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.

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)

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)

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)

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

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

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

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

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)

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)

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.

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.

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)

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

Rules common to nuclear incidents occurring in installations or during transport of nuclear substances

International Nuclear Information System (INIS)

Lagorce, M.

1976-01-01

As concerns the peaceful applications of nuclear power, the traditional third party liability regulations were found to be inadequate to cover the specific aspects of the nuclear risk, and this was likely to hinder the progress of this new activity. This was why the countries involved opted for the elaboration of a special liability regime by adopting the Paris Convention of 29th July 1960, the Convention Supplementary to the Paris Convention of the 31st January 1963 and the Vienna Convention of 21st May 1963. The Paris and Vienna Conventions set up a regime characterized by the nuclear operator's absolute and exclusive liability, the limitation of such liability in amount and in time the uniquity of jurisdictional competence, the obligation to provide financial security for compensation of damage. The purpose of the Brussels Supplementary Convention is to increase the amount of compensation for damage by additional funds supplied partly by the State involved and partly by a collective contribution from the various countries Parties to the Convention, thus setting up a mechanism of international solidarity. (NEA) [fr

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

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.)

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

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

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.

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.)

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

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

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

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

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

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...

Nuclear fusion during yeast mating occurs by a three-step pathway.

Science.gov (United States)

Melloy, Patricia; Shen, Shu; White, Erin; McIntosh, J Richard; Rose, Mark D

2007-11-19

In Saccharomyces cerevisiae, mating culminates in nuclear fusion to produce a diploid zygote. Two models for nuclear fusion have been proposed: a one-step model in which the outer and inner nuclear membranes and the spindle pole bodies (SPBs) fuse simultaneously and a three-step model in which the three events occur separately. To differentiate between these models, we used electron tomography and time-lapse light microscopy of early stage wild-type zygotes. We observe two distinct SPBs in approximately 80% of zygotes that contain fused nuclei, whereas we only see fused or partially fused SPBs in zygotes in which the site of nuclear envelope (NE) fusion is already dilated. This demonstrates that SPB fusion occurs after NE fusion. Time-lapse microscopy of zygotes containing fluorescent protein tags that localize to either the NE lumen or the nucleoplasm demonstrates that outer membrane fusion precedes inner membrane fusion. We conclude that nuclear fusion occurs by a three-step pathway.

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

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

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

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

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)

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)

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.)

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?

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

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

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

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)

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

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

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.)

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.)

Nuclear decay data for radionuclides occurring in routine releases from nuclear fuel cycle facilities

Energy Technology Data Exchange (ETDEWEB)

Kocher, D.C.

1977-08-01

This report gives tabulations of the atomic and nuclear radiations emitted by 240 radionuclides. Most of the radionuclides are those expected to occur in routine releases of effluents from nuclear fuel cycle facilities. For each radionuclide are given the half-life and recommended values for the energies, intensities, and equilibrium absorbed-dose constants for each of the atomic and nuclear radiations. Also given are the daughter radionuclides produced and recommended values for decay branching ratios, where applicable. The radioactivity decay chains and branching ratios are displayed in diagram form.

Nuclear decay data for radionuclides occurring in routine releases from nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Kocher, D.C.

1977-08-01

This report gives tabulations of the atomic and nuclear radiations emitted by 240 radionuclides. Most of the radionuclides are those expected to occur in routine releases of effluents from nuclear fuel cycle facilities. For each radionuclide are given the half-life and recommended values for the energies, intensities, and equilibrium absorbed-dose constants for each of the atomic and nuclear radiations. Also given are the daughter radionuclides produced and recommended values for decay branching ratios, where applicable. The radioactivity decay chains and branching ratios are displayed in diagram form

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.

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

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

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.)

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

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

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

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

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

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.)

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.)

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.

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.

Modification of radiation damage by naturally occurring substances

International Nuclear Information System (INIS)

Prasad, K.N.

1984-01-01

The major objectives of studying the modification of radiation sensitivity have been (1) to identify a compound that will produce a differential protection or sensitization of the effect of irradiation on normal and tumor tissue, and (2) to understand more about the mechanisms of radiation damage. In spite of massive research on this particular problem since World War II, the first objective remains elusive. During this period, numerous radioprotective and radiosensitizing agents have been identified. These agents have served as important biologic tools for increasing our understanding of radiation injuries. Most of these substances are synthetic compounds and are very toxic to humans. In addition, very few of the compounds provide differential modifications of the effect of radiation on tumor and normal cells. This chapter presents objectives for identifying naturally occurring substances that modify the effect of x-radiation on mammalian cells and discusses the role of physiologic substances in modifying radiation injuries on mammalian normal and tumor cells

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)

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

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

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

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

Plight of China nuclear liability law and solutions of nuclear operating companies

International Nuclear Information System (INIS)

Su Guangchao; Wang Yonggang; Tang Yangyang

2010-01-01

With the development of nuclear use for peaceful purposes and the intensification of international cooperation in the field of nuclear energy, many countries attach more and more importance to legal risks of nuclear liability, and the companies in nuclear industry also enhance research on restrictive articles of nuclear liability in their international businesses. However, because China has neither signed any international convention on civil liability for nuclear damage nor adopted any law on atomic energy and on compensation for nuclear damage, many impediments often occur in international cooperation and trade. This essay is trying to outline the status and structure of international nuclear liability, analyze nuclear liabilities in international procurement for nuclear operating companies and respective solutions. (authors)

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

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

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.

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

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

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)

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

chemical of steel components concentration profiles after irradiated, among others. MCNPX version 2005 and SRIM-2011 there are the computer codes used in the Monte Carlo simulation for analyzing the vessel damage theoretically due to penetration and the radiation transport of the neutrons coming of the reactor core. With MCNPX was determined the profile of neutrons penetration, the photons flux, electrons, alphas, protons deuterons, etc, in the interior of the vessel, the profile of energy deposited by all particles generated in the interaction of neutrons with the steel atomic structures, the profile displacement, the regions of greater damage as well as the total damage over the life of the reactor, among many others. With SRIM-2011 was determined the atomic displacements profile of each atomic species in the steel (Fe, Ni, Mn, Cr, Mo, V, Cu, etc.), the energy deposited profile by each atomic species, the profile of damage in the interior of the vessel, the greater damage region as well as the total damage throughout the life of the nuclear reactor. The theoretical results have enabled understanding of physical phenomena occurring in the crystalline structure of steel, by influence of irradiation neutron to determine the region of greatest possible damage in the crock. The theoretical results were compared with experimental results and those of international references in this field of research. Among other results, is determined that the region of greater damage occurs in the first millimeter of depth of the vessel and confirms its full integrity after eight years of neutron irradiation and to not less than 60 years of life with a thickness of 12 cm. (Author)

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.

Damages of industrial equipments in the 1995 Hyougoken-Nanbu Earthquake

International Nuclear Information System (INIS)

Iwatsubo, Takuzo

1997-01-01

Hanshin-Awaji area has a population of approximately 3 million and many industries, including heavy industry, harbor facilities and international trading companies. The 1995 Hyougoken-Nanbu Earthquake occurred just in this area which is 25kmx2km oblong containing Kobe city. About 5,500 people were killed and 250,000 people lost their houses. Japan society of mechanical engineers organized the investigative committee of earthquake disaster of industrial equipments after the earthquake in order to investigate the disaster damages of industrial equipments and to give data for a design manual for mechanical equipments against earthquake excitation. This is an investigation report of the disaster damages of industrial machine equipments. Damages to machine equipment of industries in the high intensity region of the earthquake are illustrated. The mechanisms of the damages and measures against earthquake and safety of nuclear power plant design are discussed. Then it is known that the design of nuclear power plant is different from the general industrial facilities and the damage which was suffered in the general industrial facilities does not occur in the nuclear power plant. (J.P.N.)

Damages of industrial equipments in the 1995 Hyougoken-Nanbu Earthquake

Energy Technology Data Exchange (ETDEWEB)

Iwatsubo, Takuzo [Kobe Univ. (Japan). Faculty of Engineering

1997-03-01

Hanshin-Awaji area has a population of approximately 3 million and many industries, including heavy industry, harbor facilities and international trading companies. The 1995 Hyougoken-Nanbu Earthquake occurred just in this area which is 25kmx2km oblong containing Kobe city. About 5,500 people were killed and 250,000 people lost their houses. Japan society of mechanical engineers organized the investigative committee of earthquake disaster of industrial equipments after the earthquake in order to investigate the disaster damages of industrial equipments and to give data for a design manual for mechanical equipments against earthquake excitation. This is an investigation report of the disaster damages of industrial machine equipments. Damages to machine equipment of industries in the high intensity region of the earthquake are illustrated. The mechanisms of the damages and measures against earthquake and safety of nuclear power plant design are discussed. Then it is known that the design of nuclear power plant is different from the general industrial facilities and the damage which was suffered in the general industrial facilities does not occur in the nuclear power plant. (J.P.N.)

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)

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

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.

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

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)

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.

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)

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.

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.

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)

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

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)

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

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

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)

Descriptions of selected accidents that have occurred at nuclear reactor facilities

Energy Technology Data Exchange (ETDEWEB)

Bertini, H.W.

1980-04-01

This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established.

Descriptions of selected accidents that have occurred at nuclear reactor facilities

International Nuclear Information System (INIS)

Bertini, H.W.

1980-04-01

This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established

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)

Analysis of events occurred at overseas nuclear power plants in 2004

International Nuclear Information System (INIS)

Miyazaki, Takamasa; Nishioka, Hiromasa; Sato, Masahiro; Chiba, Gorou; Takagawa, Kenichi; Shimada, Hiroki

2005-01-01

The Institute of Nuclear Safety Systems (INSS) investigates the information related to events and incidents occurred at overseas nuclear power plants, and proposes recommendations for the improvement of the safety and reliability of domestic PWR plants by evaluating them. Succeeding to the 2003 report, this report shows the summary of the evaluation activity and of the tendency analysis based on about 2800 information obtained in 2004. The tendency analysis was undertaken on about 1700 analyzed events, from the view point of mechanics, electrics and operations, about the causes, troubled equipments and so on. (author)

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

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)

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)

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)

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)

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

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)

Insurance of nuclear risk

International Nuclear Information System (INIS)

Lacroix, M.

1976-01-01

Insurance for large nuclear installations covers mainly four types of risk: third party liability which in accordance with the nuclear conventions, is borne by a nuclear operator following an incident occurring in his installation or during transport of nuclear substances; material damage to the installation itself, which precisely is not covered by third party liability insurance; machinery breakdown, i.e. accidental damage or interruption of operation. Only the first category must be insured. In view of the magnitude of the risk, nuclear insurance resorts to co-insurance and reinsurance techniques which results in a special organisation of the nuclear insurance market, based on national nuclear insurance pools and on the Standing Committee on Atomic Risk of the European Insurance Committee. Conferences of the chairmen of nuclear insurance pools are convened regularly at a worldwide level. (NEA) [fr

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

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.

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.

Analysis of external flooding events occurred in foreign nuclear power plant sites

International Nuclear Information System (INIS)

Li Dan; Cai Hankun; Xiao Zhi; An Hongzhen; Mao Huan

2013-01-01

This paper screens and studies 17 external flooding events occurred in foreign NPP sites, analysis the characteristic of external flooding events based on the source of the flooding, the impact on the building, systems and equipment, as well as the threat to nuclear safety. Furthermore, based on the experiences and lessons learned from Fukushima nuclear accident relating to external flooding and countermeasures carried out in the world, some suggestions are proposed in order to improve external flooding response capacity for Chinese NPPs. (authors)

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

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).

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).

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)

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)

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)

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

Protection of naturally occurring antioxidants against oxidative damages to protein

International Nuclear Information System (INIS)

Zhu Hongping; Zhang Zhaoxia; Hao Shumei; Wang Wenfeng; Yao Side

2006-01-01

One of the most compelling theories explaining age-related deterioration is the free radical theory of aging. It has been shown that reactive oxygen species are involved in oxidative damages to biomolecules and this is related to a number of diseases. Proteins, the second most abundant components of cells (next to water by weight), are now increasingly recognized as major biological targets of oxidative damages. Convincing evidences have indicated that damages to protein have been implicated in Alzheimer's disease, Parkinson's disease, cancer, and aging. Antioxidant has been the subject of great attention because they are known to lower the risk of cardiovascular and other diseases. Hydroxycinnamic acid derivatives (HCAs) are antioxidants abundant in tea, red wine, fruits, beverages and various medicinal plants. Results showed that they exhibit remarkable activity for scavenging oxidizing radicals and triplet states. The protective effects of four kinds of HCAs on oxidative damages to lysozyme were investigated in our lab. Protein damages induced by two different paradigms: riboflavin-sensitized photooxidation and hydroxyl ( . OH)-mediated oxidation, were investigated using polyacrylamide gel electrophoresis. HCAs were found to inhibit the cross-linking of protein induced by riboflavin-mediated photooxidation. HCAs also exhibited protection effect on lysozyme damage induced by γ-ray irradiation. The rate constants for quenching triplet state of riboflavin by lysozyme and HCAs were obtained using laser flash photolysis. The protective mechanism was proposed based on the dynamic study. HCAs were found to protect protein against oxidation by scavenging oxidizing species and repairing the damaged protein. (authors)

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

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)

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)

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.)

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.

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

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)

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

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

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)

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

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)

DNA damage in plant herbarium tissue.

Science.gov (United States)

Staats, Martijn; Cuenca, Argelia; Richardson, James E; Vrielink-van Ginkel, Ria; Petersen, Gitte; Seberg, Ole; Bakker, Freek T

2011-01-01

Dried plant herbarium specimens are potentially a valuable source of DNA. Efforts to obtain genetic information from this source are often hindered by an inability to obtain amplifiable DNA as herbarium DNA is typically highly degraded. DNA post-mortem damage may not only reduce the number of amplifiable template molecules, but may also lead to the generation of erroneous sequence information. A qualitative and quantitative assessment of DNA post-mortem damage is essential to determine the accuracy of molecular data from herbarium specimens. In this study we present an assessment of DNA damage as miscoding lesions in herbarium specimens using 454-sequencing of amplicons derived from plastid, mitochondrial, and nuclear DNA. In addition, we assess DNA degradation as a result of strand breaks and other types of polymerase non-bypassable damage by quantitative real-time PCR. Comparing four pairs of fresh and herbarium specimens of the same individuals we quantitatively assess post-mortem DNA damage, directly after specimen preparation, as well as after long-term herbarium storage. After specimen preparation we estimate the proportion of gene copy numbers of plastid, mitochondrial, and nuclear DNA to be 2.4-3.8% of fresh control DNA and 1.0-1.3% after long-term herbarium storage, indicating that nearly all DNA damage occurs on specimen preparation. In addition, there is no evidence of preferential degradation of organelle versus nuclear genomes. Increased levels of C→T/G→A transitions were observed in old herbarium plastid DNA, representing 21.8% of observed miscoding lesions. We interpret this type of post-mortem DNA damage-derived modification to have arisen from the hydrolytic deamination of cytosine during long-term herbarium storage. Our results suggest that reliable sequence data can be obtained from herbarium specimens.

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

Phenomena occuring in the reactor coolant system during severe core damage accidents

International Nuclear Information System (INIS)

Malinauskas, A.P.

1990-01-01

The reactor coolant system (RCS) of a nuclear power plant consists of the reactor pressure vessel and the piping and associated components that are required for the continuous circulation of the coolant which is used to maintain thermal equilibrium throughout the system. This paper discusses, how in the event of an accident, the RCS also serves as one of several barriers to the escape of radiotoxic material into the biosphere. The physical and chemical processes occurring within the RCS during normal operation of the reactor are relatively uncomplicated and are reasonably well understood. When the flow of coolant is properly adjusted, the thermal energy resulting from nuclear fission (or, in the shutdown mode, from radioactive decay processes) and secondary inputs, such as pumps, are exactly balanced by thermal losses through the RCS boundaries and to the various heat sinks that are employed to effect the conversion of heat to electrical energy. Because all of the heat and mass fluxes remain sensibly constant with time, mathematical descriptions of the thermophysical processes are relatively straightforward, even for boiling water reactor (BWR) systems. Although the coolant in a BWR does undergo phase changes, the phase boundaries remain well-defined and time-invariant

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.

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)

Phenomena occurring in the reactor coolant system during severe core damage accidents

International Nuclear Information System (INIS)

Malinauskas, A.P.

1989-01-01

The reactor coolant system (RCS) of a nuclear power plant consists of the reactor pressure vessel and the piping and associated components that are required for the continuous circulation of the coolant which is used to maintain thermal equilibrium throughout the system. In the event of an accident, the RCS also serves as one of several barriers to the escape of radiotoxic material into the biosphere. In contrast to normal operating conditions, severe core damage accidents are characterized by significant temporal and spatial variations in heat and mass fluxes, and by eventual geometrical changes within the RCS. Furthermore, the difficulties in describing the system in the severe accident mode are compounded by the occurrence of chemical reactions. These reactions can influence both the thermal and the mass transport behavior of the system. In addition, behavior of the reactor vessel internals and of materials released from the core region (especially the radioactive fission products) in the course of the accident likewise become of concern to the analyst. This report addresses these concerns. 9 refs., 1 tab

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.

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

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

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)

Analysis of adverse events occurred at overseas nuclear power plants in 2003

International Nuclear Information System (INIS)

Miyazaki, Takamasa; Sato, Masahiro; Takagawa, Kenichi; Fushimi, Yasuyuki; Shimada, Hiroki; Shimada, Yoshio

2004-01-01

The adverse events that have occurred in the overseas nuclear power plants can be studied to provide an indication of how to improve the safety and the reliability of nuclear power plants in Japan. The Institute of Nuclear Safety Systems (INSS) obtains information related to overseas adverse events and incidents, and by evaluating them proposes improvements to prevent similar occurrences in Japanese PWR plants. In 2003, INSS obtained approximately 2800 pieces of information and, by evaluating them, proposed nine recommendations to Japanese utilities. This report shows a summary of the evaluation activity and of the tendency analysis based on individual event analyzed in 2003. The tendency analysis was undertaken on about 1600 analyzed events, from the view point of Mechanics, Electrics, Instruments and Controls and Operations, about the causes, countermeasures, troubled equipments and the possible of lessons learnt from overseas events. This report is to show the whole tendency of overseas events and incidents for the improvement of the safety and reliability of domestic PWR plants. (author)

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.

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

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)

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

chemical of steel components concentration profiles after irradiated, among others. MCNPX version 2005 and SRIM-2011 there are the computer codes used in the Monte Carlo simulation for analyzing the vessel damage theoretically due to penetration and the radiation transport of the neutrons coming of the reactor core. With MCNPX was determined the profile of neutrons penetration, the photons flux, electrons, alphas, protons deuterons, etc, in the interior of the vessel, the profile of energy deposited by all particles generated in the interaction of neutrons with the steel atomic structures, the profile displacement, the regions of greater damage as well as the total damage over the life of the reactor, among many others. With SRIM-2011 was determined the atomic displacements profile of each atomic species in the steel (Fe, Ni, Mn, Cr, Mo, V, Cu, etc.), the energy deposited profile by each atomic species, the profile of damage in the interior of the vessel, the greater damage region as well as the total damage throughout the life of the nuclear reactor. The theoretical results have enabled understanding of physical phenomena occurring in the crystalline structure of steel, by influence of irradiation neutron to determine the region of greatest possible damage in the crock. The theoretical results were compared with experimental results and those of international references in this field of research. Among other results, is determined that the region of greater damage occurs in the first millimeter of depth of the vessel and confirms its full integrity after eight years of neutron irradiation and to not less than 60 years of life with a thickness of 12 cm. (Author)

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

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

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.)

Radiation Effects in Nuclear Ceramics

Directory of Open Access Journals (Sweden)

L. Thomé

2012-01-01

Full Text Available Due to outstanding physicochemical properties, ceramics are key engineering materials in many industrial domains. The evaluation of the damage created in ceramics employed in radiative media is a challenging problem for electronic, space, and nuclear industries. In this latter field, ceramics can be used as immobilization forms for radioactive wastes, inert fuel matrices for actinide transmutation, cladding materials for gas-cooled fission reactors, and structural components for fusion reactors. Information on the radiation stability of nuclear materials may be obtained by simulating the different types of interactions involved during the slowing down of energetic particles with ion beams delivered by various types of accelerators. This paper presents a review of the radiation effects occurring in nuclear ceramics, with an emphasis on recent results concerning the damage accumulation processes. Energetic ions in the KeV-GeV range are used to explore the nuclear collision (at low energy and electronic excitation (at high energy regimes. The recovery by electronic excitation of the damage created by ballistic collisions (SHIBIEC process is also addressed.

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.

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

Lessons from nuclear disasters

International Nuclear Information System (INIS)

Shigematsu, Itsuzo

2005-01-01

The most severe and worst of all nuclear disasters is, needless to say, the explosion of an atomic bomb. The WHO committee on the effects of nuclear war, established in 1982, concluded that the only approach to the treatment of the health effects of nuclear warfare is primary prevention, that is, the prevention of nuclear war. Nuclear disasters have also occurred in nuclear power plants and nuclear facilities, causing various damage and acute anxiety among the workers and general public, but thus far the related health effects have not always been correctly evaluated. Such problems as exposed population, individual exposed dose and health risks which are associated with these evaluation efforts are discussed here. (author)

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.

