Analysis of core damage frequency: Nuclear power plant Dukovany, VVER/440 V-213 Unit 1, internal events. Volume 1: Main report

    International Nuclear Information System (INIS)

    Pugila, W.J.

    1994-01-01

    This report presents the final results from the Level 1 probabilistic safety assessment (PSA) for the Dukovany VVER/440 V-213 nuclear power plant, Unit 1. Section 1.1 describes the objectives of this study. Section 1.2 discusses the approach that was used for completing the Dukovany PSA. Section 1.3 summarizes the results of the PSA. Section 1.4 provides a comparison of the results of the Dukovany PSA with the results of other PSAs for different types of reactors worldwide. Section 1.5 summarizes the conclusions of the Dukovany PSA

  13. Klasifikasi Kecamatan Berdasarkan Nilai Akhir SMA/MA di Kabupaten Aceh Selatan Menggunakan Analisis Diskriminan

    Directory of Open Access Journals (Sweden)

    Fitriana A.R.

    2015-11-01

    Full Text Available Analisis diskriminan merupakan bagian dari analisis peubah ganda. Analisis diskriminan digunakan untuk memodelkan variabel tak bebas yang bersifat kualitatif dengan variabel bebas yang bersifat kuantitatif. Pada penelitian ini, analisis diskriminan lebih dari dua kelompok diterapkan pada data nilai akhir SMA/MA di Kabupaten Aceh Selatan yang bertujuan untuk mendapatkan model untuk pengklasifikasian kecamatan. Pengklasifikasian ini bertujuan untuk melihat perbedaan kualitas siswa SMA/MA yang berada di masing-masing kecamatan Kabupaten Aceh Selatan berdasarkan data nilai akhir. Variabel tak bebas yang digunakan berupa klasifikasi kecamatan berdasarkan rata-rata jumlah nilai akhir SMA/MA yang berada di masing-masing kecamatan yang dibentuk dengan K-Means Cluster. Sedangkan variabel bebas yang digunakan adalah data rata-rata nilai akhir SMA/MA untuk setiap mata pelajaran yang diujiankan pada masing-masing jurusan setiap kecamatan. Model yang didapatkan adalah dua model diskriminan untuk jurusan IPA dan IPS.

  14. La financial education nella regione Puglia: analisi e prospettive di intervento

    OpenAIRE

    A. Garzoni; V. Nastasi

    2010-01-01

    Analisi del contesto e delle principali tematiche di financial education affrontate a livello internazionale e nazionale, valutazione delle opportunità e degli aspetti critici, il progetto pilota nella regione Puglia e le nuove idee di progetto da realizzare

  15. In honour of N. Yngve Öhrn: surveying proton cancer therapy reactions with Öhrn's electron nuclear dynamics method. Aqueous clusters radiolysis and DNA-base damage by proton collisions

    Science.gov (United States)

    Mclaurin, Patrick M.; Privett, Austin J.; Stopera, Christopher; Grimes, Thomas V.; Perera, Ajith; Morales, Jorge A.

    2015-02-01

    Proton cancer therapy (PCT) utilises high-energy H+ projectiles to cure cancer. PCT healing arises from its DNA damage in cancerous cells, which is mostly inflicted by the products from PCT water radiolysis reactions. While clinically established, a complete microscopic understanding of PCT remains elusive. To help in the microscopic elucidation of PCT, Professor Öhrn's simplest-level electron nuclear dynamics (SLEND) method is herein applied to H+ + (H2O)3-4 and H+ + DNA-bases at ELab = 1.0 keV. These are two types of computationally feasible prototypes to study water radiolysis reactions and H+-induced DNA damage, respectively. SLEND is a time-dependent, variational, non-adiabatic and direct-dynamics method that adopts a nuclear classical-mechanics description and an electronic single-determinantal wavefunction. Additionally, our SLEND + effective-core-potential method is herein employed to simulate some computationally demanding PCT reactions. Due to these attributes, SLEND proves appropriate for the simulation of various types of PCT reactions accurately and feasibly. H+ + (H2O)3-4 simulations reveal two main processes: H+ projectile scattering and the simultaneous formation of H and OH fragments; the latter process is quantified through total integrals cross sections. H+ + DNA-base simulations reveal atoms and groups displacements, ring openings and base-to-proton electron transfers as predominant damage processes. The authors warmly dedicate this SLEND investigation in honour of Professor N. Yngve Öhrn on the occasion of his 80th birthday celebration during the 54th Sanibel Symposium in St. Simons' Island, Georgia, on February 16-21, 2014. Associate Professor Jorge A. Morales was a former chemistry PhD student under the mentorship of Professor Öhrn and Dr Ajith Perera took various quantum chemistry courses taught by Professor Öhrn during his chemistry PhD studies. Both Jorge and Ajith look back to those great times of their scientific formation under