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...

Pre-fire planning for nuclear power plants

International Nuclear Information System (INIS)

Talbert, J.H.

1980-01-01

Regardless of the fire prevention measures which are taken, plant experience indicates that fires will occur in a nuclear power plant. When a fire occurs, the plant staff must handle the fire emergency. Pre-fire planning is a method of developing detailed fire attack plans and salvage operations to protect equipment from damage due to fire and fire fighting operations. This paper describes the purpose and use of a pre-fire plan to achieve these goals in nuclear power plants

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)

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

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.

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

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

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.

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

Nuclear Liability and Insurance Protection for Nuclear Transport Accidents Involving Non-Contracting EU States: An assessment

International Nuclear Information System (INIS)

Horbach, N. L. J. T.

2006-01-01

This paper provides an analysis of the possible complications and consequences with respect to nuclear liability and insurance protection applicable in respect of transport activities resulting in damage suffered and/or accidents occurring in EU States that are not party to the Paris Convention. It looks at the different legal aspects (jurisdiction, applicable law, liability amounts, reciprocity) should the revised Vienna and Paris Convention become applicable in comparison with the unrevised Conventions. Within Europe, a large number of States are party to the 1960 Paris Convention and the 1963 Brussels Supplementary Convention, providing liability and insurance protection, in general, up to a limit of 300 million SDRs (or even higher). In principle, such protection is confined to nuclear incidents occurring and nuclear damage suffered in the territory of Contracting Parties, including, as recommended, the high seas, unless the legislation of the Installation State determines otherwise (Article 2). The geographical scope of application of the Paris Convention would thus vary according to the law of the Installation State. However, some EU States never became party to the Paris Convention, and are not bound by its the liability principles (notably, channelling of liability), such as Austria, Luxembourg and Ireland. Transport accidents involving these countries might therefore result in liability claims outside the treaty liability regime against operators, suppliers, carriers or persons involved and for types of damages different from those currently covered by the Paris Convention (e.g., environmental damage). It is uncertain to what extent liability insurance of the installation operators would provide adequate protection and whether related damage claims can be enforceable. In addition, a number of newly entered EU States are party to the Vienna Convention, which, although bound by liability principles basically similar to those of the Paris Convention, will

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

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

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.

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.)

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

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)

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.)

Role of the Checkpoint Clamp in DNA Damage Response

Directory of Open Access Journals (Sweden)

Mihoko Kai

2013-01-01

Full Text Available DNA damage occurs during DNA replication, spontaneous chemical reactions, and assaults by external or metabolism-derived agents. Therefore, all living cells must constantly contend with DNA damage. Cells protect themselves from these genotoxic stresses by activating the DNA damage checkpoint and DNA repair pathways. Coordination of these pathways requires tight regulation in order to prevent genomic instability. The checkpoint clamp complex consists of Rad9, Rad1 and Hus1 proteins, and is often called the 9-1-1 complex. This PCNA (proliferating cell nuclear antigen-like donut-shaped protein complex is a checkpoint sensor protein that is recruited to DNA damage sites during the early stage of the response, and is required for checkpoint activation. As PCNA is required for multiple pathways of DNA metabolism, the checkpoint clamp has also been implicated in direct roles in DNA repair, as well as in coordination of the pathways. Here we discuss roles of the checkpoint clamp in DNA damage response (DDR.

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

Around and beyond 53BP1 Nuclear Bodies.

Science.gov (United States)

Fernandez-Vidal, Anne; Vignard, Julien; Mirey, Gladys

2017-12-05

Within the nucleus, sub-nuclear domains define territories where specific functions occur. Nuclear bodies (NBs) are dynamic structures that concentrate nuclear factors and that can be observed microscopically. Recently, NBs containing the p53 binding protein 1 (53BP1), a key component of the DNA damage response, were defined. Interestingly, 53BP1 NBs are visualized during G1 phase, in daughter cells, while DNA damage was generated in mother cells and not properly processed. Unlike most NBs involved in transcriptional processes, replication has proven to be key for 53BP1 NBs, with replication stress leading to the formation of these large chromatin domains in daughter cells. In this review, we expose the composition and organization of 53BP1 NBs and focus on recent findings regarding their regulation and dynamics. We then concentrate on the importance of the replication stress, examine the relation of 53BP1 NBs with DNA damage and discuss their dysfunction.

Around and beyond 53BP1 Nuclear Bodies

Directory of Open Access Journals (Sweden)

Anne Fernandez-Vidal

2017-12-01

Full Text Available Within the nucleus, sub-nuclear domains define territories where specific functions occur. Nuclear bodies (NBs are dynamic structures that concentrate nuclear factors and that can be observed microscopically. Recently, NBs containing the p53 binding protein 1 (53BP1, a key component of the DNA damage response, were defined. Interestingly, 53BP1 NBs are visualized during G1 phase, in daughter cells, while DNA damage was generated in mother cells and not properly processed. Unlike most NBs involved in transcriptional processes, replication has proven to be key for 53BP1 NBs, with replication stress leading to the formation of these large chromatin domains in daughter cells. In this review, we expose the composition and organization of 53BP1 NBs and focus on recent findings regarding their regulation and dynamics. We then concentrate on the importance of the replication stress, examine the relation of 53BP1 NBs with DNA damage and discuss their dysfunction.

Mono and sequential ion irradiation induced damage formation and damage recovery in oxide glasses: Stopping power dependence of the mechanical properties

International Nuclear Information System (INIS)

Mir, A.H.; Monnet, I.; Toulemonde, M.; Bouffard, S.; Jegou, C.; Peuget, S.

2016-01-01

Simple and complex borosilicate glasses were irradiated with single and double ion beams of light and heavy ions over a broad fluence and stopping power range. As a result of the heavy ion irradiation (U, Kr, Au), the hardness was observed to diminish and saturate after a decrease by 35 ± 1%. Unlike slow and swift heavy ion irradiation, irradiation with light ions (He,O) induced a saturation hardness decrease of 18 ± 1% only. During double ion beam irradiation; where glasses were first irradiated with a heavy ion (gold) and then by a light ion (helium), the light ion irradiation induced partial damage recovery. As a consequence of the recovery effect, the hardness of the pre-irradiated glasses increased by 10–15% depending on the chemical composition. These results highlight that the nuclear energy loss and high electronic energy loss (≥4 keV/nm) result in significant and similar modifications whereas light ions with low electronic energy loss (≤1 keV/nm) result in only mild damage formation in virgin glasses and recovery in highly pre-damaged glasses. These results are important to understand the damage formation and recovery in actinide bearing minerals and in glasses subjected to self-irradiation by alpha decays. - Highlights: • Behavior of glasses strongly depends on the electronic energy loss (Se) of the ions. • High Se (≥4 keV/nm) induces large changes in comparison to lower Se values. • Apart from mild damage formation, low Se causes recovery of pre-existing damage. • Alpha induced partial recovery of the damage would occur in nuclear waste glasses.

The Greenpeace book of the nuclear age

International Nuclear Information System (INIS)

May, John

1989-01-01

This is a comprehensive popular account of both civil and military nuclear accidents. It documents major reactor accidents in certain categories such as where significant injury of death occurred, where there was considerable radioactivity release offsite or where there was actual or suspected core damage. Military accidents on nuclear submarines or involving nuclear weapons and civil incidents such as those involving radioactive waste are also included. the book is organised chronologically from the 1940s through succeeding decades to the 1980s. A concluding chapter gives Greenpeace's own perspective on the state of the nuclear age. (author)

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

Imaging the DNA damage response with PET and SPECT

Energy Technology Data Exchange (ETDEWEB)

Knight, James C.; Koustoulidou, Sofia; Cornelissen, Bart [University of Oxford, CR-UK/MRC Oxford Institute for Radiation Oncology, Department of Oncology, Oxford (United Kingdom)

2017-06-15

DNA integrity is constantly challenged by endogenous and exogenous factors that can alter the DNA sequence, leading to mutagenesis, aberrant transcriptional activity, and cytotoxicity. Left unrepaired, damaged DNA can ultimately lead to the development of cancer. To overcome this threat, a series of complex mechanisms collectively known as the DNA damage response (DDR) are able to detect the various types of DNA damage that can occur and stimulate the appropriate repair process. Each DNA damage repair pathway leads to the recruitment, upregulation, or activation of specific proteins within the nucleus, which, in some cases, can represent attractive targets for molecular imaging. Given the well-established involvement of DDR during tumorigenesis and cancer therapy, the ability to monitor these repair processes non-invasively using nuclear imaging techniques may facilitate the earlier detection of cancer and may also assist in monitoring response to DNA damaging treatment. This review article aims to provide an overview of recent efforts to develop PET and SPECT radiotracers for imaging of DNA damage repair proteins. (orig.)

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)

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.)

Nuclear liability interest in population and environmental exposures from the nuclear fuel cycle

International Nuclear Information System (INIS)

Piccolo, R.G.

1988-01-01

The potential for costly nuclear liability claims is often a hidden dimension to the operation of a nuclear power plant. There are two predominant modes for this to occur: either from on-site exposures to plant workers and alleged bodily injury; or from the release of plant effluents to the environment and alleged property damage and bodily injury. ANI/MAELU recently received 2 multi-million dollar nuclear liability claims alleging environmental damage caused by the routine release of radioactive effluents from nuclear facilities. In both cases, the release of radionuclides appeared to be within appropriate regulations. Two important goals of the regulations are to monitor releases and to ensure that releases are within limits intended to protect the public. While, in fact radionuclide releases are normally within regulatory limits, this does not address the growing perception that radiation at any level is harmful. ANI/MAELU is concerned because this perception impacts the possibility of tort litigation. ANI/MAELU conducted a partial review of the nuclear industry environmental monitoring programs. One general conclusion of this effort is that the industry is adequately monitoring environmental releases, thereby protecting the public. They have also generally concluded that the industry is not well poised to protect itself from some of the consequences of potential liability claims alleging property damage or bodily injury from radiation released to the environment. ANI/MAELU Bulletin 86-1, Environmental Monitoring Programs was issued in February of 1986 addressing this concern. The Bulletin identifies five areas where improvements can be made in environmental monitoring programs to reduce the potential for litigation

Air pollution and brain damage.

Science.gov (United States)

Calderón-Garcidueñas, Lilian; Azzarelli, Biagio; Acuna, Hilda; Garcia, Raquel; Gambling, Todd M; Osnaya, Norma; Monroy, Sylvia; DEL Tizapantzi, Maria Rosario; Carson, Johnny L; Villarreal-Calderon, Anna; Rewcastle, Barry

2002-01-01

Exposure to complex mixtures of air pollutants produces inflammation in the upper and lower respiratory tract. Because the nasal cavity is a common portal of entry, respiratory and olfactory epithelia are vulnerable targets for toxicological damage. This study has evaluated, by light and electron microscopy and immunohistochemical expression of nuclear factor-kappa beta (NF-kappaB) and inducible nitric oxide synthase (iNOS), the olfactory and respiratory nasal mucosae, olfactory bulb, and cortical and subcortical structures from 32 healthy mongrel canine residents in Southwest Metropolitan Mexico City (SWMMC), a highly polluted urban region. Findings were compared to those in 8 dogs from Tlaxcala, a less polluted, control city. In SWMMC dogs, expression of nuclear neuronal NF-kappaB and iNOS in cortical endothelial cells occurred at ages 2 and 4 weeks; subsequent damage included alterations of the blood-brain barrier (BBB), degenerating cortical neurons, apoptotic glial white matter cells, deposition of apolipoprotein E (apoE)-positive lipid droplets in smooth muscle cells and pericytes, nonneuritic plaques, and neurofibrillary tangles. Persistent pulmonary inflammation and deteriorating olfactory and respiratory barriers may play a role in the neuropathology observed in the brains of these highly exposed canines. Neurodegenerative disorders such as Alzheimer's may begin early in life with air pollutants playing a crucial role.

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

The deleterious effects of the nuclear crisis in Japan; Os deleterios impactos da crise nuclear no Japao

Energy Technology Data Exchange (ETDEWEB)

Marques, Paulo [Universidade de Sao Paulo (USP), SP (Brazil)

2012-07-01

This work reports the severe nuclear incident occurred in Japan on March 11, 2011, due a earthquake followed by tsunami, where three of six existing reactors in Daiichi-Fukushima were damaged. The explosions with releasing of radioactive materials to environment have been discussed. It has shown the harmful effects of radiations to the exposed human being. Besides, the existence of the main impediment of the nuclear electric generation represented by production of non-disposable atomic waste has been discussed. (author)

Rules specific to nuclear incidence occurring in installations or during transport of nuclear substances

International Nuclear Information System (INIS)

Rocamora, P.

1976-01-01

International nuclear third party liability conventions deal in depth with the liability system governing the transport of nuclear substances. Without appropriate legislation, international transport would be likely to meet very serious legal difficulties. The rule of nuclear conventions apply the same system to transport as to nuclear installations and mainly enable a determination of the operator liable. They also allow the person responsible for transport to assume liability therefor in place of the operator who whould normally have been liable. These nuclear conventions do not affect application of international transport conventions and this provision has been the cause of serious difficulties regarding maritime transport. This resulted in the adoption in 1971 in Brussels of a convention relating to civil liability in the field of maritime carriage of nuclear material. The purpose of this convention is to establish in the field of maritime transport, the priority of the system of absolute, exclusive and limited liability in the nuclear conventions. (NEA) [fr

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

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

Lessons of nuclear robot history

International Nuclear Information System (INIS)

Oomichi, Takeo

2014-01-01

Severe accidents occurred at Fukushima Daiichi Nuclear Power Station stirred up people's great expectation of nuclear robot's deployment. However unexpected nuclear disaster, especially rupture of reactor building caused by core meltdown and hydrogen explosion, made it quite difficult to introduce nuclear robot under high radiation environment to cease accidents and dispose damaged reactor. Robotics Society of Japan (RSJ) set up committee to look back upon lessons learned from 50 year's past experience of nuclear robot development and summarized 'Lessons of nuclear robot history', which was shown on the home page website of RSJ. This article outlined it with personal comment. History of nuclear robot developed for inspection and maintenance at normal operation and for specific required response at nuclear accidents was reviewed with many examples at home and abroad for TMI, Chernobyl and JCO accidents. Present state of Fukushima accident response robot's introduction and development was also described with some comments on nuclear robot development from academia based on lessons. (T. Tanaka)

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

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.

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.

Tokai earthquakes and Hamaoka Nuclear Power Station

International Nuclear Information System (INIS)

Komura, Hiroo

1981-01-01

Kanto district and Shizuoka Prefecture are designated as ''Observation strengthening districts'', where the possibility of earthquake occurrence is high. Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., is at the center of this district. Nuclear power stations are vulnerable to earthquakes, and if damages are caused by earthquakes in nuclear power plants, the most dreadful accidents may occur. The Chubu Electric Power Co. underestimates the possibility and scale of earthquakes and the estimate of damages, and has kept on talking that the rock bed of the power station site is strong, and there is not the fear of accidents. However the actual situation is totally different from this. The description about earthquakes and the rock bed in the application of the installation of No.3 plant was totally rewritten after two years safety examination, and the Ministry of International Trade and Industry approved the application in less than two weeks thereafter. The rock bed is geologically evaluated in this paper, and many doubtful points in the application are pointed out. In addition, there are eight active faults near the power station site. The aseismatic design of the Hamaoka Nuclear Power Station assumes the acceleration up to 400 gal, but it may not be enough. The Hamaoka Nuclear Power Station is intentionally neglected in the estimate of damages in Shizuoka Prefecture. (Kako, I.)

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

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.

Chemical effects of nuclear transformations symposium in Prague

Energy Technology Data Exchange (ETDEWEB)

NONE

1961-01-15

The Symposium on Chemical Effects of Nuclear Transformations showed that interest in the subject matter is far from being exclusively academic. Though a large number of the papers dealt with theoretical aspects, it was felt that hot atom reactions provided a valuable means by which a large number of radioactive isotopes and labelled compounds could be prepared practically free from their inactive counterparts. Such so-called carrier-free preparations are in great demand for industrial, medical and scientific applications. Discussions showed that a detailed knowledge o: the characteristics of radiation damage was essential to the successful development of nuclear power Nuclear transformations in solids provide a method of generating such damage and at the same time leave radioactive products that permit the study of the subsequent repair. This technique permits studies a' levels of damage much below those that are necessary with the less sensitive purely physical procedures. A number of papers emphasized the theoretical importance of the insight which hot atom chemistry gives into the mechanism of reactions occurring at abnormal temperatures.

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

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)

Survey of naturally occurring hazardous materials in deep geologic formations: a perspective on the relative hazard of deep burial of nuclear wastes

International Nuclear Information System (INIS)

Tonnessen, K.A.; Cohen, J.J.

1977-01-01

Hazards associated with deep burial of solidified nuclear waste are considered with reference to toxic elements in naturally occurring ore deposits. This problem is put into perspective by relating the hazard of a radioactive waste repository to that of naturally occurring geologic formations. The basis for comparison derives from a consideration of safe drinking water levels. Calculations for relative toxicity of FBR waste and light water reactor (LWR) waste in an underground repository are compared with the relative toxicity indices obtained for average concentration ore deposits. Results indicate that, over time, nuclear waste toxicity decreases to levels below those of naturally occurring hazardous materials

Cleanup and decommissioning of a nuclear reactor after a severe accident

International Nuclear Information System (INIS)

1992-01-01

Although the development of commercial nuclear power plants has in general been associated with an excellent record of nuclear safety, the possibility of a severe accident resulting in major fuel and core damage cannot be excluded and such accidents have in fact already occurred. For over a decade, IAEA publications have provided technical guidance and recommendations for post-accident planning to be considered by appropriate authorities. Guidance and recommendations have recently been published on the management of damaged nuclear fuel, sealing of the reactor building and related safety and performance assessment aspects. The present technical report on the cleanup and decommissioning of reactors which have undergone a severe accident represents a further publication in the series. Refs, figs and tabs.

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

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)

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

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)

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.

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)

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

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.)

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

Sensitivity Analysis of Core Damage by Loss of Auxiliary Feed Water during the Extended Loss of All AC Power

Energy Technology Data Exchange (ETDEWEB)

Jeon, Woo Jae; Chung, Soon Il; Hwang, Su Hyun; Lee, Kyung Jin; Lee, Byung Chul [FNC Tech., Yongin (Korea, Republic of); Yun, Duk Joo; Lee, Seung Chan [Korea Hydro and Nuclear Power Co. Ltd., Daejeon (Korea, Republic of)

2015-10-15

In this study, the reactor core damage time for OPR1000 type Nuclear Power Plant (NPP) was analyzed to develop a strategy to handle ELAP and to apply to the EOP. The reactor core damage time in the ELAP condition was calculated according to the time of Auxiliary Feedwater (AFW) loss. Fukushima accident was caused by long hours of Station Black Out (SBO) caused by natural disaster beyond Design Based Accident (DBA) criteria. It led to the reactor core damage. After the accident, the regulatory authorities of each country (Japan, US, EU, IAEA, and etc.) recommended developing the necessary systems and strategies in order to cover up the Extended Loss of All AC Power (ELAP) such as one occurred in the Fukushima accident. And the need of procedure or guideline to cope with ELAP has been raised through the stress test for Wolsong Nuclear Power Plant unit 1. Current Emergency Operating Procedures (EOP) used in domestic nuclear power plant are seemed to be insufficient to cope with ELAP. Therefore, it has been required to be improved. As the result, the time of AFW loss in the ELAP condition influences greatly on core damage time.

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)

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

Nuclear liability act and nuclear insurance

International Nuclear Information System (INIS)

Clarke, Roy G.; Goyette, R.; Mathers, C.W.; Germani, T.R.

1976-01-01

The Nuclear Liability Act, enacted in June 1970 and proclaimed effective October 11, 1976, is a federal law governing civil liability for nuclear damage in Canada incorporating many of the basic principles of the international conventions. Exceptions to operator liability for breach of duty imposed by the Act and duty of the operator as well as right of recourse, time limit on bringing actions, special measures for compensation and extent of territory over which the operator is liable are of particular interest. An operator must maintain $75,000,000. of insurance for each nuclear installation for which he is the operator. The Nuclear Insurance Association of Canada (NIAC) administers two ΣPoolsΣ or groups of insurance companies where each member participates for the percentage of the total limit on a net basis, one pool being for Physical Damage Insurance and the other for Liability Insurance. The Atomic Energy Control Board recommends to the Treasury Board the amount of insurance (basic) for each installation. Basic insurance required depends on the exposure and can range from $4 million for a fuel fabricator to $75 million for a power reactor. Coverage under the Operator's Policy provides for bodily injury, property damage and various other claims such as damage from certain transportation incidents as well as nuclear excursions. Workmen's Compensation will continue to be handled by the usual channels. (L.L.)