  16. ANALISIS FINANSIAL DAN KELEMBAGAAN RANTAI NILAI MEBEL MAHONI JEPARA

    Directory of Open Access Journals (Sweden)

    Nunung Parlinah

    2011-12-01

    Full Text Available Industri mebel umumnya termasuk dalam industri kecil dan menengah. Selain berperan dalam penerimaan devisa, bisnis di bidang mebel ini juga menciptakan lapangan kerja bagi masyarakat terutama di Kabupaten Jepara. Adanya hubungan (pemberi kepercayaan - (penerima kepercayaan yang terjadi antar aktor atau pelaku di dalam rantai berpengaruh terhadap besarnya distribusi nilai tambah yang diperoleh oleh masingmasing pelaku di sepanjang rantai nilai Tujuan dari penelitian ini adalah mengidentifikasi kelembagaan (aturan yang terjadi antar pelaku di sepanjang rantai nilai mebel mahoni Jepara dan menentukan skenario kebijakan yang dapat mendukung bagi kelestarian industri mebel Jepara. Data yang digunakan meliputi data primer dan data sekunder. Analisis data meliputi identifikasi aktor dan kelembagaan (aturan yang terjadi antar pelaku serta analisis manfaat biaya yang terdiri dari NVP, BCR dan IRR. Hasil penelitian menunjukkan bahwa (1 para pengrajin ( memproduksi mebelnya lebih didasarkan pada pesanan pembeli ( . agent principal Asymetic information yang terjadi antara pedagang kayu dan petani juga telah mengakibatkan posisi petani sebagai (2 Nilai NPV, BCRdan IRR untuk tiap pelaku berbeda-beda tetapi nilai-nilai tersebut mengindikasikan bahwa pola kemitraan yang terjadi antar pelaku dalam rantai nilai mebel mahoni saat ini sudah efektif. Skenario kebijakan yang dapat diterapkan adalah kebijakan yang bersifat insentif bagi petani hutan rakyat, peningkatan kemampuan pengrajin di bidang pemasaran; dan membangun aksi kolektif diantara pengrajin. price taker;

  17. Analisis Rugi Daya Pada Penyulang Bangli Dengan Beroperasinya PLTS Kayubihi

    Directory of Open Access Journals (Sweden)

    I GN Dion Adiputra

    2015-06-01

    Full Text Available Analisis rugi daya pada Penyulang Bangli dilakukan untuk mengetahui perbanding an rugi daya pada jaringan distribusi setelah penempatan pembangkit tersebar jenis PLTS berkapasitas 1 MWp. Lokasi penempatan PLTS ditentukan berdasarkan analisis sensitivitas bus. Nilai sensitivitas bus(?didapat dengan cara membandingkan nilai rugi daya pada sistem dengan total beban yang terhubung pada bus. Penelitian ini menggunakan simulasi aliran daya dengan metode aliran daya Newton-Raphson. Hasil penelitian menunjukkan bus TK 0041 memiliki sensitivitas terbesar dengan nilai ?= 0,178. Dari hasil simulasi aliran daya, penempatan PLTS 1MWp pada lokasi alternatif 1 menghasilkan rugi daya minimum pada Penyulang Bangli yaitu 103,1 kW atau 3,3% dari total suplai daya 3071 kW. Pemasangan PLTS dapat menurunkan rugi daya pada Penyulang Bangli sebesar 57 kW dari total rugi daya pada kondisi tanpa PLTS yaitu 160,1 kW. Bila dibandingkan dengan kondisi eksisting, penem patan PLTS pada lokasi alternatif 1 memiliki selisih rugi daya 7,3 kW lebih kecil dari total rugi daya yang dihasilkan kondisi eksisting sebesar 110,4kW.