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)

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

In-pool damaged fuel bundle recovery

International Nuclear Information System (INIS)

Piascik, T.G.; Patenaude, R.S.

1988-01-01

While preparing to rerack the Oyster Creek Nuclear Generating Station, GPU Nuclear had need to move a damaged fuel bundle. This bundle had no upper tie plate and could not be moved in the normal manner. GPU Nuclear formed a small, dedicated project team to disassemble, package and move this damaged bundle. The team was composed of key personnel from GPU Nuclear Fuels Projects, OCNGS Operations and Proto-Power / Bisco, a specialty contractor who has fuel bundle reconstitution and rod consolidation experience, remote tooling, underwater video systems and experienced technicians. Proven tooling, clear procedures and a simple approach were important, but the key element was the spirit of teamwork and leadership exhibited by the people involved

Radiation damage of structural materials

International Nuclear Information System (INIS)

Koutsky, J.; Kocik, J.

1994-01-01

Maintaining the integrity of nuclear power plants (NPP) 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 reactor pressure vessels (RPV) and Zr-Nb alloys for fuel element cladding. The book is divided into seven main chapters, with the exception of the opening one and the chapter providing phenomenological background for the subject of radiation damage. Chapters 3-6 are devoted to RPV steels and chapters 7-9 to zirconium alloys, analyzing their radiation damage structure, changes of mechanical properties due to neutron irradiation as well as factors influencing the degree of their performance degradation. The recovery of damaged materials is also discussed. Considerable attention is paid to a comparison of VVER-type and western-type light-water materials

The deleterious effects of the nuclear crisis in Japan

International Nuclear Information System (INIS)

Marques, Paulo

2012-01-01

This work reports the severe nuclear incident occurred in Japan on March 11, 2011, due a earthquake followed by tsunami, where three of six existing reactors in Daiichi-Fukushima were damaged. The explosions with releasing of radioactive materials to environment have been discussed. It has shown the harmful effects of radiations to the exposed human being. Besides, the existence of the main impediment of the nuclear electric generation represented by production of non-disposable atomic waste has been discussed. (author)

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)

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)

Insurance and nuclear power

International Nuclear Information System (INIS)

Whipple, C.

1985-01-01

The Price-Anderson Act is discussed, which establishes procedures for insuring nuclear facilities (including nuclear power plants). The act was enacted with the dual purpose of protecting the public and encouraging the development of a private nuclear energy industry. Criticisms that can generally be grouped into four categories regarding the Act are presented, the most controversial aspect being that should an accident occur, the aggregate liability of the reactor operator, the NRC, or any others who might be at fault is limited to $560 million. Lawsuits for amounts in excess of $560 million are prohibited. The 1975 renewal of the Price-Anderson Act does provide that damages in excess of the $560 million prompt Congress to review the particular incident and take action to protect the public from the consequences of a disaster of such magnitude

What occurred in the reactors

International Nuclear Information System (INIS)

Kudo, Kazuhiko

2013-01-01

Described is what occurred in the reactors of Fukushima Daiichi Nuclear Power Plant at the Tohoku earthquake and tsunami (Mar. 11, 2011) from the aspect of engineering science. The tsunami attacked the Plant 1 hr after the quake. The Plant had reactors in buildings no.1-4 at 10 m height from the normal sea level which was flooded by 1.5-5.5 m high wave. All reactors in no.1-6 in the Plant were the boiling water type, and their core nuclear reactions were stopped within 3 sec due to the first quake by control rods inserted automatically. Reactors in no.1-5 lost their external AC power sources by the breakdown and subsequent submergence (no.1-4) of various equipments and in no.1, 2 and 4, the secondary DC power was then lost by the battery death. Although the isolation condenser started to cool the reactor in no.1 after DC cut, its valve was then kept closed to heat up the reactor, leading to the reaction of heated Zr in the fuel tube and water to yield H 2 which was accumulated in the building: the cause of hydrogen explosion on 12th. The reactor in no.2 had the reactor core isolation cooling system (RCIC) which operated normally for few hrs, then probably stopped to heat up the reactor, resulting in meltdown of the core but no explosion occurred because of the opened door of the blowout panel on the wall by the blast of no.1 explosion. The reactor in no.3 had RCIC and high pressure coolant injection system, but their works stopped to result in the core damage and H 2 accumulation leading to the explosion on 14th. The reactor in no.4 had not been operated because of its periodical annual examination, but was explored on 15th, of which cause was thought to be due to backward flow of H 2 from no.3. Finally, the author discusses about this accident from the industrial aspect of the design of safety level (defense in depth) on international views, and problems and tasks given. (T.T.)

Considering nuclear emergency preparedness from realities after Fukushima nuclear disaster

International Nuclear Information System (INIS)

Idokawa, Katsutaka

2013-01-01

As an ex-chief of affected town of Fukushima nuclear disaster, basic ideas were enumerated as no more accident occurring, necessity of early evacuation, all budget and right belonging to end administrator, appropriate response of government's emergency countermeasure headquarter on proposal of end administrator, failure of evacuation lead coming from government's information concealment, no more secondary damage of affected refuge, public disclosure of information, safety as the top priority with no compromise or preferred profit, new mechanism of resident's direct participation in preventing accidents, and fair review system of inspection based on checklist. Nuclear-related regulatory organizations and electric utilities should be reformed as open and transparent organization and responsible for following results of accidents. Public trust on government was completely lost after the Fukushima nuclear disaster and people should not rely on some organizations and be respective expert and foster self-defense capability so as to establish government by the people. (T. Tanaka)

Public international law and civil law liability for compensation for damages by virtue of international environmental law

International Nuclear Information System (INIS)

Rest, A.

1982-01-01

The author analyses the current provisions in international law and international private law for their suitability to establish liability for damages due to transfrontier pollution, also taking into account damage occurred through the operation of nuclear power plants. As a result the author suggests that the national goverments should jointly set up standards and catalogues of environmentally detrimental effects and impacts, and of the seriousness thereof, and to make these form part of international conventions and agreements which also should unambigiously state liability for compensation for damages. For activities involving special hazards, liability for risks should be introduced in such a body of international regulations. (CB) [de

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)

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.)

Accident at the Fukushima Dai-ichi Nuclear Power Stations of TEPCO —Outline & lessons learned—

OpenAIRE

TANAKA, Shun-ichi

2012-01-01

The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety o...

Detection of Fatigue Damage by Using High Frequency Nonlinear Laser Ultrasonic Signals

International Nuclear Information System (INIS)

Park, Seung Kyu; Park, Nak Kyu; Baik, Sung Hoon; Cheong, Yong Moo; Cha, Byung Heon

2012-01-01

The detection of fatigue damage for the components of a nuclear power plant is one of key techniques to prevent a catastrophic accident and the subsequent severe losses. Specifically, it is preferred to detect at an early stage of the fatigue damage. If the fatigue damage that is in danger of growing into a fracture is accurately detected, an appropriate treatment could be carried out to improve the condition. Although most engineers and designers take precautions against fatigue, some breakdowns of nuclear power plant components still occur due to fatigue damage. It is considered that ultrasound testing technique is the most promising method to detect the fatigue damage in many nondestructive testing methods. Laser ultrasound has attracted attention as a noncontact testing technique. Especially, laser ultrasonic signal has wide band frequency spectrum which can provide more accurate information for a testing material. The conventional linear ultrasonic technique is sensitive to gross defects or opened cracks whereas it is less sensitive to evenly distributed micro-cracks or degradation. An alternative technique to overcome this limitation is nonlinear ultrasound. The principal difference between linear and nonlinear technique is that in the latter the existence and characteristics of defects are often related to an acoustic signal whose frequency differs from that of the input signal. This is related to the radiation and propagation of finite amplitude, especially high power, ultrasound and its interaction with discontinuities, such as cracks, interfaces and voids. Since material failure or degradation is usually preceded by some kind of nonlinear mechanical behavior before significant plastic deformation or material damage occurs. The presence of nonlinear terms in the wave equation causes intense acoustic waves to generate new waves at frequencies which are multiples of the initial sound wave frequency. The nonlinear effect can exert a strong effect on the

A compilation of experiences of corrosion in Nordic nuclear power plants

International Nuclear Information System (INIS)

Norring, K.; Rosborg, B.

1985-01-01

14 reactors in commercial operation in the Nordic countries exhibit a great variety of corrosion induced damages. The largest number of such damages have affected turbine plants and seawater cooling systems. More severe cases of corrosion which have been experienced are intergranular stress corrosion cracking of steam generator tubing, stainless steel piping, and high strenght bolts and screws, together with erosion corrosion of structural steel in turbine plants. In all units in operation some form of corrosion damage has occurred. In a worldwide perspective the corrosion problems in the Nordic nuclear power plants have been of manageable extent

Detection of Fatigue Damage by Using Frequency Attenuation of a Laser Ultrasonic Longitudinal Wave

International Nuclear Information System (INIS)

Park, Seung-Kyu; Baik, Sung-Hoon; Jung, Hyun-Kyu; Joo, Young-Sang; Cha, Hyung-Ki; Kang, Young-June

2006-01-01

The measurement of fatigue damage in nuclear power plant components is very important to prevent a catastrophic accident and the subsequent severe losses. Specifically, it is preferred to detect at an early stage of the fatigue damage. If the fatigue damage that is in danger of growing into a fracture is accurately detected, an appropriate treatment could be carried out to improve the condition. Although most engineers and designers take precautions against fatigue, some breakdowns of nuclear power plant components still occur due to fatigue damage. It is considered that ultrasound testing technique is the most promising method to detect the fatigue damage in many nondestructive testing methods. Ultrasound testing method has a variety of elastic waves, such as a longitudinal wave, a shear wave, a surface wave and a lamb wave. Also we can use various analysis methods, such as a velocity variation and a signal attenuation. Laser ultrasonic testing has attracted attention as a non-contact testing technique. This system consists of a pulse laser to remotely generate ultrasound and a laser interferometer to remotely measure the surface displacement due to the generated ultrasound. This noncontact testing technique has the following advantages over the conventional piezoelectric transducers. Firstly, the inspection system can be remotely operated for a structure in hostile environments, such as in high radioactivity, high temperatures and narrow spaces. Secondly, we can obtain lots of information from the received ultrasonic waveforms because the laser ultrasonic technique does not require fluid couplant which disturbs the ultrasonic waveforms. Thirdly, laser ultrasound has a wideband spectrum and a high spatial resolution. Therefore, the laser ultrasound provides more accurate information for a testing material and has potential for the detection of fatigue damage in various metals composing a nuclear power plant

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

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

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

Natural Disaster as a Reason to Annul the Nuclear Liability: From National and International Law’s Perspective

International Nuclear Information System (INIS)

Taufiq, D.

2016-01-01

One serious issue that deserves more attention from Indonesia before constructing its first NPP, regarding its ''ring of fire'' geological position, is the natural disaster as a reason to annul the nuclear liability. Article 32 of Act No 10 Year 1997 on Nuclear Energy stipulates that ''nuclear installation operator shall not be responsible for the damage caused by a nuclear accident that occurred as a direct impact of a domestic or international armed conflict or natural disaster that exceeded the design limits and acceptance criteria set by the regulatory body.'' In its explanation natural disaster includes earthquakes. This article adopts the provision of article IV paragraph 3b 1963 Vienna Convention on Civil Liability for Nuclear Damage. But, in 1997 Amendment Protocol, this provision has been deleted. Natural disasters often referred to as an ''act of god'' because it occurs outside the control of the human. Nevertheless, not all natural disasters could cause the operator to annul its civil liability. The most important question is: ''has the operator taken all necessary preventive actions to prevent accidents, before and during the natural disaster?''

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)

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.)

Water hammer phenomena occurring in nuclear power installations while filling horizontal pipe containing saturated steam with liquid

Energy Technology Data Exchange (ETDEWEB)

Selivanov, Y.F.; Kirillov, P.L.; Yefanov, A.D. [Institute of Physics and Power Engineering, Obninsk (Russian Federation)

1995-09-01

The potentiality of the water hammer occurrence in nuclear reactor loop components has been considered under the conditions of filling a steam-containing pipeline leg involving horizontal and vertical sections with liquid subcooled to the saturation temperature. As a result of free discharging from the tank, the liquid enters the horizontal pipeline. When the liquid slug formation in the pipeline is fulfilled. The pressure drop being occurred in steam flowing along the pipelines causes the liquid slug to move to the pipeline inlet. When the liquid slug decelerates, a water hammer occurs. This mechanism of water hammer occurrence is tested by experiments. The regimes of the occurrence of multiple considerable water hammers were identified.

Water hammer phenomena occurring in nuclear power installations while filling horizontal pipe containing saturated steam with liquid

International Nuclear Information System (INIS)

Selivanov, Y.F.; Kirillov, P.L.; Yefanov, A.D.

1995-01-01

The potentiality of the water hammer occurrence in nuclear reactor loop components has been considered under the conditions of filling a steam-containing pipeline leg involving horizontal and vertical sections with liquid subcooled to the saturation temperature. As a result of free discharging from the tank, the liquid enters the horizontal pipeline. When the liquid slug formation in the pipeline is fulfilled. The pressure drop being occurred in steam flowing along the pipelines causes the liquid slug to move to the pipeline inlet. When the liquid slug decelerates, a water hammer occurs. This mechanism of water hammer occurrence is tested by experiments. The regimes of the occurrence of multiple considerable water hammers were identified

Radiation protection aspects of the repair work at Paks Nuclear Power Plant

International Nuclear Information System (INIS)

Bujtas, T.; Nenyei, A.

2006-01-01

On the Unit 2 at Paks Nuclear Power Plant accident occurred on 10th April 2003. Thirty fuel assemblies damaged in the cleaning tank installed in the Pit No. 1. Due to the accident casing of the fuel elements and uranium-dioxide pellets inside them damaged. The scratched fuel assemblies and nuclear fuel fragments should be removed and safely deposited. In order to restore the operational condition of the Pit No. 1 a lot of complicated activities with radiation hazard should be implemented. These tasks bring up both technical difficulties and serious radiation protection problems, and it is essential to resolve them in order to reduce radiation exposure of the working personnel and to minimize the amount of off-site radioactive releases.There was a serious incident (An INES level 3 event) at Paks Nuclear Power plant in april 10, 2003. (TRA)

Damage detection in high-rise buildings using damage-induced rotations

International Nuclear Information System (INIS)

Sung, Seung Hun; Jung, Ho Youn; Lee, Jung Hoon; Jung, Hyung Jo

2016-01-01

In this paper, a new damage-detection method based on structural vibration is proposed. The essence of the proposed method is the detection of abrupt changes in rotation. Damage-induced rotation (DIR), which is determined from the modal flexibility of the structure, initially occurs only at a specific damaged location. Therefore, damage can be localized by evaluating abrupt changes in rotation. We conducted numerical simulations of two damage scenarios using a 10-story cantilever-type building model. Measurement noise was also considered in the simulation. We compared the sensitivity of the proposed method to localize damage to that of two conventional modal-flexibility-based damage-detection methods, i.e., uniform load surface (ULS) and ULS curvature. The proposed method was able to localize damage in both damage scenarios for cantilever structures, but the conventional methods could not

Damage detection in high-rise buildings using damage-induced rotations

International Nuclear Information System (INIS)

Sung, Seung Hoon; Jung, Ho Youn; Lee, Jung Hoon; Jung, Hyung Jo

2014-01-01

In this paper, a new damage-detection method based on structural vibration is proposed. The essence of the proposed method is the detection of abrupt changes in rotation. Damage-induced rotation (DIR), which is determined from the modal flexibility of the structure, initially occurs only at a specific damaged location. Therefore, damage can be localized by evaluating abrupt changes in rotation. We conducted numerical simulations of two damage scenarios using a 10-story cantilever-type building model. Measurement noise was also considered in the simulation. We compared the sensitivity of the proposed method to localize damage to that of two conventional modal-flexibility-based damage-detection methods, i.e., uniform load surface (ULS) and ULS curvature. The proposed method was able to localize damage in both damage scenarios for cantilever structures, but the conventional methods could not.

DNA Damage Signals and Space Radiation Risk

Science.gov (United States)

Cucinotta, Francis A.

2011-01-01

Space radiation is comprised of high-energy and charge (HZE) nuclei and protons. The initial DNA damage from HZE nuclei is qualitatively different from X-rays or gamma rays due to the clustering of damage sites which increases their complexity. Clustering of DNA damage occurs on several scales. First there is clustering of single strand breaks (SSB), double strand breaks (DSB), and base damage within a few to several hundred base pairs (bp). A second form of damage clustering occurs on the scale of a few kbp where several DSB?s may be induced by single HZE nuclei. These forms of damage clusters do not occur at low to moderate doses of X-rays or gamma rays thus presenting new challenges to DNA repair systems. We review current knowledge of differences that occur in DNA repair pathways for different types of radiation and possible relationships to mutations, chromosomal aberrations and cancer risks.

The nuclear policy and the way to atomic weapons

International Nuclear Information System (INIS)

Rosa, L.P.

1985-01-01

The Brazilian Nuclear Policy that culminated with the polemical Brazil-West Germany Nuclear Agreement, in 1975, during the Geisel government, is one of the most evident and negative results of the military regime which was imposed to the nation during 21 years, from March 31, 1964 to March 15, 1985. This book presents the point of view of the author about the reasons that conducted to the bilateral agreement, the problems that occured during its execution, the possibility of damage to the environment, the so called 'parallel nuclear programme' developed by the army and the perspective of changes due to the 'New Republic' after 1985. (E.O.)

Questions of jurisdiction in the event of a nuclear accident in a member state of the European union

International Nuclear Information System (INIS)

Galizzi, P.

1996-01-01

Jurisdictional problems are outlined that could be encountered by victims of a serious nuclear accident, with transboundary consequences, seeking to recover compensation (in a Member State of the European Union). The situation is only partly covered by existing treaty law and not all Member States are a party to the relevant treaties. A hypothetical case-study has been devised which supposes that a nuclear accident has occurred in the Netherlands causing damage in three selected countries. Of these, the first (Germany) is a party to the 1960 Paris Convention on Third Party Liability in the field of Nuclear Energy, the second (Hungary) is a party to the 1963 Vienna Convention on Civil Liability for Nuclear Damage, and the third (Luxembourg) is a not a party to either Convention. Answers are sought for two questions related to this hypothetical accident. Firstly, which courts have jurisdiction over private claims for damage caused in these various countries? Secondly, which law will the competent courts apply? (UK)

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.

Repair of Clustered Damage and DNA Polymerase Iota.

Science.gov (United States)

Belousova, E A; Lavrik, O I

2015-08-01

Multiple DNA lesions occurring within one or two turns of the DNA helix known as clustered damage are a source of double-stranded DNA breaks, which represent a serious threat to the cells. Repair of clustered lesions is accomplished in several steps. If a clustered lesion contains oxidized bases, an individual DNA lesion is repaired by the base excision repair (BER) mechanism involving a specialized DNA polymerase after excising DNA damage. Here, we investigated DNA synthesis catalyzed by DNA polymerase iota using damaged DNA templates. Two types of DNA substrates were used as model DNAs: partial DNA duplexes containing breaks of different length, and DNA duplexes containing 5-formyluracil (5-foU) and uracil as a precursor of apurinic/apyrimidinic sites (AP) in opposite DNA strands. For the first time, we showed that DNA polymerase iota is able to catalyze DNA synthesis using partial DNA duplexes having breaks of different length as substrates. In addition, we found that DNA polymerase iota could catalyze DNA synthesis during repair of clustered damage via the BER system by using both undamaged and 5-foU-containing templates. We found that hPCNA (human proliferating cell nuclear antigen) increased efficacy of DNA synthesis catalyzed by DNA polymerase iota.

Effectiveness of Existing International Nuclear Liability Regime

Energy Technology Data Exchange (ETDEWEB)

Al-Doais, Salwa; Kessel, Daivd [KEPCO International Nuclear Graduate School, Daejeon (Korea, Republic of)

2015-10-15

The first convention was the Paris Convention on Third Party Liability in the Field of Nuclear Energy (the Paris Convention) had been adopted on 29 July 1960 under the auspices of the OECD, and entered into force on 1 April 1968. In 1963,the Brussels Convention - supplementary to the Paris Convention- was adopted in to provide additional funds to compensate damage as a result of a nuclear incident where Paris Convention funds proved to be insufficient. The IAEA's first convention was the Vienna Convention on Civil Liability for Nuclear Damage (the Vienna Convention) which adopted on 21 May 1963,and entered into force in 1977. Both the Paris Convention and the Vienna Convention laid down very similar nuclear liability rules based on the same general principles. The broad principles in these conventions can be summarized as follows: 1- The no-fault liability principle (strict liability) 2- Liability is channeled exclusively to the operator of the nuclear installation (legal channeling) 3- Only courts of the state in which the nuclear accident occurs would have jurisdiction (exclusive jurisdiction) 4- Limitation of the amount of liability and the time frame for claiming damages (limited liability) 5- The operator is required to have adequate insurance or financial guarantees to the extent of its liability amount (liability must be financially secured). 6- Liability is limited in time. Compensation rights are extinguished after specific time. 7- Non-discrimination of victims on the grounds of nationality, domicile or residence. Nuclear liability conventions objective is to provide adequate compensation payments to victims of a nuclear accident. Procedures for receiving these compensation are controlled by some rules such as exclusive jurisdiction, that rule need a further amendment to ensure the effectiveness of the exiting nuclear liability regime . Membership of the Conventions is a critical issue, because the existence of the conventions without being party to

Effectiveness of Existing International Nuclear Liability Regime

International Nuclear Information System (INIS)

Al-Doais, Salwa; Kessel, Daivd

2015-01-01

The first convention was the Paris Convention on Third Party Liability in the Field of Nuclear Energy (the Paris Convention) had been adopted on 29 July 1960 under the auspices of the OECD, and entered into force on 1 April 1968. In 1963,the Brussels Convention - supplementary to the Paris Convention- was adopted in to provide additional funds to compensate damage as a result of a nuclear incident where Paris Convention funds proved to be insufficient. The IAEA's first convention was the Vienna Convention on Civil Liability for Nuclear Damage (the Vienna Convention) which adopted on 21 May 1963,and entered into force in 1977. Both the Paris Convention and the Vienna Convention laid down very similar nuclear liability rules based on the same general principles. The broad principles in these conventions can be summarized as follows: 1- The no-fault liability principle (strict liability) 2- Liability is channeled exclusively to the operator of the nuclear installation (legal channeling) 3- Only courts of the state in which the nuclear accident occurs would have jurisdiction (exclusive jurisdiction) 4- Limitation of the amount of liability and the time frame for claiming damages (limited liability) 5- The operator is required to have adequate insurance or financial guarantees to the extent of its liability amount (liability must be financially secured). 6- Liability is limited in time. Compensation rights are extinguished after specific time. 7- Non-discrimination of victims on the grounds of nationality, domicile or residence. Nuclear liability conventions objective is to provide adequate compensation payments to victims of a nuclear accident. Procedures for receiving these compensation are controlled by some rules such as exclusive jurisdiction, that rule need a further amendment to ensure the effectiveness of the exiting nuclear liability regime . Membership of the Conventions is a critical issue, because the existence of the conventions without being party to

Radiation-damage calculations with NJOY

International Nuclear Information System (INIS)

MacFarlane, R.E.; Muir, D.W.; Mann, F.W.

1983-01-01

Atomic displacement, gas production, transmutation, and nuclear heating can all be calculated with the NJOY nuclear data processing system using evaluated data in ENDF/B format. Using NJOY helps assure consistency between damage cross sections and those used for transport, and NJOY provides convenient interface formats for linking data to application codes. Unique features of the damage calculation include a simple momentum balance treatment for radiative capture and a new model for (n, particle) reactions based on statistical model calculations. Sample results for iron and nickel are given and compared with the results of other methods

Measuring Public Acceptance of Nuclear Technology with Big data

Energy Technology Data Exchange (ETDEWEB)

Roh, Seugkook [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

Surveys can be conducted only on people in specific region and time interval, and it may be misleading to generalize the results to represent the attitude of the public. For example, opinions of a person living in metropolitan area, far from the dangers of nuclear reactors and enjoying cheap electricity produced by the reactors, and a person living in proximity of nuclear power plants, subject to tremendous damage should nuclear meltdown occur, certainly differs for the topic of nuclear generation. To conclude, big data is a useful tool to measure the public acceptance of nuclear technology efficiently (i.e., saves cost, time, and effort of measurement and analysis) and this research was able to provide a case for using big data to analyze public acceptance of nuclear technology. Finally, the analysis identified opinion leaders, which allows target-marketing when policy is executed.

Measuring Public Acceptance of Nuclear Technology with Big data

International Nuclear Information System (INIS)

Roh, Seugkook

2015-01-01

Surveys can be conducted only on people in specific region and time interval, and it may be misleading to generalize the results to represent the attitude of the public. For example, opinions of a person living in metropolitan area, far from the dangers of nuclear reactors and enjoying cheap electricity produced by the reactors, and a person living in proximity of nuclear power plants, subject to tremendous damage should nuclear meltdown occur, certainly differs for the topic of nuclear generation. To conclude, big data is a useful tool to measure the public acceptance of nuclear technology efficiently (i.e., saves cost, time, and effort of measurement and analysis) and this research was able to provide a case for using big data to analyze public acceptance of nuclear technology. Finally, the analysis identified opinion leaders, which allows target-marketing when policy is executed

Revised Paris and Vienna Nuclear Liability Conventions - Challenges for Nuclear Insurers

International Nuclear Information System (INIS)

Tetley, M.

2006-01-01

The revisions recently implemented to both the Vienna and Paris nuclear liability Conventions are intended to widen significantly the amount and scope of compensation payable in the event of a nuclear accident. Whilst this is a laudable objective, the final extent of the revisions leaves nuclear site operators and their insurers with greater uncertainty as a result of the wider and unquantifiable nature of some aspects of the revised nuclear damage definition, in particular where reference is made to environmental reinstatement and extended prescription periods. Incorporating broader definitions in the Convention revisions will therefore leave gaps in the insurance cover where insurers are unable to insure the new, wider scope of cover. If no insurance is available, then the liability for the revised scope of cover must fall upon either the operator or the national Government. This presentation will give an overview of where and why the major gaps in nuclear liability insurance cover will occur in the revised Conventions; it will also examine the problems in defining the revised scope of cover and will look at where these unquantifiable risks should now reside, to ensure there is equity between the liabilities imposed on the nuclear industry and those imposed on other industrial sectors. (author)

Pressure waves transient occurred in the steam generators feedwater lines of the Atucha-1 Nuclear Power Plant

International Nuclear Information System (INIS)

Balino, J.L.; Carrica, P.M.; Larreteguy, A.E.

1993-01-01

The pressure transient occurred at Atucha I Nuclear Power Plant in March 1990 is simulated. The transient was due to the fast closure of a flow control valve at the steam generators feedwater lines. The system was modelled, including the actuation of the relief valves. The minimum closure time for no actuation of the relief valves and the evolution of the velocity and piezo metric head for different cases were calculated. (author)

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)

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

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

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)

What the public want in nuclear use

International Nuclear Information System (INIS)

Tsuchida, Shoji

2013-01-01

This article described public opinion poll by the web in October 2011 and considered human behavior facing a danger to understand silent majority's opinion change and what safety was required from the public. Web's social investigation showed (1) opposition to nuclear power with great anxiety (no admission and necessity of nuclear power was strong enough at east Japan (Tohoku, Niigata and Tokyo area)), (2) trust on electric utilities and government was lost and accident was thought manmade, and (3) as for radioactivity contamination, residents at east Japan were more acceptable than at west Japan (Osaka and Kyushu) (radiation hazards were scientifically better understood at east Japan). Human behavior facing a danger such as accident or natural disaster could be predicted by two factors: controllability and extend of damage. If recognized as controllable and damage was slightly greater than threshold, cost vs. benefit action or rational response might be taken. If recognized as controllable and damage were far beyond threshold, psychological excessive reaction would be taken. If recognized not controllable, apathy, patience and resignation would prevail dependent on extent of damage evaluation. Also 'confidence bias' would occur at facing a danger. Results of web poll and public opinion of silent majority were analyzed from these psychological aspect of human mind facing a danger. After the Fukushima accident, the public might require appropriate measures to assure (1) security not to allow the accident, (2) safety to minimize accident damage and (3) resilience for efficient and swift restoration from the damage. (T. Tanaka)

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

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

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

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.)

Third party nuclear liability regime in the Romanian legislation - current status

International Nuclear Information System (INIS)

Chirica, T.; Chiripus, V.

2004-01-01

The regime of civil liability for nuclear damages in the Romanian legislation is defined by Law no. 703/2001 on civil liability for nuclear damages, as well as 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 aims at presenting to the audience the main elements of the relatively recent legal framework, namely: the scope of Law no. 703/2001, as well as the subjects to whom such law applies, the regime of civil liability for nuclear damages in Romania (with special emphasis on the relevant responsibilities of nuclear operators), the Romanian nuclear damages compensation system, statute of limitation for claims, types of insurance and financial guarantees covering against 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.(author)

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

In-pool damaged fuel bundle recovery

International Nuclear Information System (INIS)

Piascik, T.G.; Patenaude, R.S.

1988-01-01

While preparing to rerack the Oyster Creek Nuclear Generating Station, GPU Nuclear had need to move a damaged fuel bundle. This bundle had no upper tie plate and could not be moved in the normal manner. GPU Nuclear formed a small, dedicated project team to disassemble, package, and move this damaged bundle. The team was composed of key personnel from GPU Nuclear Fuels Projects, OCNGS Operations and Proto-Power/Bisco, a specialty contractor who has fuel bundle reconstitution and rod consolidation experience, remote tooling, underwater video systems and experienced technicians. Proven tooling, clear procedures and a simple approach were important, but the key element was the spirit of teamwork and leadership exhibited by the people involved. In spite of several emergent problems which a task of this nature presents, this small, close knit utility/vendor team completed the work on schedule and within the exposure and cost budgets

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....

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

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

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

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)

A study on the international cooperation in the nuclear liability system related to the supply of nuclear power plants to North Korea

Energy Technology Data Exchange (ETDEWEB)

Ham, Chul Hoon.; Kim, Tae Myeong [The Catholic University, Seoul (Korea)

2001-12-01

System of nuclear damage compensation was prepares to protect the interested parties in the implementation of nuclearenterprise and conciliate the conflicts of interests of them. The Light-water Reactor (LWR) Project to supply two units of light-water reactors to North Korea faced difficulties concerning nuclear damage compensation system due to decline of the international reliability and aggravation of economic condition of North Korea. It is necessary to study the special nuclear damage compensation system of the LWR Project to promote the Project and peaceful uses of atomic energy in northeast Asia. The contents and scope of the study is composed as follows; 1. Background of the LWR Project . the pending issues of them and the necessary of the special nuclear damage compensation system 2. Investigation of nuclear damage compensation system of United States, Japan, German, France and Korea 3. Account of conventions on liability for nuclear damage, especially Vienna Convention and its Protocols 4. Searching for issues of the nuclear damage compensation system of the LWR Project and its resolution 5. Comprehensive arrangement on the main issues through the study. 4 tabs. (Author)

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)

Track structure model for damage to mammalian cell cultures during solar proton events

Science.gov (United States)

Cucinotta, F. A.; Wilson, J. W.; Townsend, L. W.; Shinn, J. L.; Katz, R.

1992-01-01

Solar proton events (SPEs) occur infrequently and unpredictably, thus representing a potential hazard to interplanetary space missions. Biological damage from SPEs will be produced principally through secondary electron production in tissue, including important contributions due to delta rays from nuclear reaction products. We review methods for estimating the biological effectiveness of SPEs using a high energy proton model and the parametric cellular track model. Results of the model are presented for several of the historically largest flares using typical levels and body shielding.

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

A list of abnormal occurences at Swedish nuclear power stations

International Nuclear Information System (INIS)

McHugh, B.

1974-08-01

This report consists of a list of extracts from documents belonging to Statens Kaernkraftinspektion (SKI) in Sweden. It deals with non-routine occurrences at the Swedish nuclear power stations which are in operation or where test operations of components and systems have started. The investigation has included matter about the following nuclear power plants: Barsebaeck-1, Oskarshamn-1, Oskarshamn-2, Ringhals-1, Ringhals-2, Aagesta. In all cases from the start of the test operations up to latest the 1st of June 1974. (M.S.)

The energy overcompensating disintegrations of residual target nuclei damaged in hadron-nucleus collisions

International Nuclear Information System (INIS)

Strugalski, Z.

1995-01-01

Massive target nuclei damaged in hadron-nucleus collisions at high energies are used to disintegrate into nuclear fragments. In many cases such breakup is egzoergic - some portion of nuclear energy is released; this portion should be overcompensating the energy used for the nuclear damage, in some cases. 30 refs

To What Extent International Law Constitutes an Appropriate Answer to Nuclear Accidents?

International Nuclear Information System (INIS)

Durand-Poudret, E.

2015-01-01

Regulating high risks activities has always been an ambitious task as the regime shall both prevent and compensate the potential damage of such activities. It becomes even more complex with nuclear energy as radioactivity possesses this transboundary character which implies an international cooperation. The need for an appropriate framework for nuclear energy started to raise in the 60s, when States realise that the classic liability system was not relevant for that kind of activity. The Paris and Vienna conventions were subsequently adopted in order to fill this legal gap. Nonetheless, the real turning point remains the Chernobyl accident which resulted in a considerable number of new international instruments as 5 conventions were adopted in the fields of safety and emergency preparedness within a 11 years period: the Convention on Early Notification of a Nuclear Accident, the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency, the Convention on Nuclear Safety, the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management and the Convention on Supplementary Compensation for Nuclear Damage. This catastrophe was also the occasion to identify and mitigate the shortcomings of the existing regime in undertaking a revision process through several supplementary protocols, the Joint Protocol Relating to the Application of the Vienna Convention and the Paris Convention, the Protocol to Amend the Vienna Convention on Civil Liability for Nuclear Damage. 25 years after Chernobyl, another tragic nuclear event occurred in Fukushima. Once again it challenged the efficiency of the existing international regime and raises the question as to whether international law represents a relevant solution to such accident. (author)

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

Quantitative analysis of gene-specific DNA damage in human spermatozoa

International Nuclear Information System (INIS)

Sawyer, Dennis E.; Mercer, Belinda G.; Wiklendt, Agnieszka M.; Aitken, R. John

2003-01-01

Recent studies have suggested that human spermatozoa are highly susceptible to DNA damage induced by oxidative stress. However, a detailed analysis of the precise nature of this damage and the extent to which it affects the mitochondrial and nuclear genomes has not been reported. To induce DNA damage, human spermatozoa were treated in vitro with hydrogen peroxide (H 2 O 2 ; 0-5 mM) or iron (as Fe(II)SO 4 , 0-500 μM). Quantitative PCR (QPCR) was used to measure DNA damage in individual nuclear genes (hprt, β-pol and β-globin) and mitochondrial DNA. Single strand breaks were also assessed by alkaline gel electrophoresis. H 2 O 2 was found to be genotoxic toward spermatozoa at concentrations as high as 1.25 mM, but DNA damage was not detected in these cells with lower concentrations of H 2 O 2 . The mitochondrial genome of human spermatozoa was significantly (P 2 O 2 -induced DNA damage than the nuclear genome. However, both nDNA and mtDNA in human spermatozoa were significantly (P<0.001) more resistant to damage than DNA from a variety of cell lines of germ cell and myoblastoid origin. Interestingly, significant DNA damage was also not detected in human spermatozoa treated with iron. These studies report, for the first time, quantitative measurements of DNA damage in specific genes of male germ cells, and challenge the commonly held belief that human spermatozoa are particularly vulnerable to DNA damage

Characteristics of severely damaged fuel from PBF tests and the TMI-2 accident

International Nuclear Information System (INIS)

Osetek, D.J.; Cook, B.A.; Dallman, R.J.; Broughton, J.M.

1986-01-01

As a result of the TMI-2 reactor accident, the US Nuclear Regulatory Commission initiated a research program to investigate phenomena associated with severe fuel damage accidents. This program is sponsored by several countries and includes in-pile and out-of-pile experiments, separate effects studies, and computer code development. The principal in-pile testing portion of the program includes four integral severe fuel damage (SFD) tests in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory (INEL). The INEL is also responsible for examining the damaged core in the Three Mile Island-Unit 2 (TMI-2) reactor, which offers the unique opportunity to directly compare the findings of an experimental program to those of an actual reactor accident. The principal core damage phenomena which can occur during a severe accident are discussed, and examples from the INEL research programs are used to illustrate the characteristics of these phenomena. The preliminary results of the programs are presented, and their impact on plant operability during severe accidents is discussed

A rigorous treatment of uncertainty quantification for Silicon damage metrics

International Nuclear Information System (INIS)

Griffin, P.

2016-01-01

These report summaries the contributions made by Sandia National Laboratories in support of the International Atomic Energy Agency (IAEA) Nuclear Data Section (NDS) Technical Meeting (TM) on Nuclear Reaction Data and Uncertainties for Radiation Damage. This work focused on a rigorous treatment of the uncertainties affecting the characterization of the displacement damage seen in silicon semiconductors. (author)

The effect of higher order chromatin structure on DNA damage and repair

International Nuclear Information System (INIS)

Yasui, L.S.; Warters, R.L.; Higashikubo, R.

1985-01-01

Alterations in chromatin structure are thought to play an important role in various radiobiological end points, i.e., DNA damage, DNA damage repair and cell survival. The authors use here the isoleucine deprivation technique to decondense higher order chromatin structure and asses X-ray induced DNA damage, DNA damage repair and cell survival on cells with decondensed chromatin as compared to controls. This chromatin decondensation manifests itself as a 30 fold decrease in nuclear area occupied by heterochromatin, an increased rate of Micrococcal nuclease digestion, 15% increased ethidium bromide intercalation and an altered binding capacity of Hl histone. These chromatin/nuclear changes do not affect X-ray induced DNA damage as measured by the alkaline elution technique or cell survival but slows DNA damage repair by 2 fold. Therefore, even though the chromatin appears more accessible to DNA damage and repair processes, these particular nuclear changes do not affect the DNA damaging effects of X-rays and in addition, repair is not enhanced by the ''relaxed'' state of chromatin. It is proposed that the altered metabolic state of isoleucine deprived cells provides a less efficient system for the repair of X-ray induced DNA damage

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)

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

Unintentional exposure to radiation during pregnancy from nuclear medical diagnostic procedures

International Nuclear Information System (INIS)

Moka, D.

2005-01-01

The administration of radiopharmaceuticals during pregnancy is contraindicated due to a lack of vital indications. However, if prenatal exposure to radiation should occur in the framework of a nuclear medical diagnostic procedure then fortunately no longterm side-effects would normally be expected. Radiation damage in the preimplantation phase leads to early abortion. However, if the further course of pregnancy remains uncomplicated then no subsequent side-effects need be expected. On a conservative estimate, it would require doses exceeding 50 mGy to cause radiation damage within the uterus after the preimplantation phase. However, the standard radioactivities applied for diagnostic purposes in nuclear medicine, can be obtained with doses of less than 20 mGy. On the basis of current knowledge, therefore, there is no reason to terminate pregnancy on medical grounds after diagnostic exposure to radiopharmaceuticals. (orig.)

Abnormality diagnostic technology for nuclear power plants

International Nuclear Information System (INIS)

Ishikawa, Satoshi

1986-01-01

In nuclear power plants, it is feared that the failure of the installations containing radioactive substances may inflict serious damage on public and workers. Therefore in nuclear power plants, the ensuring of safety is planned by supposing hypothetical accidents which are not likely to occur from engineering viewpoint, and multiple protection measures are taken in the plant constitution. In addition to the safety measures from such hardware aspect, recently in order to prevent the occurrence of accidents by using various safety-confirming means, and to detect early when any accident occurred, the development and putting in practical use of many monitoring equipments have been promoted. In such background, the development of nuclear power generation supporting system was carried out for five years since fiscal year 1980, subsidized by the Ministry of International Trade and Industry, and in this report, the technology of equipment abnormality diagnosis developed as a part of that project and the diagnostic techniques for actual plants are described. The technology of diagnosing nuclear reactor abnormality includes the diagnosis of loose metal pieces and the abnormal vibration of in-core structures. The detection and diagnosis of valve leak and the diagnosis of the deterioration of detectors are also explained. (Kako, I.)

The United States should forego a damage-limitation capability against China

Science.gov (United States)

Glaser, Charles L.

2017-11-01

Bottom Lines • THE KEY STRATEGIC NUCLEAR CHOICE. Whether to attempt to preserve its damage-limitation capability against China is the key strategic nuclear choice facing the United States. The answer is much less clear-cut than when the United States faced the Soviet Union during the Cold War. • FEASIBILITY OF DAMAGE LIMITATION. Although technology has advanced significantly over the past three decades, future military competition between the U.S. and Chinese forces will favor large-scale nuclear retaliation over significant damage limitation. • BENEFITS AND RISKS OF A DAMAGE-LIMITATION CAPABILITY. The benefits provided by a modest damage-limitation capability would be small, because the United States can meet its most important regional deterrent requirements without one. In comparison, the risks, which include an increased probability of accidental and unauthorized Chinese attacks, as well as strained U.S.—China relations, would be large. • FOREGO DAMAGE LIMITATION. These twin findings—the poor prospects for prevailing in the military competition, and the small benefits and likely overall decrease in U.S. security—call for a U.S. policy that foregoes efforts to preserve or enhance its damage-limitation capability.

Six Decades of Nuclear Accidents, Nuclear Compensation, and Issues of Radioactive Waste Management

International Nuclear Information System (INIS)

Boonsuwan, P.; Songjakkeaw, A.