  18. Pembuatan Dan Analisis Exciter Generator Rf Untuk Siklotron Proton Decy-13

    OpenAIRE

    Prajitno, Prajitno

    2011-01-01

    PEMBUATAN DAN ANALISIS EXCITER GENERATOR RF UNTUK SIKLOTRON PROTON DECY-13.Telah dilakukan analisis dan pembuatan exciter generator RF untuk siklotron proton 13MeV. Generator RFakan digunakan sebagai sumber tegangan pemercepat bolak-Balik siklotron DECY-13 rancangan PTAPBBATAN.Berdasarkan dokumen rancangan dasar yang telah dibuat siklotron Decy-13 akan menggunakanmedan magnet 1,275 Tesla, sehingga frekuensi generator RF bila menggunakan harmonik keempat adalah77,667 MHz. Salah satu teknik pem...

  19. ANALISIS HARGA POKOK PRODUKSI DAN PENERAPAN TARGET COSTING PADA UD WAJUKU MAKASSAR

    OpenAIRE

    -, CHAIDIR HAFID

    2017-01-01

    ABSTRAK Analisis Harga Pokok Produksi dan Penerapan Target Costing pada UD Wajuku Makassar The Analysis of The Cost of Goods Manufactured and Implementation of Target Costing in UD Wajuku Makassar Chaidir Hafid Asri Usman Syahrir Penelitian ini bertujuan untuk mengetahui perhitungan harga pokok produksi baju kaos polos sebelum dan setelah penerapan metode target costing pada UD Wajuku Makassar. Metode pengumpulan data yang digunakan adalah dokumentasi. Metode analisis dat...

  20. PENGUKURAN KINERJA PERUSAHAAN PT. HADJI KALLA DENGAN MENGGUNAKAN ANALISIS ECONOMIC VALUE ADDED

    OpenAIRE

    2013-01-01

    Tujuan dari penelitian ini adalah mengetahui kinerja Economic Value Added (EVA) yang dicapai oleh perusahaan PT. Hadji Kalla, sedangkan metode analisis yang digunakan dalam penelitian ini adalah analisis perkembangan Economic Value Added (EVA), Net Operating Profit After Tax (NOPAT) dan The purpose of this study was to determine the performance of the Economic Value Added (EVA), which is achieved by the company PT. Hadji Kalla...

  1. Responsability of nuclear industry

    International Nuclear Information System (INIS)

    Cadiz Deleito, J.C.

    1985-01-01

    Since the beginning of nuclear industry, civil responsibility with damages to the public health and properties was a critical problem, because the special conditions of this industry (nuclear accident, damages could be very high but probability of these events is very low). Legal precepts, universally accepted, in the first 60 years for all countries interested in nuclear energy are being revised, then 20 years of experience. The civil responsibility limited is being questioned and indemnities updated. (author)

  2. ANALISIS MODEL PREDIKSI AWAL MUSIM HUJAN DI SULAWESI SELATAN

    Directory of Open Access Journals (Sweden)

    Alimatul Rahim

    2016-03-01

    Full Text Available Model prediksi awal musim hujan merupakan salah satu kunci yang dapat digunakan untuk mengurangi resiko kegagalan panen padi yang disebabkan oleh faktor iklim di provinsi Sulawesi Selatan. Model prediksi awal musim hujan dibangun  dengan menggunakan data curah hujan observasi Sulawesi Selatan dan anomali suhu muka laut di kawasan Pasifik dan perairan Sulawesi. Pada studi ini dilakukan analisis pemilihan stasiun hujan observasi, penentuan awal musim hujan, analisis komponen utama dan pengelompokan, analisis korelasi awal musim hujan terhadap anomali suhu muka laut, pembangunan model untuk prediksi awal musimhujan dan verifikasi model.Hasil analisis awal musim hujan menunjukkan setiap stasiun hujan mempunyai perbedaan awal musim hujan dengan rata-rata jatuh pada Julian Date (JD ke-348 (14 Desember. Berdasarkan hasil analisis PCA dan cluster, diperoleh bahwa di Sulawesi Selatan terbagi menjadi 3 cluster wilayah. Cluster 1 mempunyai pola hujan lokal, sedangkan cluster 2 dan 3 mempunyai pola hujan monsun. Pada peta korelasi antara awal musim hujan di Sulawesi Selatan dan anomali suhu muka laut menunjukkan bahwa terdapat korelasi nyata(r≥0.5 antara kawasan Pasifik dan Laut Sulawesi pada cluster 1 dan 2 pada bulan Juni Juli Agustus September(JJAS. Sedangkan pada cluster 3, korelasi nyata hanya pada bulan Juni di perairan Sulawesi. Model prediksi AMH terbaik, pada cluster 2 terdapat di domain prediktor kawasan pasifik dengan nilai r=0.82, sedangkan pada cluster 1 dan 3, terdapat di domain perairan Sulawesi dengan nilai r=0.78 dan r-0.48. Verifikasi model terpilih pada cluster 3 mempunyai RMSE = 3, sedangkan cluster 1 dan 2, nilai RMSE berturut-turut sebesar 16 dan 29.   Model prediction of rainy season onset is one of the keys to reduce the risk of paddy haverst failure because of climate factor in South Sulawesi province. The model prediction for rainy season onset was build using rainfall data in South Sulawesi and SST anomaly in Pacific Ocean and