2011-11-01

Thailand has made a serious aim to employ nuclear power by adopting five 1,000 MWt in the 2010 national Power Development Plan (PDP 2010) with the first NPP coming online in 2020. However, after the Fukushima nuclear disaster in March 2011, the National Energy Policy Committee had made the resolution to postpone the plan by 3 years. The post-Fukushima atmosphere does not bode well for the public sentiment towards the proposed programme, especially with regards to safety of an NPP. Nonetheless, during the six decades that NPPs have been in operation in 32 countries worldwide, there are only 19 serious accidents involving fatalities and/or damage to properties in excess of 100 million USD. Out of the three significant accidents - Fukushima nuclear accident (2011), Chernobyl nuclear accident (1986), and Three Miles Island nuclear accident (1979) - only the accident at Three Miles Island occurs during normal operation. Such can be implied that the operation of NPPs does maintain a high level of safety. The current technology on nuclear safety has been advancing greatly to the point that the new NPP design claims to render the possibility of a severe accident resulting in core melting insignificant. Along with the technical improvements, laws and regulations have also be progressing in parallel to adequately compensate and limit the liability of operators in case of a nuclear accident. The international agreements such as the Vienna Convention on Civil Liability for Nuclear Damage and the Convention of the Third Party Liability in the Field of Nuclear Energy had also been established and also the national laws of countries such as the United States and Japan have been implemented to address such issues to the point that victims of a nuclear accidents are adequately and justly compensated. In addition to the issues of nuclear accident, the dilemma in nuclear waste management, especially with regards to the High Level Waste which is highly radioactive while having very

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

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

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.

Power Burst Facility severe-fuel-damage test program

International Nuclear Information System (INIS)

McCardell, R.K.; MacDonald, P.E.

1982-01-01

As a result of the Three Mile Island Unit 2 (TMI-2) accident, the United States Nuclear Regulatory Commission (USNRC) has initiated a severe fuel damage research program to investigate fuel rod and core response, and fission product and hydrogen release and transport during degraded core cooling accidents. This paper presents a discussion of the expected benefits of the PBF severe fuel damage tests to the nuclear industry, a description of the first five planned experiments, the results of pretest analysis performed to predict the fuel bundle heatup for the first two experiments, and a discussion of Phase II severe fuel damage experiments. Modifications to the fission product detection system envisioned for the later experiments are also described

Nuclear power investment risk economic model

International Nuclear Information System (INIS)

Houghton, W.J.; Postula, F.D.

1985-12-01

This paper describes an economic model which was developed to evaluate the net costs incurred by a utility due to an accident induced outage at a nuclear power plant. During such an outage the portion of the plant operating costs associated with power production are saved; however, the owning utility faces a sizable expense as fossil fuels are burned as a substitute for the incapacitated nuclear power. Additional expenses are incurred by the utility for plant repair and if necessary, decontamination costs. The model makes provision for mitigating these costs by sales of power, property damage insurance payments, tax write-offs and increased rates. Over 60 economic variables contribute to the net cost uncertainty. The values of these variables are treated as uncertainty distributions and are used in a Monte carlo computer program to evaluate the cost uncertainty (investment risk) associated with damage which could occur from various categories of initiating accidents. As an example, results of computations for various levels of damage associated with a loss of coolant accident are shown as a range of consequential plant downtime and unrecovered cost. A typical investment risk profile is shown for these types of accidents. Cost/revenue values for each economic factor are presented for a Three Mile Island - II type accident, e.g., uncontrolled core heatup. 4 refs., 6 figs., 3 tabs

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

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)

Nuclear polyhedrosis virus as a biological control agent for Malacosoma americanum (Lepidoptera: Lasiocampidae)

Science.gov (United States)

R.A. Progar; M.J. Rinella; D. Fekedulegn; L. Butler

2010-01-01

In addition to damaging trees, the eastern tent caterpillar is implicated in early fetal loss and late-term abortion in horses. In a field study, we evaluated the potential biological control of the caterpillar using eastern tent caterpillar nuclear polyhedrosis virus (ETNPV), a naturally occurring virus that is nearly species-specific. Egg masses were hatched and...

Damage Assessment Technologies for Prognostics and Proactive Management of Materials Degradation (PMMD)

International Nuclear Information System (INIS)

Bond, Leonard J.; Doctor, Steven R.; Griffin, Jeffrey W.; Hull, Amy B.; Malik, Shah

2009-01-01

There are approximately 440 operating reactors in the global nuclear power plant (NPP) fleet with an average age greater than 20 years and design lives of 30 or 40 years. The United States is currently implementing license extensions of 20 years on many plants, and consideration is now being given to the concept of 'life-beyond-60', license extension from 60 to 80 years and potentially longer. In almost all countries with NPPs, authorities are looking at some form of license renewal program. In support of NPP license renewal over the past decade, various national and international programs have been initiated. This paper discusses stressor-based prognostics and its role as part of emerging trends in Proactive Management of Materials Degradation (PMMD) applied to nuclear power plant structures, systems and components (SSC). The paper concisely explains the US Nuclear Regulatory Commission's (NRC) program in PMMD, the basic principles of PMMD and its relationship to advanced diagnostics and prognostics. It then provides an assessment of the state of maturity for diagnostic and prognostic technologies, including NDE and related technologies for damage assessment, and the current trend to move from condition-based maintenance to on-line monitoring for advanced diagnostics and stressor-based prognostics. This development in technology requires advances in sensors; better understanding of what and how to measure within a nuclear power plant; enhanced data interrogation, communication and integration; new prediction models for damage/aging evolution; system integration for real-world deployments and quantification of uncertainties in what are inherently ill-posed problems. Stressor-based analysis is based upon understanding which stressor characteristics (e.g., pressure transients) provide a percussive indication that can be used for mapping subsequent damage due to a specific degradation mechanism. The resulting physical damage and the associated decrease in asset

Risk assessment of natural disasters in the course of selection of nuclear waste disposal

International Nuclear Information System (INIS)

Wu Weicheng; Ai Guigen

1995-01-01

Natural disasters are calamities which bring about enormous damage to human beings and their accommodations and equipment. Based on the research of disaster risk and example study of volcanism, we tried to carry out the risk assessment of natural disasters which potentially occur in the candidate area of nuclear waste disposal by three steps of analyses, defining the most frequent occurring area of disasters, determining the parameters of risk assessment and dividing the most dangerous site and risk grades

Ab initio and Molecular Dynamic models of displacement damage in crystalline and turbostratic graphite

Science.gov (United States)

McKenna, Alice

One of the functions of graphite is as a moderator in several nuclear reactor designs, including the Advanced Gas-cooled Reactor (AGR). In the reactor graphite is used to thermalise the neutrons produced in the fission reaction thus allowing a self-sustained reaction to occur. The graphite blocks, acting as the moderator, are constantly irradiated and consequently suffer damage. This thesis examines the types of damage caused using molecular dynamic (MD) simulations and ab intio calculations. Neutron damage starts with a primary knock-on atom (PKA), which is travelling so fast that it creates damage through electronic and thermal excitation (this is addressed with thermal spike simulations). When the PKA has lost energy the subsequent cascade is based on ballistic atomic displacement. These two types of simulations were performed on single crystal graphite and other carbon structures such as diamond and amorphous carbon as a comparison. The thermal spike in single crystal graphite produced results which varied from no defects to a small number of permanent defects in the structure. It is only at the high energy range that more damage is seen but these energies are less likely to occur in the nuclear reactor. The thermal spike does not create damage but it is possible that it can heal damaged sections of the graphite, which can be demonstrated with the motion of the defects when a thermal spike is applied. The cascade simulations create more damage than the thermal spike even though less energy is applied to the system. A new damage function is found with a threshold region that varies with the square root of energy in excess of the energy threshold. This is further broken down in to contributions from primary and subsequent knock-on atoms. The threshold displacement energy (TDE) is found to be Ed=25eV at 300K. In both these types of simulation graphite acts very differently to the other carbon structures. There are two types of polycrystalline graphite structures

Estimation of radiation exposed area by the nuclear accident occurred at Tokai village using ESR measurements of household sugar

International Nuclear Information System (INIS)

Kuzuya, Masayuki; Kondo, Shinichi; Ito, Kousuke; Sawa, Takashi

2001-01-01

The area of radiation exposure by the nuclear accident occurred at Tokai village in 1999 was estimated by the ESR measurement of 95 household sugar samples collected from the accident area. These samples were roughly classified into three types of sugar, fine white sugar, fine brown sugar and coarse brown sugar. The control fine white sugar showed no radical in the ESR spectrum, while those of fine brown sugar and coarse brown sugar showed the presence of a small amount of radicals. It was also shown that, among these three kinds of sugar, the radical concentration of fine white sugar sampled from wooden houses at the area similar to each other did not vary much with the samples, while those of fine brown sugar and coarse brown sugar varied to a considerable extent. Thus, the fine white sugar is considered to be more suitable for the estimation of the level of radiation exposure. The radical concentration of each fine white sugar sample was plotted against the distance from the site of the nuclear accident with a correction of the difference in the shielding effect between concrete houses and wooden houses. The samples obtained at more than 2 km north of the site of nuclear accident showed no ESR spectral signal to a detectable extent. On the other hand, the ESR spectra were observed from the samples obtained within 10 km south and 4 km west of the accident site. These results suggest that the radiation exposure by the contaminant blown by the northeast wind blowing on the day of the accident may occur at the south and west areas. (author)

Reactor shutdown: nuclear power plant performance

International Nuclear Information System (INIS)

Anon.

1982-01-01

The article essentially looks at the performance of nine of Sweden's nuclear reactors. A table lists the percentage of time for the first three quarters of 1981 that the reactors were operating, and the number of hours out of service for planned or other reasons. In particular, one station - Ringhals 3 - was out of action because of a damaged tube in the associated steam generator. The same fault occurred with another reactor - Ringhals 4 - before this was brought into service. The reasons for the failure and its importance are briefly discussed. (G.P.)

Frequency of damage by external explosion hazards based on geographical information

International Nuclear Information System (INIS)

Becker, Guenter; Camarinopoulos, Alexis; Theodora, Karali; Camarinopoulos, Leonidas; Schubert, B.

2013-01-01

External explosions can significantly contribute to risk of damage for industrial plants. External explosions may origin from other plants in the neighbourhood, which store and operate with explosive substances, or from transport of such substances on road, rail, or water. If deflagration is involved, ignition will not necessarily occur at the place of the accident, but a cloud of a combustible gas-air mixture may develop, which will ignite at some distance depending on wind velocity. A probabilistic model has been developed to calculate frequencies of damage based on numerical integration or on Monte Carlo simulation. Geographical information systems provide map material for sites, roads, rail and rivers on a computer. Data has been collected and applied for a nuclear power plant in Germany as an example. The method, however, can be used for any type of plant subject to external explosion hazards. (orig.)

Frequency of damage by external explosion hazards based on geographical information

Energy Technology Data Exchange (ETDEWEB)

Becker, Guenter [Risa Sicherheitsanalysen GmbH, Berlin-Charlottenburg (Germany); Camarinopoulos, Alexis; Theodora, Karali [Environment Reliability and Risk Analysis (ERRA), Athens (Greece); Camarinopoulos, Leonidas [Piraeus Univ. (Greece); Schubert, B. [VENE, Hamburg (Germany)

2013-05-15

External explosions can significantly contribute to risk of damage for industrial plants. External explosions may origin from other plants in the neighbourhood, which store and operate with explosive substances, or from transport of such substances on road, rail, or water. If deflagration is involved, ignition will not necessarily occur at the place of the accident, but a cloud of a combustible gas-air mixture may develop, which will ignite at some distance depending on wind velocity. A probabilistic model has been developed to calculate frequencies of damage based on numerical integration or on Monte Carlo simulation. Geographical information systems provide map material for sites, roads, rail and rivers on a computer. Data has been collected and applied for a nuclear power plant in Germany as an example. The method, however, can be used for any type of plant subject to external explosion hazards. (orig.)

Radiation damage effects in solids special topic volume with invited peer reviewed papers only

CERN Document Server

Virk, Hardev Singh

2013-01-01

Public interest and concern about radiation damage effects has increased during recent times. Nuclear radiation proved to be a precursor for the study of radiation damage effects in solids. In general, all types of radiation, e.g. X-ray, gamma ray, heavy ions, fission fragments and neutrons produce damage effects in materials. Radiation damage latent tracks in solids find applications in nuclear and elementary particle physics, chemistry, radiobiology, earth sciences, nuclear engineering, and a host of other areas such as nuclear safeguards, virus counting, ion track filters, uranium exploration and archaeology. Radiation dosimetry and reactor shielding also involve concepts based on radiation damage in solids. This special volume consists of ten Chapters, including Review and Research Papers on various topics in this field.Physical scientists known to be investigating the effects of radiation on material were invited to contribute research and review papers on the areas of their specialty. The topics include...

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.

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

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

Analysis of the phenomena associated with structural damage using real time vibration analysis

International Nuclear Information System (INIS)

Garcia Peyrano, O; Cismondi, L; Damiani, H; Torres, E

2004-01-01

It is of interest to have analytical methodologies available for the dynamic behavior of large mechanical structures like those in thermal cycle systems of nuclear power plants or in transport systems during the experimental stage prior to their construction, as happens in aeronautics, where prototypes are tested in experimental banks on a scale of 1 to 1. The same does not occur with systems for the generation of electrical energy such as a nuclear power plant or in ships, competition automobiles, railway systems, etc. Not because of the technical impossibility but because of the high costs involved. This work aims to implement a technology based on the analysis of the vibrations to obtain a profile of the modal dynamic response and its influence on the critical components of the mechanisms with the particularity of detecting the preventive location of the component that may suffer a potential damage. The Vibrations Analysis Laboratory has resolved different cases in the Embalse Nuclear Plant, in the Atucha Nuclear Plant, in the Heavy Water Industrial Plant, in the automobile industry and in other industrial areas (CW)

Regulation of naturally occurring radioactive materials in non-nuclear industries

International Nuclear Information System (INIS)

Scott, L.M.

1997-01-01

The volume and concentrations of naturally occurring radioactive material is large across a variety of industries commonly thought not to involve radioactive material. The regulation of naturally occurring radioactive material in the United States is in a state of flux. Inventory of naturally occurring radioactive materials is given, along with a range of concentrations. Current and proposed regulatory limits are presented. (author)

Corrosion engineering in nuclear power industry

International Nuclear Information System (INIS)

Prazak, M.; Tlamsa, J.; Jirousova, D.; Silber, K.

1990-01-01

Corrosion problems in nuclear power industry are discussed from the point of view of anticorrosion measures, whose aim is not only increasing the lifetime of the equipment but, first of all, securing ecological safety. A brief description is given of causes of corrosion damage that occurred at Czechoslovak nuclear power plants and which could have been prevented. These involve the corrosion of large-volume radioactive waste tanks made of the CSN 17247 steel and of waste piping of an ion exchange station made of the same material, a crack in a steam generator collector, contamination of primary circuit water with iron, and corrosion of CrNi corrosion-resistant steel in a spent fuel store. It is concluded that if a sufficient insight into the corrosion relationships exists and a reasonable volume of data is available concerning the corrosion state during the nuclear facility performance, the required safety can be achieved without adopting extremely costly anticorrosion measures. (Z.M.)

Field damage of sorghum (Sorghum bicolor) with reduced lignin levels by naturally occurring insect pests and pathogens

Science.gov (United States)

Mutant lines of sorghum with low levels of lignin are potentially useful for bioenergy production, but may have problems with insects or disease. Field grown normal and low lignin bmr6 and bmr12 sorghum (Sorghum bicolor) were examined for insect and disease damage in the field, and insect damage in ...

1986 Agreement on third party liability in the nuclear field

International Nuclear Information System (INIS)

1986-01-01

This Agreement intends to facilitate the settlement of disputes, if they are due to an event (caused by the peaceful utilisation of nuclear energy) which occurs on the territory of one State and gives rise to damage on the territory of the other State. Unlike the Federal Republic of Germany, Switzerland has neither ratified the Paris Convention of 29th July 1960 on Third Party Liability in the Field of Nuclear Energy nor the Brussels Supplementary Convention of 31st January 1963. This might result in diverging interpretations by the German and Swiss courts, in particular, regarding the competent courts and the laws applicable if a third party liability problem were to arise between both countries. The Agreement therefore aims to settle these matters directly by treaty between the States before the courts are confronted by an occurrence of damage and have to seek a solution which conforms to international private law. (NEA) [fr

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.

Countermeasures to earthquakes in nuclear plants

International Nuclear Information System (INIS)

Sato, Kazuhide

1979-01-01

The contribution of atomic energy to mankind is unmeasured, but the danger of radioactivity is a special thing. Therefore in the design of nuclear power plants, the safety has been regarded as important, and in Japan where earthquakes occur frequently, the countermeasures to earthquakes have been incorporated in the examination of safety naturally. The radioactive substances handled in nuclear power stations and spent fuel reprocessing plants are briefly explained. The occurrence of earthquakes cannot be predicted effectively, and the disaster due to earthquakes is apt to be remarkably large. In nuclear plants, the prevention of damage in the facilities and the maintenance of the functions are required at the time of earthquakes. Regarding the location of nuclear plants, the history of earthquakes, the possible magnitude of earthquakes, the properties of ground and the position of nuclear plants should be examined. After the place of installation has been decided, the earthquake used for design is selected, evaluating live faults and determining the standard earthquakes. As the fundamentals of aseismatic design, the classification according to importance, the earthquakes for design corresponding to the classes of importance, the combination of loads and allowable stress are explained. (Kako, I.)

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)

Comparison of Measured Dark Current Distributions with Calculated Damage Energy Distributions in HgCdTe

Science.gov (United States)

Marshall, C. J.; Marshall, P. W.; Howe, C. L.; Reed, R. A.; Weller, R. A.; Mendenhall, M.; Waczynski, A.; Ladbury, R.; Jordan, T. M.

2007-01-01

This paper presents a combined Monte Carlo and analytic approach to the calculation of the pixel-to-pixel distribution of proton-induced damage in a HgCdTe sensor array and compares the results to measured dark current distributions after damage by 63 MeV protons. The moments of the Coulombic, nuclear elastic and nuclear inelastic damage distributions were extracted from Monte Carlo simulations and combined to form a damage distribution using the analytic techniques first described in [1]. The calculations show that the high energy recoils from the nuclear inelastic reactions (calculated using the Monte Carlo code MCNPX [2]) produce a pronounced skewing of the damage energy distribution. While the nuclear elastic component (also calculated using the MCNPX) contributes only a small fraction of the total nonionizing damage energy, its inclusion in the shape of the damage across the array is significant. The Coulombic contribution was calculated using MRED [3-5], a Geant4 [4,6] application. The comparison with the dark current distribution strongly suggests that mechanisms which are not linearly correlated with nonionizing damage produced according to collision kinematics are responsible for the observed dark current increases. This has important implications for the process of predicting the on-orbit dark current response of the HgCdTe sensor array.

Lessons learned from first generation nuclear plant probabalistic risk assessments

International Nuclear Information System (INIS)

Garrick, B.J.

1984-01-01

The paper by Garrick summarizes the state-of-the-art in what are perhaps the most archetypical probabilistic risk assessments (PRAs). Because of its unique regulatory environment and because of the high levels of perceived (not necessarily actual) risk, the nuclear industry more than any other has been concerned with quantitative risk analysis. Garrick's paper summarizes the lessons learned from ten PRA's conducted in the nuclear industry, including six that can be characterized as full-scope risk studies. Most of the quantitative data, though, came from two especially thorough studies done for the Zion and Indian Point power plants, operated by Commonwealth Edison and Consolidated Edison respectively. The principal conclusions of the Garrick survey are that the public risk (from radiation release) is now known to be very small for commercial nuclear power plants, but that the risk to utilities (from core damage) is somewhat larger. Significant radiation releases require both core meltdown -- an event occurring only about once every 10,000 reactor-years -- and containment failure, occurring only about once in every hundred meltdowns

A SAS/AF application to administrate and query a file of incidents occurring in foreign nuclear power plants

International Nuclear Information System (INIS)

Durbec, V.

1994-07-01

The Research and Development Division of Electricite de France has a file of incidents occurring in foreign pressurized water nuclear power stations. These incidents have an impact either on safety or reliability. The file is stored on an IBM 3090. For each incident, a docket is assigned, containing the identity of the nuclear plant and information in the form of code or text on the incident. An application has been built with the SAS System under IBM (MVS) in order to: - allow the input of new nuclear plant identities, monthly operating coefficients and new incidents; - subset data from each SAS data set, according to selection criteria (country, manufacturers, period, materials, etc...) in the form of coded fields and characters strings; -calculate simple statistical analyses on subset data (histograms of break duration, distribution of operating coefficients, cross-tabulation tables of sets and materials which bring about the incident) with a restitution on screen and/or printer; - edit an annual booklet containing general results of functioning of plants. After validation, data retrieved from the database are used in probabilistic safety analysis of nuclear power plants and materials designing studies (comparison with French materials, identification of factors having an impact on performance). The application is an interactive menu-driven tool and contains data entry screens (for new data or selection criteria). These screens have been built with SAS/AF software and Screen Control Language. Data selection and processing have been developed with Base SAS and SAS/GRAPH software. (author). 1 ref., 6 figs., 2 tabs

Electromagnetic Dissociation and Spacecraft Electronics Damage

Science.gov (United States)

Norbury, John W.