  3. Thermographic Analisys, an Energy Audit Approach

    Energy Technology Data Exchange (ETDEWEB)

    Braga, Luis; Coelho, Sonia [RAR - Refinaria de Acucar Reunidas, S.A. (Portugal)

    2009-07-01

    Thermography is a technique that allows the thermal characterization of one, of several objects, based on heat transfer by radiation recuring to infrared system. Observing the images we can easily locate heat losses, compressed air leaks, and identify potential problems with equipment or insulation. When correctly used it can reduce the time spent in the analysis performed on location, for a large quantity of equipment observed, and also provide useful information otherwise unavailable. This paper states the work developed in Portuguese Sugar Refinery - RAR - Refinaria de Acucar Reunidas S.A. more specifically on its cogen plant. Using an infra-red camera it was made an identification of the places to be checked regarding the thermal insulation (installation and recovery of damaged material and bad applications). This technique provided good information regarding the best places to achieve maximum results, some sections with heat losses were identified which otherwise would persist undetected. This analysis provided the best information with minimal spent time, maximizing the productivity of the auditor's work. The practical result of this work was insulation installation and repair. The outcome was a payback time of about five months.

  4. Design of the accelerator stand with the ecr-source for simulation experiments on the of radiation damage of the steels of the nuclear industry

    International Nuclear Information System (INIS)

    Chalykh, B.B.; Kuybeda, R.P.; Kulevoy, T.V.; Ziyatdinova, A.V.

    2014-01-01

    The imitation experiments of irradiation resistivity for steels used in nuclear industry by heavy ion beams are promising demand for material properties investigation. The formation of the defects on the real-existing reactors is fraught with many difficulties such as a long-term session of exposure and induced radioactivity in samples. Simulation of radiation defects on accelerators of charged particles does not have such a drawback. To form radiation defects in matter, it is necessary to have beams of various ions with different energy. The concept of the test bench based on a ECR heavy-ion source for the imitation experiments of the materials resistance under irradiation is presented and discussed.

  5. Membandingkan Tingkat Kemiripan Rekaman Voice Changer Menggunakan Analisis Pitch, Formant dan Spectogram

    Directory of Open Access Journals (Sweden)

    Ahmad Subki

    2018-02-01

    Full Text Available Audio forensik merupakan salah satu ilmu yang mnyandingkan antara ilmu pengetahuan dan metode ilmiah dalam proses analisis rekaman suara untuk membantu dan mendukung pengungkapan suatu tindak kejahatan yang diperlukan dalam proses persidangan. Undang-undang ITE No.19 Tahun 2016 menyebutkan bahwa rekaman suara merupakan salah satu alat bukti digital yang sah dan dapat digunakan sebagai penguat dakwaan. Rekaman suara yang merupakan barang bukti digital sangatlah mudah dan rentan dimanipulasi, baik secara sengaja maupun tidak disengaja. Pada penelitian ini dilakukan analisis terkait tingkat kemiripan antara rekaman suara voice changer dengan rekaman suara asli menggunakan analisis pitch, formant dan spectogram, rekaman suara yang dianalisis ada dua jenis rekaman suara yaitu suara laki-laki dan suara perempuan. Rekaman suara voice changer  dan rekaman suara asli, diekstrak menggunakan tools praat kemudian informasi yang diperoleh dianalisis dengan analisis statistik pitch, formant dan spectrogrammenggunakan tools gnumeric. Penelitian ini menghasilkan bahwa analisis rekaman suara voice changer dengan rekaman suara asli dapat menggunakan analisis statistik pitch, formant dan spectrogram, rekaman suara voice changer A memiliki tingkat kemiripan yang paling tinggi dengan rekaman suara asli pada posisi low pitch, sedangkan voice changer yang lain lebih sulit untuk diidentifikasi.

  6. Estimating the lifetimes of titanium containers for nuclear fuel waste: A damage function for the crevice corrosion of grade-2 titanium

    International Nuclear Information System (INIS)

    Shoesmith, D.W.; Ikeda, B.M.; Quinn, M.J.; Kolar, M.

    1995-06-01

    The assumptions upon which the lifetime failure model used in the postclosure assessment is based are reevaluated. In particular, the conservations involved in assuming that crevice initiation would occur, and that sufficient oxygen would be present to maintain crevice propagation to failure, are discussed. Unless the period required to saturate the environment around the container can be specified with some certainty, it remains necessary to assume corrosion would initiate rapidly on all containers. A modified version of the container lifetime model has been developed which avoids the need to use averaged temperature profiles. In this model, these profiles are converted to propagation rate profiles using an experimental activation energy and then numerically integrated to predict container failure times. A damage function is developed relating the maximum depth of penetration by crevice corrosion to either the time since emplacement in the vault or the total amount of oxygen consumed. This function is used to estimate the maximum penetration depth expected if all the oxygen available in a borehole is consumed in crevice corrosion and to determine the impact on container lifetimes of various repassivation criteria. The factors likely to cause repassivation are summarized, and a number of engineering approaches to extending container lifetimes suggested. (author). 22 refs., 1 tab., 17 figs

  7. [Economic damage caused by lowered prices in the agro-food sector in areas contaminated by radioactive materials leaked from the nuclear power plant severely damaged by the 2011 Great East Japan Earthquake--consideration from the viewpoints of epidemiology, economics and social psychology].

    Science.gov (United States)

    Sugita, Minoru; Miyakawa, Michiko

    2013-01-01

    Large amounts of radioactive materials were leaked into the environment from the Fukushima Daiichi Nuclear Power Plant (FDNPP) of the Tokyo Electric Power Company, which was severely damaged by the 2011 Tohoku Region Pacific Coast Earthquake and accompanying tsunami. Economic damage due to lowered prices and supplies of food products produced in the areas contaminated by the radioactive materials leaked from the damaged FDNPP to the agro-food sector in the affected areas is notable. In Japanese, this is known as fuhyo higai. In this study, we investigated fuhyo higai from the viewpoints of epidemiology, economics, and social psychology in an effort to seek solutions. Information was obtained from articles in print and on the Internet. Fuhyo higai, or economic damage of the agro-food sector, which is the main industry in the contaminated areas, is serious because it is difficult to reassure the general population regarding food safety. This fuhyo higai does not derive solely from rumor. It has been reported that improving the science literacy of the general population is important as a countermeasure against fuhyo higai, but this may not be effective because of the human social structure and behavior of people who seek subjective safety. Almost all radiological laboratory results of samples of food produced in the contaminated areas were below detectable limits. Very high values were rarely detected. In general, information about the dose-response relationship is obtained under the assumption that there may be error in the response but not in the dose. The rare cases of extremely high radiological values of food samples from the contaminated areas may correspond to large errors in dose. However, it is difficult to deny a high-dose risk. The reported information on the dose-response relationship obtained under the assumption that there is no error in dose is not sufficient. Thus, response, i.e., health risk, cannot be correctly estimated. This leads the general

  8. Electricity and nuclear energy

    International Nuclear Information System (INIS)

    Krafft, P.