2016-01-01

When protons or heavy ions from galactic cosmic rays (GCR) or solar particle events (SPE) interact with target nuclei in spacecraft, there can be two different types of interactions. The more familiar strong nuclear interaction often dominates and is responsible for nuclear fragmentation in either the GCR or SPE projectile nucleus or the spacecraft target nucleus. (Of course, the proton does not break up, except possibly to produce pions or other hadrons.) The less familiar, second type of interaction is due to the very strong electromagnetic fields that exist when two charged nuclei pass very close to each other. This process is called electromagnetic dissociation (EMD) and primarily results in the emission of neutrons, protons and light ions (isotopes of hydrogen and helium). The cross section for particle production is approximately defined as the number of particles produced in nucleus-nucleus collisions or other types of reactions. (There are various kinematic and other factors which multiply the particle number to arrive at the cross section.) Strong, nuclear interactions usually dominate the nuclear reactions of most interest that occur between GCR and target nuclei. However, for heavy nuclei (near Fe and beyond) at high energy the EMD cross section can be much larger than the strong nuclear interaction cross section. This paper poses a question: Are there projectile or target nuclei combinations in the interaction of GCR or SPE where the EMD reaction cross section plays a dominant role? If the answer is affirmative, then EMD mechanisms should be an integral part of codes that are used to predict damage to spacecraft electronics. The question can become more fine-tuned and one can ask about total reaction cross sections as compared to double differential cross sections. These issues will be addressed in the present paper.

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.

Continuum Damage Mechanics A Continuum Mechanics Approach to the Analysis of Damage and Fracture

CERN Document Server

Murakami, Sumio

2012-01-01

Recent developments in engineering and technology have brought about serious and enlarged demands for reliability, safety and economy in wide range of fields such as aeronautics, nuclear engineering, civil and structural engineering, automotive and production industry.  This, in turn, has caused more interest in continuum damage mechanics and its engineering applications.   This book aims to give a concise overview of the current state of damage mechanics, and then to show the fascinating possibility of this promising branch of mechanics, and to provide researchers, engineers and graduate students with an intelligible and self-contained textbook.   The book consists of two parts and an appendix.  Part I  is concerned with the foundation of continuum damage mechanics.  Basic concepts of material damage and the mechanical representation of damage state of various kinds are described in Chapters 1 and 2.  In Chapters 3-5, irreversible thermodynamics, thermodynamic constitutive theory and its application ...

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

Methods of quantitative analysis of nuclear energy hazards

International Nuclear Information System (INIS)

Papp, R.; Caldarola, L.; Helm, F.; Jansen, P.; McGrath, P.; Weber, G.

1975-03-01

Risk can be defined as the sum of all possible damage types weighted with their associated cumulative probability distributions of occurrence. Risk defined in this manner is not very suitable for comparison purposes. In order to be able to synthetically express the risk by means of a single parameter, two problems must be solved: 1) For each damage type an average value must be calculated which accounts not only for the occurence probability distribution but also for the degree and importance of the damage to human society. 2) The total average value (the risk) must be calculated by weighting each average damage type with a corresponding second importance function which represents the importance and acceptability of the particular damage type to human society. Here it must be pointed out that the above mentioned problems are directly connected to the problem of 'risk acceptance', which will be as well discussed as the risk associated with the entire nuclear fuel cycle. Finally, recommendations for further research work are given in section V which are thought to be needed in order to render these methods in the near future more generally applicable and accepted than they are today. (orig./RW) [de

Radiation Damage in Reactor Materials. Part of the Proceedings of the Symposium on Radiation Damage in Solids and Reactor Materials

Energy Technology Data Exchange (ETDEWEB)

NONE

1963-08-15

Radiation damage has presented a new design parameter for the selection of materials to be used in fuel and cladding elements, moderators, structural components and pressure vessels in nuclear reactors. The severe and novel requirements for certain optimum combinations of physical and nuclear properties have emphasized the need for a better understanding of the basic mechanisms of radiation damage. This knowledge is not only essential for progress in the field of nuclear energy, but has direct applications to space technology and semi-conductor research as well. The IAEA, as part of its programme of promoting nuclear technology, therefore convened the Symposium on Radiation Damage in Solids and Reactor Materials, 7-11 May 1962. At the invitation of, and with generous material assistance from, the Government of Italy, the Symposium was held at Venice. The Symposium was primarily concerned with the investigation of the fundamental processes of radiation that underlie the behaviour of metals, alloys and ceramics that are actually useful or potentially useful reactor materials. Two sessions were devoted to studies of irradiation effects on simple metals, as these effects are easiest to interpret. Other topics included general theory, alloys, fissionable and moderator materials and special experimental techniques for radiation damage studies. The properties influenced by irradiation which were of main concern were those of primary importance to the behaviour of solids as reactor materials (e. g. dimensional stability, phase transformation, radiation hardening, fracture, fission-gas escape from uranium and its compounds). Other properties, such as optical, electrical and magnetic properties, and effects on semiconductors, ionic and other non-metallic crystals are also of interest in that these studies can increase our knowledge of the mechanism of radiation damage in solids and provide a tool for investigation into the physics of the solid state by offering a means of

Radiation Damage in Reactor Materials. Part of the Proceedings of the Symposium on Radiation Damage in Solids and Reactor Materials

International Nuclear Information System (INIS)

1963-01-01

Radiation damage has presented a new design parameter for the selection of materials to be used in fuel and cladding elements, moderators, structural components and pressure vessels in nuclear reactors. The severe and novel requirements for certain optimum combinations of physical and nuclear properties have emphasized the need for a better understanding of the basic mechanisms of radiation damage. This knowledge is not only essential for progress in the field of nuclear energy, but has direct applications to space technology and semi-conductor research as well. The IAEA, as part of its programme of promoting nuclear technology, therefore convened the Symposium on Radiation Damage in Solids and Reactor Materials, 7-11 May 1962. At the invitation of, and with generous material assistance from, the Government of Italy, the Symposium was held at Venice. The Symposium was primarily concerned with the investigation of the fundamental processes of radiation that underlie the behaviour of metals, alloys and ceramics that are actually useful or potentially useful reactor materials. Two sessions were devoted to studies of irradiation effects on simple metals, as these effects are easiest to interpret. Other topics included general theory, alloys, fissionable and moderator materials and special experimental techniques for radiation damage studies. The properties influenced by irradiation which were of main concern were those of primary importance to the behaviour of solids as reactor materials (e. g. dimensional stability, phase transformation, radiation hardening, fracture, fission-gas escape from uranium and its compounds). Other properties, such as optical, electrical and magnetic properties, and effects on semiconductors, ionic and other non-metallic crystals are also of interest in that these studies can increase our knowledge of the mechanism of radiation damage in solids and provide a tool for investigation into the physics of the solid state by offering a means of

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.

Apportioning liability for transborder damages

International Nuclear Information System (INIS)

Krause-Ablass, W.-D.

1988-01-01

The legal situation in the case of cross border damage being caused by reactor accidents or transportation of nuclear material through more than one country is analysed. Two questions have to be asked - which country's courts have jurisdiction over the claims for damage? and which law is applicable? In considering the jurisdiction problem, the Paris and Vienna Conventions are discussed and also other rules of jurisdiction. The way the law is applicable is discussed in the second section. When the action for liability is based on the Paris or Vienna Convention the issue of reciprocity may arise and this is discussed. After a nuclear incident a potential plaintiff may have a choice amongst various jurisdictions and various available laws. Success may depend on the right choice of the forum chosen. This is illustrated by two examples. (U.K.)

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

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.)

Development of international law concerning nuclear liability

International Nuclear Information System (INIS)

Ifflaender, G.; Kantner, G.

1979-01-01

A short overview is given of the most important international conventions relating to civil liability for damage to, or loss of, life of persons or property, caused by nuclear incidents during the operation of stationary and non-stationary nuclear installations or transport of nuclear material. In accord with the international provisions, in the German Democratic Republic too, nuclear operators are exclusively liable for such damage unless it has been caused intentionally by the injury party. (author)

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

Beam damage of self-assembled monolayers

International Nuclear Information System (INIS)

Rieke, P.C.; Baer, D.R.; Fryxell, G.E.; Engelhard, M.H.; Porter, M.S.

1993-01-01

X-ray and electron beam damage studies were performed on Br-terminated and methyl-terminated alkylsilane self-assembled monolayers. X-ray beam initiated damage was primarily limited to removal of the labile Br group and did not significantly damage the hydrocarbon chain. Some of the x-ray beam damage could be attributed to low-energy electrons emitted by the non-monochromatic source, but further damage was attributed to secondary electrons produced in the sample by x-ray exposure. Electron beams caused significant damage to the hydrocarbon chains. Maximum damage occurred with a beam energy of 600 eV and a dosage of 6x10 -3 C/cm 2

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)

Nuclear Liability Legislation in Slovenia

International Nuclear Information System (INIS)

Skraban, A.

1998-01-01

This paper reviews Slovenian national legislation in the field of third party liability for nuclear damage, applicability of the international nuclear liability treaties in Slovenia legal system and outlines some main provisions of national legislation. It is worth mentioning that legal instruments covering third party liability and compulsory insurance of such liability exist in Slovenia for almost 20 years and that our nuclear facilities are covered by relevant international treaties and conventions in this field, among them also by the Vienna Convention on Civil Liability for Nuclear Damage (from 1977) and the Joint Protocol Relating to the Application of the Vienna Convention and the Paris Convention (from 1994). (author)

Surveillance of nuclear power reactors

International Nuclear Information System (INIS)

Marini, J.

1983-01-01

Surveillance of nuclear power reactors is now a necessity imposed by such regulatory documents as USNRC Regulatory Guide 1.133. In addition to regulatory requirements, however, nuclear reactor surveillance offers plant operators significant economic advantages insofar as a single day's outage is very costly. The economic worth of a reactor surveillance system can be stated in terms of the improved plant availability provided through its capability to detect incidents before they occur and cause serious damage. Furthermore, the TMI accident has demonstrated the need for monitoring certain components to provide operators with clear information on their functional status. In response to the above considerations, Framatome has developed a line of products which includes: pressure vessel leakage detection systems, loose part detection systems, component vibration monitoring systems, and, crack detection and monitoring systems. Some of the surveillance systems developed by Framatome are described in this paper

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

Nuclear danger in the modern world

International Nuclear Information System (INIS)

Sulejmenov, O.O.

2000-01-01

It is noted, that nowadays a nuclear danger proceeds from nuclear depositions of countries having own nuclear weapons. Since Kazakhstan is one of the first country in the world which fulfilled regulations of Lisbon Protocol and liquidated own nuclear potential, author regards that Kazakhstan have moral right for initiating process of attachment to Comprehensive Nuclear Test Ban Treaty by countries having nuclear weapon. Now for Kazakhstan there are urgent problems: financing of post-conversion processes; re-cultivation of territory contaminated by residuals from nuclear weapons test; rehabilitation of population health, damaged from test of mass destruction weapon. Scientists of Kazakhstan estimated damage from nuclear test on Kazakstan territory in 10 billion dollars. It is necessary international efforts of all public organizations of the world for all world sites. One of the financing source could be means from reduction of nuclear arms production

Electric arc discharge damage to ion thruster grids

Science.gov (United States)

Beebe, D. D.; Nakanishi, S.; Finke, R. C.

1974-01-01

Arcs representative of those occurring between the grids of a mercury ion thruster were simulated. Parameters affecting an arc and the resulting damage were studied. The parameters investigated were arc energy, arc duration, and grid geometry. Arc attenuation techniques were also investigated. Potentially serious damage occurred at all energy levels representative of actual thruster operating conditions. Of the grids tested, the lowest open-area configuration sustained the least damage for given conditions. At a fixed energy level a long duration discharge caused greater damage than a short discharge. Attenuation of arc current using various impedances proved to be effective in reducing arc damage. Faults were also deliberately caused using chips of sputtered materials formed during the operation of an actual thruster. These faults were cleared with no serious grid damage resulting using the principles and methods developed in this study.

Nuclear low and environmental protection

International Nuclear Information System (INIS)

Vencato, A.C.B.

1982-01-01

The imperceptible character of nuclear radiation on the human senses and their harmful effects on living beings and the environment is emphasised. This is based on a review of published works about the concepts of energy and ecology. The potential hazards of a possible nuclear accident and the damage it would cause to a community as well as the problem of radioactive waste disposal are raised. The conclusions and recommendations of the Brazilian Physics Society's Report on Nuclear Pollution are endorsed. The general guidelines of Brazilian Legislation are presented. The legal aspects of nuclear reactor licensing in West Germany, the United Kingdom, France and Brazil are shown from the point of view of the applicable legal system, the licensing bodies, the general frame and scope, public participation, technical safety bodies, as well as the inspection procedures. The concepts of absolute and objective civil responsibility for nuclear damage are reviewed. The judicial principle of equity is considered in view of the exceptional character of the nuclear risk. The main aspects of the international Conventions of Paris, Brussels and Viena on civil ability of nuclear damage are presented. Some philosphical and judicial questions are discussed emphasising the instrumentality of the law control and effective protection. The final suggestion is the exchange of ideas with a view to obtain the maximum safety in the operation of nuclear installations. (author) [pt

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

Lessons learned from Fukushima. Nuclear power is a risk technology and not a bridging technology

International Nuclear Information System (INIS)

Mez, Lutz

2011-01-01

The reactor accident in Fukushima-Daiichi in 2011 as a consequence of the earth quake and tsunami has produced damage cost of 300 billions $ according to the Japanese government, - the cost for the destroyed nuclear power plant are not included. The Fukushima NPP is one of the oldest nuclear power plants worldwide and was not designed for natural disaster as occurred in 2011. The owner Tepco has not properly performed the required retrofitting and maintenance measures. The contribution discusses questions with respect to the acceptability of the consequences of reactor accidents for democratic societies.

Ordinance on nuclear third party liability (ORCN)

International Nuclear Information System (INIS)

1983-12-01

The Ordinance exempts from the application of the 1983 Act on Nuclear Third Party Liability some substances with low radiation effects. It determines the amount of private insurance cover and defines the risks that insurers may exclude from cover. It establishes a special fund for nuclear damage made up of contributions from the nuclear operators. Specifications are given on the amount of the contributions and their conditions, as well as on administration of the fund. The Ordinance repeals the Ordinance of 13 June 1960 on funds for delayed atomic damage, the Order of 19 December 1960 on contributions to the fund for delayed atomic damage and the Ordinance of 30 November 1981 on cover for third party liability resulting from nuclear power plant operation [fr

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

Numerical study of damage in unsaturated Geological and Engineered barriers

International Nuclear Information System (INIS)

Arson, C.; Gatmiri, B.

2011-01-01

The theoretical framework of a damage model dedicated to non-isothermal unsaturated porous media is presented. The damage variable is a second-order tensor, and the model is formulated in independent state variables. The behavior laws are derived from a postulated expression of Helmholtz free energy. The damaged rigidities are computed by applying the Principle of Equivalent Elastic Energy (PEEE). Internal length parameters are introduced in the expressions of liquid water and vapor conductivities, to account for cracking effects on fluid flows. The damage model has been implemented in Θ-Stock Finite Element program. The mechanical aspect of the damage model is validated by simulating a triaxial compression test on a dry isothermal brittle material. Then, a sophisticated model of nuclear waste disposal, involving two non-isothermal unsaturated porous media, is reproduced. The results obtained in elasticity are in good agreement with the results presented in the corresponding reference article. A parametric study on initial damage is then performed to assess the influence of the Excavated Damaged Zone (EDZ) on the response of the nuclear waste repository during the heating phase. The trends meet the theoretical expectations. (authors)

DDG Opening Remarks [International Experts' Meeting on Decommissioning and Remediation after a Nuclear Accident

International Nuclear Information System (INIS)

Bychkov, Alexander

2013-01-01

Any significant nuclear accident results in challenges in terms of the decommissioning of the damaged facilities and in many cases also in the remediation of contaminated areas outside the site boundary. These challenges include the application of appropriate technological and human resources, public involvement and the allocation of the necessary financing, which is of course considerable. There can be no real future for nuclear energy unless the global community is convinced that the legacies associated with its use can be addressed satisfactorily, whether in connection with facilities contaminated as a result of a nuclear or radiological accident, or indeed large facilities used for research or other purposes during the developmental phase of the nuclear industry. It is evident that decommissioning and remediation projects, especially for nuclear facilities and sites after an accident, will continue to be undertaken for many decades, over which time it is expected that technological developments will occur. It will be important that the new and more sophisticated technologies of the future are applied to these activities. However we should also be aware that in case of dealing with accident-damaged facilities there is a great deal to be learnt from the experience from the past 60 years and this meeting is focused directly on reviewing and distilling that experience

The Cell Nucleus Serves as a Mechanotransducer of Tissue Damage-Induced Inflammation.

Science.gov (United States)

Enyedi, Balázs; Jelcic, Mark; Niethammer, Philipp

2016-05-19

Tissue damage activates cytosolic phospholipase A2 (cPLA2), releasing arachidonic acid (AA), which is oxidized to proinflammatory eicosanoids by 5-lipoxygenase (5-LOX) on the nuclear envelope. How tissue damage is sensed to activate cPLA2 is unknown. We investigated this by live imaging in wounded zebrafish larvae, where damage of the fin tissue causes osmotic cell swelling at the wound margin and the generation of a chemotactic eicosanoid signal. Osmotic swelling of cells and their nuclei activates cPla2 by translocating it from the nucleoplasm to the nuclear envelope. Elevated cytosolic Ca(2+) was necessary but not sufficient for cPla2 translocation, and nuclear swelling was required in parallel. cPla2 translocation upon nuclear swelling was reconstituted in isolated nuclei and appears to be a simple physical process mediated by tension in the nuclear envelope. Our data suggest that the nucleus plays a mechanosensory role in inflammation by transducing cell swelling and lysis into proinflammatory eicosanoid signaling. Copyright © 2016 Elsevier Inc. All rights reserved.

Nuclear data needs for fusion reactors

International Nuclear Information System (INIS)

Gohar, Y.

1986-01-01

The nuclear design of fusion components (e.g., first wall, blanket, shield, magnet, limiter, divertor, etc.) requires an accurate prediction of the radiation field, the radiation damage parameters, and the activation analysis. The fusion nucleonics for these tasks are reviewed with special attention to point out nuclear data needs and deficiencies which effect the design process. The main areas included in this review are tritium breeding analyses, nuclear heating calculations, radiation damage in reactor components, shield designs, and results of uncertainty analyses as applied to fusion reactor studies. Design choices and reactor parameters that impact the neutronics performance of the blanket are discussed with emphasis on the tritium breeding ratio. Nuclear data required for kerma factors, shielding analysis, and radiation damage are discussed. Improvements in the evaluated data libraries are described to overcome the existing problems. 84 refs., 11 figs., 9 tabs

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.

Nuclear energy and sustainability in Latin America

International Nuclear Information System (INIS)

Sterner, Thomas

1991-01-01

The concept of sustainability has been given numerous interpretations, some overlapping or complementary, some contradictory. Thus it is difficult to judge whether the nuclear industry does, or does not, meet sustainability criteria; particularly as the present nuclear technologies are not renewable. Uranium resources appear to be of the same order of magnitude as oil and gas resources. This implies that they are a transitional source of energy. There are also other potential arguments against the sustainability of nuclear power: its pollution, risks and costs. Environmental damage may come from various parts of the nuclear fuel cycle. Two types of risk will be discussed: first the risk of major accidents and thereby exceptional environmental damage, and second the risks associated with the proliferation of nuclear weapons. Each of these factors, as well as the pure economic cost of nuclear electricity, ought to be compared to the environmental damage, risks and costs of the available alternatives. Only the Latin American experience will be considered. For example, the need for Mexico to use nuclear power when it has large oil and gas supplies, is considered. (author)

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)

Fission product chemistry in severe nuclear reactor accidents

International Nuclear Information System (INIS)

Nichols, A.L.

1990-09-01

A specialist's meeting was held at JRC-Ispra from 15 to 17 January 1990 to review the current understanding of fission-product chemistry during severe accidents in light water reactors. Discussions focussed on the important chemical phenomena that could occur across the wide range of conditions of a damaged nuclear plant. Recommendations for future chemistry work were made covering the following areas: (a) fuel degradation and fission-product release, (b) transport and attenuation processes in the reactor coolant system, (c) containment chemistry (iodine behaviour and core-concrete interactions)

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

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

Harmonisation of Nuclear Liability Regimes in Europe

International Nuclear Information System (INIS)

Sladonja, B.

2000-01-01

After we have learned about the current discussions concerning the Paris Convention revision exercise and the open matters relating to the liability limits and insurance for nuclear damages, prescription period, definition of nuclear damage etc. and different approaches in some PCC in adopting their legislation as well as about the adoption of the Protocol to Amend the Vienna Convention and Convention on Supplementary Compensation for Nuclear Damage, within the Vienna Convention countries, during the obtained Session 9 of this Conference we will focus our attention on the matters which has been discovered from the moment when the reports has been written till the date of this Conference

The compensation of damage in Germany following the Chernobyl accident

International Nuclear Information System (INIS)

Eich, W.

2003-01-01

In the framework of the workshop on the indemnification of damage in the event of a nuclear accident, this paper presents the proceeding of the the discussion on the compensation of damage in Germany following the Chernobyl accident. This paper presents also the national experiences and opinions, a documentation of the Federal Office of Administration on the topic, the example of Tokai-mura accident third party liability and compensation and the third party liability in the field of nuclear law in Ireland. (A.L.B.)

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

Root causes and impacts of severe accidents at large nuclear power plants.

Science.gov (United States)

Högberg, Lars

2013-04-01

The root causes and impacts of three severe accidents at large civilian nuclear power plants are reviewed: the Three Mile Island accident in 1979, the Chernobyl accident in 1986, and the Fukushima Daiichi accident in 2011. Impacts include health effects, evacuation of contaminated areas as well as cost estimates and impacts on energy policies and nuclear safety work in various countries. It is concluded that essential objectives for reactor safety work must be: (1) to prevent accidents from developing into severe core damage, even if they are initiated by very unlikely natural or man-made events, and, recognizing that accidents with severe core damage may nevertheless occur; (2) to prevent large-scale and long-lived ground contamination by limiting releases of radioactive nuclides such as cesium to less than about 100 TBq. To achieve these objectives the importance of maintaining high global standards of safety management and safety culture cannot be emphasized enough. All three severe accidents discussed in this paper had their root causes in system deficiencies indicative of poor safety management and poor safety culture in both the nuclear industry and government authorities.

Root Causes and Impacts of Severe Accidents at Large Nuclear Power Plants

International Nuclear Information System (INIS)

Hoegberg, Lars

2013-01-01

The root causes and impacts of three severe accidents at large civilian nuclear power plants are reviewed: the Three Mile Island accident in 1979, the Chernobyl accident in 1986, and the Fukushima Daiichi accident in 2011. Impacts include health effects, evacuation of contaminated areas as well as cost estimates and impacts on energy policies and nuclear safety work in various countries. It is concluded that essential objectives for reactor safety work must be: (1) to prevent accidents from developing into severe core damage, even if they are initiated by very unlikely natural or man-made events, and, recognizing that accidents with severe core damage may nevertheless occur; (2) to prevent large-scale and long lived ground contamination by limiting releases of radioactive nuclides such as cesium to less than about 100 TBq. To achieve these objectives the importance of maintaining high global standards of safety management and safety culture cannot be emphasized enough. All three severe accidents discussed in this paper had their root causes in system deficiencies indicative of poor safety management and poor safety culture in both the nuclear industry and government authorities

Root Causes and Impacts of Severe Accidents at Large Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Hoegberg, Lars

2013-04-15

The root causes and impacts of three severe accidents at large civilian nuclear power plants are reviewed: the Three Mile Island accident in 1979, the Chernobyl accident in 1986, and the Fukushima Daiichi accident in 2011. Impacts include health effects, evacuation of contaminated areas as well as cost estimates and impacts on energy policies and nuclear safety work in various countries. It is concluded that essential objectives for reactor safety work must be: (1) to prevent accidents from developing into severe core damage, even if they are initiated by very unlikely natural or man-made events, and, recognizing that accidents with severe core damage may nevertheless occur; (2) to prevent large-scale and long lived ground contamination by limiting releases of radioactive nuclides such as cesium to less than about 100 TBq. To achieve these objectives the importance of maintaining high global standards of safety management and safety culture cannot be emphasized enough. All three severe accidents discussed in this paper had their root causes in system deficiencies indicative of poor safety management and poor safety culture in both the nuclear industry and government authorities.

Determination of the shapes and sizes of the regions in which in hadron-nucleus collisions reactions leading to the nucleon emission, particle production, and fragment evaporation occur

International Nuclear Information System (INIS)

Strugalski, Z.

1985-01-01

Shapes and sizes of the regions in target-nuclei in which reactions leading to the nucleon emission, particle production and fragment evaporation occur are determined. The region of nucleon emission is of cylindrical shape, with the diameter as large as two nucleon diameters, centered on the incident hadron course. The reactions leading to the particle production happen predominantly along the incident hadron course in nuclear matter. The fragment evaporation goes from the surface layer of the part of the target-nucleus damaged in nucleon emission process

DNA damage by carbonyl stress in human skin cells

International Nuclear Information System (INIS)

Roberts, Michael J.; Wondrak, Georg T.; Laurean, Daniel Cervantes; Jacobson, Myron K.; Jacobson, Elaine L.

2003-01-01

Reactive carbonyl species (RCS) are potent mediators of cellular carbonyl stress originating from endogenous chemical processes such as lipid peroxidation and glycation. Skin deterioration as observed in photoaging and diabetes has been linked to accumulative protein damage from glycation, but the effects of carbonyl stress on skin cell genomic integrity are ill defined. In this study, the genotoxic effects of acute carbonyl stress on HaCaT keratinocytes and CF3 fibroblasts were assessed. Administration of the α-dicarbonyl compounds glyoxal and methylglyoxal as physiologically relevant RCS inhibited skin cell proliferation, led to intra-cellular protein glycation as evidenced by the accumulation of N ε -(carboxymethyl)-L-lysine (CML) in histones, and caused extensive DNA strand cleavage as assessed by the comet assay. These effects were prevented by treatment with the carbonyl scavenger D-penicillamine. Both glyoxal and methylglyoxal damaged DNA in intact cells. Glyoxal caused DNA strand breaks while methylglyoxal produced extensive DNA-protein cross-linking as evidenced by pronounced nuclear condensation and total suppression of comet formation. Glycation by glyoxal and methylglyoxal resulted in histone cross-linking in vitro and induced oxygen-dependent cleavage of plasmid DNA, which was partly suppressed by the hydroxyl scavenger mannitol. We suggest that a chemical mechanism of cellular DNA damage by carbonyl stress occurs in which histone glycoxidation is followed by reactive oxygen induced DNA stand breaks. The genotoxic potential of RCS in cultured skin cells and its suppression by a carbonyl scavenger as described in this study have implications for skin damage and carcinogenesis and its prevention by agents selective for carbonyl stress

DNA damage by carbonyl stress in human skin cells

Energy Technology Data Exchange (ETDEWEB)

Roberts, Michael J.; Wondrak, Georg T.; Laurean, Daniel Cervantes; Jacobson, Myron K.; Jacobson, Elaine L

2003-01-28

Reactive carbonyl species (RCS) are potent mediators of cellular carbonyl stress originating from endogenous chemical processes such as lipid peroxidation and glycation. Skin deterioration as observed in photoaging and diabetes has been linked to accumulative protein damage from glycation, but the effects of carbonyl stress on skin cell genomic integrity are ill defined. In this study, the genotoxic effects of acute carbonyl stress on HaCaT keratinocytes and CF3 fibroblasts were assessed. Administration of the {alpha}-dicarbonyl compounds glyoxal and methylglyoxal as physiologically relevant RCS inhibited skin cell proliferation, led to intra-cellular protein glycation as evidenced by the accumulation of N{sup {epsilon}}-(carboxymethyl)-L-lysine (CML) in histones, and caused extensive DNA strand cleavage as assessed by the comet assay. These effects were prevented by treatment with the carbonyl scavenger D-penicillamine. Both glyoxal and methylglyoxal damaged DNA in intact cells. Glyoxal caused DNA strand breaks while methylglyoxal produced extensive DNA-protein cross-linking as evidenced by pronounced nuclear condensation and total suppression of comet formation. Glycation by glyoxal and methylglyoxal resulted in histone cross-linking in vitro and induced oxygen-dependent cleavage of plasmid DNA, which was partly suppressed by the hydroxyl scavenger mannitol. We suggest that a chemical mechanism of cellular DNA damage by carbonyl stress occurs in which histone glycoxidation is followed by reactive oxygen induced DNA stand breaks. The genotoxic potential of RCS in cultured skin cells and its suppression by a carbonyl scavenger as described in this study have implications for skin damage and carcinogenesis and its prevention by agents selective for carbonyl stress.

Metabolite damage and repair in metabolic engineering design

Energy Technology Data Exchange (ETDEWEB)

Sun, Jiayi; Jeffryes, James G.; Henry, Christopher S.; Bruner, Steven D.; Hanson, Andrew D.

2017-11-01

The necessarily sharp focus of metabolic engineering and metabolic synthetic biology on pathways and their fluxes has tended to divert attention from the damaging enzymatic and chemical side-reactions that pathway metabolites can undergo. Although historically overlooked and underappreciated, such metabolite damage reactions are now known to occur throughout metabolism and to generate (formerly enigmatic) peaks detected in metabolomics datasets. It is also now known that metabolite damage is often countered by dedicated repair enzymes that undo or prevent it. Metabolite damage and repair are highly relevant to engineered pathway design: metabolite damage reactions can reduce flux rates and product yields, and repair enzymes can provide robust, host-independent solutions. Herein, after introducing the core principles of metabolite damage and repair, we use case histories to document how damage and repair processes affect efficient operation of engineered pathways - particularly those that are heterologous, non-natural, or cell-free. We then review how metabolite damage reactions can be predicted, how repair reactions can be prospected, and how metabolite damage and repair can be built into genome-scale metabolic models. Lastly, we propose a versatile 'plug and play' set of well-characterized metabolite repair enzymes to solve metabolite damage problems known or likely to occur in metabolic engineering and synthetic biology projects.

Nuclear fundamentals remain

Directory of Open Access Journals (Sweden)

Stošić Zoran V.

2012-01-01

Full Text Available For Japan, the situation has become extremely difficult since counter-measures to deal with the nuclear accident had to be carried out along with dealing with the broader disaster caused by earthquake and the tsunami. In terms of damage, the Tohoku earthquake and the tsunami have caused the most fatalities and the largest economic loss ever from an earthquake and/or tsunami. The impact of this natural disaster is present not only in Japan but world-wide. The state of affairs in the global energy sector is affected by the consequences which may be lasting for decades. These effects are subject of this article dealing not with the nuclear accident at Fukushima Daiichi NPPs itself, but rather with the world-wide consequences and after effect on nuclear energy development. This includes: environmental damages, socio-economic effects, actions of safety authorities, extended protective measures against external events, the impact on global nuclear energy, triggered nuclear phase-outs and changes in new build plans as well as the sustainability of energy mix itself and an outlook.

Damage of reactor buildings occurred at the Fukushima Daiichi accident. Focusing on sequence leading to hydrogen explosions

International Nuclear Information System (INIS)

Naito, Masanori

2011-01-01

Fukushima Daiichi accident discharged enormous radioactive materials confined inside into the environment due to hydrogen explosions occurred at reactor buildings and forced many people to live the refugee life. This article described overview of Great East Japan Earthquake, specifications of Fukushima Daiichi nuclear power plants, sequence of plant status after earthquake occurrence and computerized simulation of plant behavior of Unit 1 leading to core melt and hydrogen explosion. Simulation results with estimated and assumed conditions showed water level decreased to bottom of reactor core after 4 hrs and 15 minutes passed, core melt started after 6 hrs and 49 minutes passed, failure of core support plate after 7 hrs and 18 minutes passed and through failure of penetration at bottom of pressure vessel after 7 hrs and 25 minutes passed. Hydrogen concentration at operating floor of reactor building of Unit 1 would be 15% accumulated and the pressure would amount to about 5 bars after hydrogen explosion if reactor building did not rupture with leak-tight structure. Since reactor building was not pressure-proof structure, walls of operating floor would rupture before 5 bars attained. (T. Tanaka)

Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage

International Nuclear Information System (INIS)

Qu, Jianmin; Bazant, Zdenek; Jacobs, Laurence; Guimaraes, Maria

2015-01-01

Alkali-silica reaction (ASR) is a deleterious chemical process that may occur in cement-based materials such as mortars and concretes, where the hydroxyl ions in the highly alkaline pore solution attack the siloxane groups in the siliceous minerals in the aggregates. The reaction produces a cross-linked alkali-silica gel. The ASR gel swells in the presence of water. Expansion of the gel results in cracking when the swelling-induced stress exceeds the fracture toughness of the concrete. As the ASR continues, cracks may grow and eventually coalesce, which results in reduced service life and a decrease safety of concrete structures. Since concrete is widely used as a critical structural component in dry cask storage of used nuclear fuels, ASR damage poses a significant threat to the sustainability of long term dry cask storage systems. Therefore, techniques for effectively detecting, managing and mitigating ASR damage are needed. Currently, there are no nondestructive methods to accurately detect ASR damage in existing concrete structures. The only current way of accurately assessing ASR damage is to drill a core from an existing structure, and conduct microscopy on this drilled cylindrical core. Clearly, such a practice is not applicable to dry cask storage systems. To meet these needs, this research is aimed at developing (1) a suite of nonlinear ultrasonic quantitative nondestructive evaluation (QNDE) techniques to characterize ASR damage, and (2) a physics-based model for ASR damage evolution using the QNDE data. Outcomes of this research will provide a nondestructive diagnostic tool to evaluate the extent of the ASR damage, and a prognostic tool to estimate the future reliability and safety of the concrete structures in dry cask storage systems

Nonlinear Ultrasonic Diagnosis and Prognosis of ASR Damage in Dry Cask Storage

Energy Technology Data Exchange (ETDEWEB)

Qu, Jianmin [Northwestern Univ., Evanston, IL (United States); Bazant, Zdenek [Northwestern Univ., Evanston, IL (United States); Jacobs, Laurence [Georgia Inst. of Technology, Atlanta, GA (United States); Guimaraes, Maria [Electrical Power Research Institute, Palo Alto, CA (United States)

2015-11-30

Alkali-silica reaction (ASR) is a deleterious chemical process that may occur in cement-based materials such as mortars and concretes, where the hydroxyl ions in the highly alkaline pore solution attack the siloxane groups in the siliceous minerals in the aggregates. The reaction produces a cross-linked alkali-silica gel. The ASR gel swells in the presence of water. Expansion of the gel results in cracking when the swelling-induced stress exceeds the fracture toughness of the concrete. As the ASR continues, cracks may grow and eventually coalesce, which results in reduced service life and a decrease safety of concrete structures. Since concrete is widely used as a critical structural component in dry cask storage of used nuclear fuels, ASR damage poses a significant threat to the sustainability of long term dry cask storage systems. Therefore, techniques for effectively detecting, managing and mitigating ASR damage are needed. Currently, there are no nondestructive methods to accurately detect ASR damage in existing concrete structures. The only current way of accurately assessing ASR damage is to drill a core from an existing structure, and conduct microscopy on this drilled cylindrical core. Clearly, such a practice is not applicable to dry cask storage systems. To meet these needs, this research is aimed at developing (1) a suite of nonlinear ultrasonic quantitative nondestructive evaluation (QNDE) techniques to characterize ASR damage, and (2) a physics-based model for ASR damage evolution using the QNDE data. Outcomes of this research will provide a nondestructive diagnostic tool to evaluate the extent of the ASR damage, and a prognostic tool to estimate the future reliability and safety of the concrete structures in dry cask storage systems

Strengthening Canada's nuclear liability regime

International Nuclear Information System (INIS)

McCauley, D.; Henault, J.

2014-01-01

On January 30, 2014, a Bill entitled the Energy Safety and Security Act, was introduced in Parliament that, among other things, would strengthen Canada's nuclear civil liability legislation by replacing the current Nuclear Liability Act. The proposed legislation also includes implementing provisions that would permit Canada to join the International Atomic Energy Agency's Convention on Supplementary Compensation for Nuclear Damage. This paper will discuss the importance of a comprehensive civil liability regime for nuclear damage to a country's legislative framework for nuclear development and will present the key elements of Canada's new legislation and the policy considerations behind them. (author))

Nuclear deterrence: Inherent escalation?

International Nuclear Information System (INIS)

Bergbauer, J.R. Jr.

1993-01-01

Despite 40 years of peace between the super powers, there is increasing clamor to the effect that nuclear war between the super powers is imminent; or could occur through escalation from a minor conflict; or could result from harsh rhetoric (but only on the part of the U.S.) in the super power dialogue. The factor that is ignored is that a massive nuclear attack would be rational ONLY if that attack could inflict such damage that the other super power could not launch a significant retaliatory nuclear attack. ONLY in this circumstance would there be any profit in launching an initial Strategic Nuclear Attack. This First Strike capability is not now possessed nor projected to be developed by either super power. As long as ANY possible Strategic Nuclear Attack against the national territory of one super power would be insufficient to prevent an equally destructive retaliatory attack, then a Strategic Nuclear Attack would inevitably result in the destruction of both and would be profitless, hence, pointless. This situation describes Mutually Assured Destruction (MAD), the governing conflict paradigm applicable to both super powers. The only convential attack that would even remotely rival the national-destruction potential of a Strategic Nuclear Attack and could cause the attacked power to consider launching a retaliatory Strategic Nuclear Attack would be a massive land-air invasion/occupation of one super power by the other. Since neither super power can successfully execute such a conventional invasion/occupation, this situation is moot. The geo-political environments of the two super powers are so asymmetrical and their military positions so symmetrical that the probability of ANY forseeable situation resulting in their resorting to a Strategic Nuclear Exchange is vanishingly small. It is possible escape the Chicken-Little syndrome and, instead, devote energy to ensuring the maintenance of this favorable, but fragile, world system

THE IMPACT OF THE GLOBAL NUCLEAR SAFETY REGIME IN BRAZIL

International Nuclear Information System (INIS)

Almeida, C.

2004-01-01

A turning point of the world nuclear industry with respect to safety occurred due to the accident at Chernobyl, in 1986. A side from the tragic personal losses and the enormous financial damage, the Chernobyl accident has literally demonstrated that ''a nuclear accident anywhere is an accident everywhere''. The impact was felt immediately by the nuclear industry, with plant cancellations (e.g. Austria), elimination of national programs (e.g. Italy) and general construction delays. However, the reaction of the nuclear industry was equally immediate, which led to the proposal and establishment of a Global Nuclear Safety Regime. This regime is composed of biding international safety conventions, globally accepted safety standard, and a voluntary peer review system. In a previous work, the author has presented in detail the components of this Regime, and briefly discussed its impact in the Brazilian nuclear power organizations, including the Regulatory Body. This work, on the opposite, briefly reviews the Global Nuclear Safety Regime, and concentrates in detail in the discussion of its impact in Brazil, showing how it has produced some changes, and where the peer pressure regime has failed to produce real results

Accident at the Fukushima Dai-ichi Nuclear Power Stations of TEPCO —Outline & lessons learned—

Science.gov (United States)

TANAKA, Shun-ichi

2012-01-01

The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety of NPSs, as well as radiation protection of residents under the emergency involving the accident. The materials of the current paper are those released by governmental agencies, academic societies, interim reports of committees under the government, and others. PMID:23138450

Accident at the Fukushima Dai-ichi nuclear power stations of TEPCO. Outline and lessons learned

International Nuclear Information System (INIS)

Tanaka, Shun-ichi

2012-01-01

The severe accident that broke out at Fukushima Dai-ichi nuclear power stations on March 11, 2011, caused seemingly infinite damage to the daily life of residents. Serious and wide-spread contamination of the environment occurred due to radioactive materials discharged from nuclear power stations (NPSs). At the same time, many issues were highlighted concerning countermeasures to severe nuclear accidents. The accident is outlined, and lessons learned are extracted with respect to the safety of NPSs, as well as radiation protection of residents under the emergency involving the accident. The materials of the current paper are those released by governmental agencies, academic societies, interim reports of committees under the government, and others. (author)

Lessons learned from our accident at Fukushima nuclear power stations

International Nuclear Information System (INIS)

Kawano, A.