    1987-01-01

    Consequences of getting out from nuclear energy are discussed. It is concluded that the Chernobyl accident is no reason to withdraw confidence from Swiss nuclear power plants. There are no sufficient economizing potential and other energies at disposal to substitute nuclear energy. Switching to coal, oil and gas would increase environmental damages. Economic and social cost of getting out would be too high

  9. Nuclear Energy in Perspective

    International Nuclear Information System (INIS)

    1989-01-01

    This report provides the interested non-specialist reader with insights on five major issues associated with nuclear power generation: nuclear development and economics, protection of man and the environment, power plant safety, radioactive waste management and compensation for damage from a nuclear accident

  10. Damaged Skylab

    Science.gov (United States)

    1973-01-01

    The Saturn V vehicle, carrying the unmarned orbital workshop for the Skylab-1 mission, lifted off successfully and all systems performed normally. Sixty-three seconds into the flight, engineers in the operation support and control center saw an unexpected telemetry indication that signalled that damages occurred on one solar array and the micrometeoroid shield during the launch. The micrometeoroid shield, a thin protective cylinder surrounding the workshop protecting it from tiny space particles and the sun's scorching heat, ripped loose from its position around the workshop. This caused the loss of one solar wing and jammed the other. Still unoccupied, the Skylab was stricken with the loss of the heat shield and sunlight beat mercilessly on the lab's sensitive skin. Internal temperatures soared, rendering the station uninhabitable, threatening foods, medicines, films, and experiments. This image, taken during a fly-around inspection by the Skylab-2 crew, shows a crippled Skylab in orbit. The crew found their home in space to be in serious shape; the heat shield gone, one solar wing gone, and the other jammed. The Marshall Space Flight Center (MSFC) developed, tested, rehearsed, and approved three repair options. These options included a parasol sunshade and a twin-pole sunshade to restore the temperature inside the workshop, and a set of metal cutting tools to free the jammed solar panel.

  11. Structural damage

    International Nuclear Information System (INIS)

    Gray, R.E.; Bruhn, R.W.

    1992-01-01

    Virtually all structures show some signs of distress due to deterioration of the building components, to changed loads, or to changed support conditions. Changed support conditions result from ground movements. In mining regions many cases of structural distress are attributed to mining without considering alternative causes. This is particularly true of coal mining since it occurs under extensive areas. Coal mining is estimated to have already undermined more than eight million acres and may eventually undermine 40 million acres in the United States. Other nonmetal and metal underground mines impact much smaller areas. Although it is sometimes difficult, even with careful study, to identify the actual cause of damage, persons responsible for underground coal mining should at least be aware of possible causes of building stress other than mine subsidence. This paper presents information on distress to structures and briefly reviews a number of causes of ground movements other than subsidence: Mass movements, dissolution, erosion, frost action, shrinking and swelling, yield into excavations and compressibility

  12. Nuclear Safety

    International Nuclear Information System (INIS)

    1978-09-01

    In this short paper it has only been possible to deal in a rather general way with the standards of safety used in the UK nuclear industry. The record of the industry extending over at least twenty years is impressive and, indeed, unique. No other industry has been so painstaking in protection of its workers and in its avoidance of damage to the environment. Headings are: introduction; how a nuclear power station works; radiation and its effects (including reference to ICRP, the UK National Radiological Protection Board, and safety standards); typical radiation doses (natural radiation, therapy, nuclear power programme and other sources); safety of nuclear reactors - design; key questions (matters of concern which arise in the public mind); safety of operators; safety of people in the vicinity of a nuclear power station; safety of the general public; safety bodies. (U.K.)

  13. Radiation damage prediction system using damage function

    International Nuclear Information System (INIS)

    Tanaka, Yoshihisa; Mori, Seiji

    1979-01-01

    The irradiation damage analysis system using a damage function was investigated. This irradiation damage analysis system consists of the following three processes, the unfolding of a damage function, the calculation of the neutron flux spectrum of the object of damage analysis and the estimation of irradiation effect of the object of damage analysis. The damage function is calculated by applying the SAND-2 code. The ANISN and DOT3, 5 codes are used to calculate neutron flux. The neutron radiation and the allowable time of reactor operation can be estimated based on these calculations of the damage function and neutron flux. The flow diagram of the process of analyzing irradiation damage by a damage function and the flow diagram of SAND-2 code are presented, and the analytical code for estimating damage, which is determined with a damage function and a neutron spectrum, is explained. The application of the irradiation damage analysis system using a damage function was carried out to the core support structure of a fast breeder reactor for the damage estimation and the uncertainty evaluation. The fundamental analytical conditions and the analytical model for this work are presented, then the irradiation data for SUS304, the initial estimated values of a damage function, the error analysis for a damage function and the analytical results are explained concerning the computation of a damage function for 10% total elongation. Concerning the damage estimation of FBR core support structure, the standard and lower limiting values of damage, the permissible neutron flux and the allowable years of reactor operation are presented and were evaluated. (Nakai, Y.)