2012-01-01

This paper is given in order to share the detailed information on the Fukushima Accident which occurred on March 11, 2011, and the lessons learned from it which worldwide nuclear experts might currently have more interest in. The paper first reflects how the facilities were damaged by a very strong earthquake and a series of beyond design-basis tsunamis. The earthquake caused loss of all off-site electric power at Fukushima Daiichi Nuclear Power Station (1F), and the following series of tsunami made all emergency diesel generators except one for Unit 6 and most of DC batteries inoperable and severely damaged most of the facilities located on the ocean side. Thus all the units at 1F resulted in the loss of cooling function and ultimate heat sink for a long time period. TEPCO focused on restoration of the instruments and lights in the Main Control Room (MCR), preparation of alternative water injection and venting of Primary Containment Vessel (PCV) in the recovery process. However, the workers faced a lot of difficulties such as total darkness, repeated aftershocks, high radiation dose, a lot of debris on the ground, loss of communication means, etc. Massive damages by the tsunami and lack of necessary equipments and resources hampered a quick recovery. It eventually resulted in the severe core damage of Unit 1, 2, and 3 and also the hydrogen explosions in the reactor buildings of Unit 1, 3, and 4. This paper finally extracts the lessons learned from the accident and proposes the countermeasures, such as flood protection for essential facilities, preparation of practical and effective tools, securing communication means and so on. These would help the people involved in the nuclear industries all over the world properly understand the accident and develop their own countermeasures appropriately. (authors)

Bruce B fuelling-with-flow operations: fuel damage investigation

Energy Technology Data Exchange (ETDEWEB)

Manzer, A.M. [CANTECH Associates Ltd., Burlington, Ontario (Canada); Morikawa, D. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Hains, A.J.; Cichowlas, W.M. [Nuclear Safety Solutions Limited, Toronto, Ontario (Canada); Roberts, J.G.; Wylie, J. [Bruce Power, Ontario (Canada)

2005-07-01

This paper summarizes the fuel bundle damage characterization done by Nuclear Safety Solutions Limited (NSS) and the out-reactor flow visualization tests done at Atomic Energy of Canada Limited (AECL) to reproduce the damage observed on irradiated fuel bundles. The bearing pad damage mechanism was identified and the tests showed that a minor change to the fuelling sequence would eliminate the mechanical interaction. The change was implemented in January 2005. Since then, the bearing pad damage appears to have been greatly reduced based on the small number of discharged bundles inspected to date. (author)

Bruce B fuelling-with-flow operations: fuel damage investigation

International Nuclear Information System (INIS)

Manzer, A.M.; Morikawa, D.; Hains, A.J.; Cichowlas, W.M.; Roberts, J.G.; Wylie, J.

2005-01-01

This paper summarizes the fuel bundle damage characterization done by Nuclear Safety Solutions Limited (NSS) and the out-reactor flow visualization tests done at Atomic Energy of Canada Limited (AECL) to reproduce the damage observed on irradiated fuel bundles. The bearing pad damage mechanism was identified and the tests showed that a minor change to the fuelling sequence would eliminate the mechanical interaction. The change was implemented in January 2005. Since then, the bearing pad damage appears to have been greatly reduced based on the small number of discharged bundles inspected to date. (author)

ROSFOND based heating-damage cross sections sub-library: Preliminary uncertainty assessment

International Nuclear Information System (INIS)

Sinitsa, V.V.

2016-01-01

The accuracy of radiation damage calculations for the most important LWR component, the reactor pressure vessel (RPV), directly linked with the RPV End-of-Life (EoL) prediction which is in its turn connected with fundamental nuclear safety aspects and relevant economic impacts. In this connection, for nearly ten years the ENEA-Bologna Nuclear Data Group conducts the nuclear data processing and validation activities addressed to update the specialized broad-group coupled neutron/photon working cross section libraries for shielding and radiation damage calculations through NJOY and Bologna revised version of SCAMPI data processing systems. A number of working group-wise data libraries has been prepared and transferred to the ENEA Data Bank for dissemination. Several years ago the NRC ”Kurchatov Institute” has reset the GRUCON project, originally designed to provide group constants for fast nuclear reactor calculations [12], with aim to expand its application area and to use in the WWER safety tasks, in particular, in the RPV radiation damage analyses. By means of updated GRUCON and NJOY-99 processing codes, and calculation procedure, developed in the NDG of ENEA Bologna, a sample of kerma&damage energy point-wise data sub-libraries from different evaluated data libraries has been generated. On the base of this sample, the quantitative assessment of kerma/dpa data precision in the RPV calculations is obtained

Core damage frequency estimation using accident sequence precursor data: 1990-1993

International Nuclear Information System (INIS)

Martz, H.F.

1998-01-01

The Nuclear Regulatory Commission's (NRC's) ongoing Accident Sequence Precursor (ASP) program uses probabilistic risk assessment (PRA) techniques to assess the potential for severe core damage (henceforth referred to simply as core damage) based on operating events. The types of operating events considered include accident sequence initiators, safety equipment failures, and degradation of plant conditions that could increase the probability that various postulated accident sequences occur. Such operating events potentially reduce the margin of safety available for prevention of core damage an thus can be considered as precursors to core damage. The current process for identifying, analyzing, and documenting ASP events is described in detail in Vanden Heuval et al. The significance of a Licensee Event Report (LER) event (or events) is measured by means of the conditional probability that the event leads to core damage, the so-called conditional core damage probability or, simply, CCDP. When the first ASP study results were published in 1982, it covered the period 1969--1979. In addition to identification and ranking of precursors, the original study attempted to estimate core damage frequency (CDF) based on the precursor events. The purpose of this paper is to compare the average annual CDF estimates calculated using the CCDP sum, Cooke-Goossens, Bier, and Abramson estimators for various reactor classes using the combined ASP data for the four years, 1990--1993. An important outcome of this comparison is an answer to the persistent question regarding the degree and effect of the positive bias of the CCDP sum method in practice. Note that this paper only compares the estimators with each other. Because the true average CDF is unknown, the estimation error is also unknown. Therefore, any observations or characterizations of bias are based on purely theoretical considerations

Suppositional analysis for the nuclear accidents at the Fukushima Daiichi Nuclear Power Station

International Nuclear Information System (INIS)

Yoshida, Yoshitaka

2012-01-01

The Great East Japan Earthquake which occurred on March 11, 2011 set off a series of events that have led to a serious nuclear disaster. The Fukushima Daiichi Nuclear Power Station suffered damage due to the huge tsunami waves triggered by the earthquake, which lead to release of large amounts of radioactive materials into the environment. Using the limited information presented by the government and others within several days after the accident, this study examined the amount of radioactive materials released into the atmosphere predicted using the incident progress prediction system (IPPS) and the radioactive release, radiation dose and radiological protection area prediction system (R-Cubic) each developed by INSS, and compared those findings with the amount of radioactive materials evaluated by the government and the Tokyo Electric Power Company. The following points were seen (1) The step-by-step public protection measures taken by the government were consistent with the amount of released radioactive materials by R-Cubic. (2) The IPPS underestimated the amount of released radioactive materials when the irradiation levels in the nuclear reactors were analyzed according to the observed nuclear reactor water levels, although these were well in agreement with the observed parameters. (3) The amounts of released radioactive materials predicted by R-Cubic agreed well with those of the Nuclear Safety Commission and the Nuclear and Industrial Safety Agency. (4) The 0.5MeV equivalent value of noble gases in the amount of radioactive materials released into the atmosphere shown by TEPCO on May 2012 was considered to be an underestimate. (author)

Nuclear Targeting Terms for Engineers and Scientists

Energy Technology Data Exchange (ETDEWEB)

St Ledger, John W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-02-01

The Department of Defense has a methodology for targeting nuclear weapons, and a jargon that is used to communicate between the analysts, planners, aircrews, and missile crews. The typical engineer or scientist in the Department of Energy may not have been exposed to the nuclear weapons targeting terms and methods. This report provides an introduction to the terms and methodologies used for nuclear targeting. Its purpose is to prepare engineers and scientists to participate in wargames, exercises, and discussions with the Department of Defense. Terms such as Circular Error Probable, probability of hit and damage, damage expectancy, and the physical vulnerability system are discussed. Methods for compounding damage from multiple weapons applied to one target are presented.

Reassessing the nuclear liability regime

International Nuclear Information System (INIS)

Havinh Phuong

1985-01-01

The nuclear liability regime was thoroughly reviewed by nuclear plant operators, officials of regulatory authorities, and legal and insurance experts at the Symposium on Nuclear Third Party Liability and Insurance, held in September 1984 in Munich, Federal Republic of Germany. The symposium highlighted specific areas where adjustments or improvements would be needed in order to cope with practical problems encountered or emerging issues. By focusing on questions of legitimate concern to the public, it also sought to promote confidence in a compensation system for public protection that is in many ways unique. Topics addressed included the following: greater harmonization of the compensation amounts for nuclear damage established in different countries and in territorial scope; the concept of unlimited liability; the time limitation for compensation claims; the problem of proving causation; the concept of nuclear damage; and insurance coverage

Compensation for the damage caused by the Chernobyl disaster

International Nuclear Information System (INIS)

Joirysch, A.; Supataeva, O.

1993-01-01

The teachings of the accident at the nuclear power plant of Chernobyl clearly showed that the existing rules of Russian legislation cannot handle the problems in respect of civil liability for nuclear damage. This paper describes how the Soviet State and Soviet law tried to cope with the question of compensation for damage to human health and property in a special legal situation, due to the lack of any particular legislation covering this area and to the fact that the USSR is a Party neither to the Vienna nor the Paris Convention. In 1991 a law of the Russian Federation 'On the social protection of citizens who suffered as a consequence of the Chernobyl disaster' established a State system of services and compensation for such damage and the procedure for financing was laid down by a ministerial letter. 4 refs

Liability for international nuclear transport: an overview

International Nuclear Information System (INIS)

Brown, O.F.; Horbach, N.

2000-01-01

Many elements can bear on liability for nuclear damage during transport. For example, liability may depend upon a number of facts that may be categorized as follows: shipment, origin or destination of the shipment, deviation from the planed route, temporary storage incidental to carriage; content of shipment, type of nuclear material involved, whether its origin is civilian or defence-related; sites of accident, number and type of territories damaged (i.e. potential conventions involved), applicable territorial limits, exclusive economic zone, high seas, etc.; nature of damages, personal injury, property damage, damage to the means of carriage, indirect damage, preventive measures, environmental cleanup or retrieval at seas, res communis, transboundary damages etc.; victims involved, nationality and domiciles of victims; jurisdiction, flag (for ships) or national registration (for aircraft) of the transporting vessel, courts of one or more states may have (or assert) jurisdiction to hear claims, and may have to determine what law to apply to a particular accident; applicable law, the applicability laws and/or international nuclear liability conventions; the extent to which any applicable convention has been implemented or modified by domestic legislation, conflicts with the 1982 Law of the Sea Convention or other applicable international agreements, and finally, also written agreements between installation operators and carriers can define applicable law as well as responsibilities. Harmonizing nuclear liability protection and applying it to additional international shipments would be facilitated by more countries being in treaty relations with each other as soon as possible. Adherence to an international convention by more countries (including China, Russia, the United States, etc.) would promote the open flow of services and advanced technology, and better facilitate international transport. The conventions protect the public, harmonize legislation in the

International Law governing the Safe and Peaceful Uses of Nuclear Energy

International Nuclear Information System (INIS)

Jankowitsch-Prevor, O.

2002-01-01

1. The International Governmental Institutions. History and mandates: IAEA, OECD/NEA, EURATOM. 2. International Treaties and Conventions: The Peaceful Uses of Nuclear Energy: Commitment and Verification (the NPT, Safeguards Agreements with the IAEA, The Additional protocol, Regional Non-proliferation Treaties); the Physical protection of Nuclear Material (Convention on the Physical Protection of Nuclear Material); Civil Liability for Nuclear Damage (Vienna Convention on the Civil Liability for Nuclear Damage, Protocol to Amend the Vienna Convention, Paris Convention on Civil Liability, Joint Protocol relating to the Application of the Vienna Convention and the Paris Convention, Convention on Supplementary compensation for Nuclear Damage); In case of Nuclear Accident: Notification and Assistance (Convention on Early Notification of a Nuclear Accident, Convention on Assistance in the case of a Nuclear Accident or Radiological Emergency); International Law Governing Nuclear Safety (Nuclear Safety Convention, Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management). 3. Relationship between International and National Law

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.

An experimental study on developing seismic damage indicator appearing OBE exceedance

International Nuclear Information System (INIS)

Park, D. S.; Kwon, K. J.; Lee, J. L.

2000-01-01

Immediate measurement should be taken depending on the level of seismic damage to nuclear power plants when an earthquake exceeds Operating Base Earthquake by NRC regulatory guide. An earthquake at nuclear plant site is felt with seismic instrument and analyzed by seismic monitoring systems. However, if operators of insufficient knowledge to earthquake can recognize the intensity of the earthquake with a subsidiary indicating model, more immediate response can be conducted. This subsidiary indicating model is called seismic damage indicator. In this regard, an experimental study using shaking table was conducted to develop the seismic damage indicator by CAV and OBE compatible with NRC standard response spectrum. In this test result, stacked acrylic cylinders were manufactured to behave consistently for each direction of seismic load. If the developed SDI is installed in nuclear power plants, it is seemed to be useful in easily determining OBE exceedance easily, and counteracting by plant operator along with the existing seismic monitoring systems

Introduction of damage in an elasto-plastic model for unsaturated geo-materials

International Nuclear Information System (INIS)

Le Pense, S.; Pouya, A.; Gatmiri, B.

2012-01-01

Document available in extended abstract form only. During the excavation of nuclear waste repository galleries, the surrounding soil is suspected to undergo structural changes as well as modification of its stress state. The desaturation due to ventilation of galleries during this stage makes it necessary to consider the unsaturated state of the host geo-material. The decompression occurring after the excavation leads to a modification of the stress state. The purpose of our work is to develop a mechanical model to simulate the non-linear stress-strain behaviour of geo-materials which will have to contain radioactivity of nuclear waste for a very long time. Two irreversible phenomena can explain the non-linear behaviour of geo-materials. Plasticity leads to irrecoverable strains. Damage, linked to the appearance and extension of microcracks, results in a deterioration of elastic and hydraulic properties. We will present here the bases of a new model coupling damage and plasticity for the stress-strain behaviour of unsaturated geo-materials. This model should be thermodynamically consistent and use only a reasonable number of parameters. Based on the work of Houlsby, (Houlsby 1997), we choose to use as constitutive variables for unsaturated soils Bishop's stress and suction. This choice as the advantage to allow for continuity at the transition between saturated and unsaturated states. Damage is taken into account by defining a damaged constitutive stress, which is similar to the effective stress principle defined by Kachanov (Kachanov 1958). A simple damage criterion is proposed and an associative flow rule is assumed. We choose to follow the principle of strain equivalence defined by Lemaitre (Lemaitre 1996). This leads to the following elasticity law giving the damaged constitutive stress as a function of elastic strain. If non-linear elasticity is considered, a pressure-dependent bulk modulus and a constant shear modulus can be chosen in order to fit

Historical aspects of the nuclear right development

International Nuclear Information System (INIS)

Puig, Diva E.

1999-01-01

This paper analyses the historical aspects of the nuclear right development. It makes the evolution of the fundamental principles of nuclear right, in special, the civil responsibility for nuclear damages. (author)

Heavy ion linear accelerator for radiation damage studies of materials

Energy Technology Data Exchange (ETDEWEB)

Kutsaev, Sergey V.; Mustapha, Brahim; Ostroumov, Peter N.; Nolen, Jerry; Barcikowski, Albert; Pellin, Michael; Yacout, Abdellatif

2017-03-01

A new eXtreme MATerial (XMAT) research facility is being proposed at Argonne National Laboratory to enable rapid in situ mesoscale bulk analysis of ion radiation damage in advanced materials and nuclear fuels. This facility combines a new heavy-ion accelerator with the existing high-energy X-ray analysis capability of the Argonne Advanced Photon Source. The heavy-ion accelerator and target complex will enable experimenters to emulate the environment of a nuclear reactor making possible the study of fission fragment damage in materials. Material scientists will be able to use the measured material parameters to validate computer simulation codes and extrapolate the response of the material in a nuclear reactor environment. Utilizing a new heavy-ion accelerator will provide the appropriate energies and intensities to study these effects with beam intensities which allow experiments to run over hours or days instead of years. The XMAT facility will use a CW heavy-ion accelerator capable of providing beams of any stable isotope with adjustable energy up to 1.2 MeV/u for U-238(50+) and 1.7 MeV for protons. This energy is crucial to the design since it well mimics fission fragments that provide the major portion of the damage in nuclear fuels. The energy also allows damage to be created far from the surface of the material allowing bulk radiation damage effects to be investigated. The XMAT ion linac includes an electron cyclotron resonance ion source, a normal-conducting radio-frequency quadrupole and four normal-conducting multi-gap quarter-wave resonators operating at 60.625 MHz. This paper presents the 3D multi-physics design and analysis of the accelerating structures and beam dynamics studies of the linac.

Heavy ion linear accelerator for radiation damage studies of materials.

Science.gov (United States)

Kutsaev, Sergey V; Mustapha, Brahim; Ostroumov, Peter N; Nolen, Jerry; Barcikowski, Albert; Pellin, Michael; Yacout, Abdellatif

2017-03-01

A new eXtreme MATerial (XMAT) research facility is being proposed at Argonne National Laboratory to enable rapid in situ mesoscale bulk analysis of ion radiation damage in advanced materials and nuclear fuels. This facility combines a new heavy-ion accelerator with the existing high-energy X-ray analysis capability of the Argonne Advanced Photon Source. The heavy-ion accelerator and target complex will enable experimenters to emulate the environment of a nuclear reactor making possible the study of fission fragment damage in materials. Material scientists will be able to use the measured material parameters to validate computer simulation codes and extrapolate the response of the material in a nuclear reactor environment. Utilizing a new heavy-ion accelerator will provide the appropriate energies and intensities to study these effects with beam intensities which allow experiments to run over hours or days instead of years. The XMAT facility will use a CW heavy-ion accelerator capable of providing beams of any stable isotope with adjustable energy up to 1.2 MeV/u for 238 U 50+ and 1.7 MeV for protons. This energy is crucial to the design since it well mimics fission fragments that provide the major portion of the damage in nuclear fuels. The energy also allows damage to be created far from the surface of the material allowing bulk radiation damage effects to be investigated. The XMAT ion linac includes an electron cyclotron resonance ion source, a normal-conducting radio-frequency quadrupole and four normal-conducting multi-gap quarter-wave resonators operating at 60.625 MHz. This paper presents the 3D multi-physics design and analysis of the accelerating structures and beam dynamics studies of the linac.

The potential for vault-induced seismicity in nuclear fuel waste disposal: experience from Canadian mines

International Nuclear Information System (INIS)

Martin, C.D.; Chandler, N.A.

1996-12-01

A seismic event which causes damage to an underground opening is called a rockburst. Practical experience indicates that these damaging seismic events are associated with deep mines where extraction ratios are greater than 0.6. For the arrangement being considered by AECL for nuclear fuel waste disposal vaults, extraction ratios, for the room and pillar design, will be less than 0.3. At this extraction ratio the stress magnitudes will not be sufficient to induce seismic events that can damage the underground openings. Documented world-wide experience shows that unless the underground opening is very close to the source of a naturally occurring seismic event, such as an earthquake, the opening will also not experience any significant damage. Backfilling a disposal vault will improve its resistance to earthquake damage. Backfilling a disposal vault will also reduce the total convergence of the openings caused by thermal loads and hence minimize the potential for thermally-induced seismic events. (author)

Metabolite damage and repair in metabolic engineering design.

Science.gov (United States)

Sun, Jiayi; Jeffryes, James G; Henry, Christopher S; Bruner, Steven D; Hanson, Andrew D

2017-11-01

The necessarily sharp focus of metabolic engineering and metabolic synthetic biology on pathways and their fluxes has tended to divert attention from the damaging enzymatic and chemical side-reactions that pathway metabolites can undergo. Although historically overlooked and underappreciated, such metabolite damage reactions are now known to occur throughout metabolism and to generate (formerly enigmatic) peaks detected in metabolomics datasets. It is also now known that metabolite damage is often countered by dedicated repair enzymes that undo or prevent it. Metabolite damage and repair are highly relevant to engineered pathway design: metabolite damage reactions can reduce flux rates and product yields, and repair enzymes can provide robust, host-independent solutions. Herein, after introducing the core principles of metabolite damage and repair, we use case histories to document how damage and repair processes affect efficient operation of engineered pathways - particularly those that are heterologous, non-natural, or cell-free. We then review how metabolite damage reactions can be predicted, how repair reactions can be prospected, and how metabolite damage and repair can be built into genome-scale metabolic models. Lastly, we propose a versatile 'plug and play' set of well-characterized metabolite repair enzymes to solve metabolite damage problems known or likely to occur in metabolic engineering and synthetic biology projects. Copyright © 2017 International Metabolic Engineering Society. All rights reserved.

Transport of nuclear material under the 1971 Brussels Convention

International Nuclear Information System (INIS)

Lagorce, M.

1975-01-01

The legal regime in force before entry into force of the 1971 Brussels Convention relating to civil liability for the maritime carriage of nuclear material created serious difficulties for maritime carriers, regarding both the financial risks entailed and restrictions on enjoyment of the rights granted by civil liability conventions. The 1971 Convention exonerates from liability any person likely to be held liable for nuclear damage under maritime law, provided another person is liable under the nuclear conventions or an equivalent national law. A problem remaining is that of compensation of nuclear damage to the means of transport for countries not having opted for re-inclusion of such damage in the nuclear law regime; this does not apply however to countries having ratified the Convention to date. A feature of the latter is that it establishes as extensively as possible the priority of nuclear law over maritime law. Furthermore the new regime continues to preserve efficiently the interests of victims of nuclear incidents. It is therefore to be hoped that insurers will no longer hesitate to cover international maritime carriage of nuclear material [fr