  14. Liability for damage to the global commons

    International Nuclear Information System (INIS)

    Leigh, K.

    1993-01-01

    The 'global commons' discussed in this paper are the areas beyond the limits of national jurisdiction. Responsibility to prevent environmental damage to these areas is clearly recognized in customary international law. On the other hand, although liability for such damage undoubtedly has a useful role to play in protecting these areas, the precise nature of liability for such damage is unclear. Some issues, such as whether liability for such damage is strict or tied to breaching a standard of care and the definition of environmental damage, equally arise in relation to damage to the environment of States. Others, such as who could take action to enforce the liability and the nature of the remedy, raise special problems in the case of damage to the global commons. The work under way in the IAEA Standing Committee on Liability for Nuclear Damage provides an opportunity for clarifying these issues in relation to nuclear damage to the global commons. Treaties dealing with particular types of damage which have recently been adopted or are currently being developed in other fields provide a starting point in dealing with this matter. More work, however, needs to be done

  15. ANALISIS KELAYAKAN FINANSIAL WISATA AIR WADUK JATIGEDE KABUPATEN SUMEDANG

    Directory of Open Access Journals (Sweden)

    Bambang Susanto

    2016-04-01

    pendahuluan agar manfaatnya jauh lebih besar dari biaya yang dikeluarkan. Oleh sebab itu untuk kepentingan ilmiah perlu dilakukan kajian akademisnya berupa Analisis kelayakan Finansial. Berdasarkan analisis kelayakan keuangan   ,dapat  disimpulkan bahwa wisata air di Waduk jatigede Kabupaten Sumedang  memberikan manfaat yang lebih dibandingkan dengan biaya yang dikeluarkan . ini dapat dilihat dari hasil analisis net present value yang positif, internal rate of return yang lebih besar dari tingkat bunga bank serta benefit cost yang lebih besar dari satu. Kata Kunci: Kelayakan Finansial; Wisata Air.

  16. ANALISIS RELEVANSI LULUSAN PERGURUAN TINGGI DENGAN DUNIA KERJA

    Directory of Open Access Journals (Sweden)

    Ali Muhson

    2012-04-01

    Full Text Available Abstract: A Relevance Analysis of University Graduates with World of Work. Education should be oriented to the competencies required by the workforce as a percentage of unemployment among the educated increase continuously. This study aims to examine the relevance of YSU Economic Education graduates. The study only focuses on the type of work and subjects taught. The subject of this study is the alumni of Economic Education Study Program. Sampling technique used is snowball sampling. Data collection technique using questionnaires and documentation while the technique of data analysis using descriptive analysis. The result suggests that the majority of the graduates find their first job as private a teacher, a private employee and a tutor, while current job of the most graduates are private teacher, private employee, and civil servant (teacher. The data shows that more than 50 percent of the graduates work in the education area. This implies that the relevance level based on the type of work is categorized as sufficient. Majority of the graduates teaches social science, economic, and entrepreneurship, hence it can be concluded that the relevance level based on the subjects taught is highly relevant.   Keyword: relevance of graduates, type of work, unemployment, employment     Abstrak: Analisis Relevansi Lulusan Perguruan Tinggi dengan Dunia Kerja. Pendidikan harus berorientasi pada kompetensi yang dibutuhkan oleh dunia kerja karena persentase penganggur di kalangan terdidik terus meningkat. Penelitian ini bertujuan untuk mengkaji tingkat relevansi (kesesuaian lulusan Pendidikan Ekonomi UNY. Kajian hanya diarahkan pada jenis pekerjaan dan mata pelajaran yang diampu. Penelitian ini mengambil subjek alumni Prodi Pendidikan Ekonomi dari berbagai angkatan. Teknik sampling yang digunakan adalah snowball sampling. Teknik pengumpulan data menggunakan angket dan dokumentasi sedangkan teknik analisis data menggunakan analisis deskriptif. Penelitian ini

  17. Effective atomic number, energy loss and radiation damage studies in some materials commonly used in nuclear