WorldWideScience

Sample records for stabilized special nuclear

  1. Data quality objectives for moisture measurement in stabilized special nuclear material

    International Nuclear Information System (INIS)

    Weier, D.R.; Pulsipher, B.A.; Silvers, K.L.

    2000-01-01

    Data Quality Objectives methodology is applied to Loss-on-Ignition (LOI) moisture content testing for stabilized nuclear materials. This work was performed by Pacific Northwest National Laboratory in support of the Plutonium Finishing Plant (PFP)/Fluor Hanford, Inc. Historical results on LOI test results for two material types, oxide and sludge, are used to estimate within container variability. This variability estimate is then used in formulating the two recommended acceptance criteria for containers of material. The criteria which follow are proposed to replace the current criterion, which requires recycle if either of two container LOI measurements exceed 0.5 wt%, the DOE Standard 3013-99 threshold value. (1) The 95% upper confidence limit (UCL) for the true mean underlying moisture content in the container material should be less than 0.5 wt%. (2) The difference between the two LOI measurements per container should not exceed their expected 95th percentile relative to the estimated variability. Containers not meeting the first criterion, or those that generate in any negative LOI result, require material recycle. Containers not meeting the second criteria require review of the measurement results, potentially leading to resampling and retesting. Data from Los Alamos National Laboratory studies on moisture testing are obtained and analyzed. The performance of Supercritical Fluid Extraction (SFE), which will soon be implemented at the PFP, is described for several material types. This information will be used to establish initial acceptance criteria when SFE comes on line

  2. Limits of Nuclear Stability

    CERN Document Server

    Nerlo-Pomorska, B; Kleban, M

    2003-01-01

    The modern version of the liquid-drop model (LSD) is compared with the macroscopic part of the binding energy evaluated within the Hartree-Fock- Bogoliubov procedure with the Gogny force and the relativistic mean field theory. The parameters of a liquid-drop like mass formula which approximate on the average the self-consistent results are compared with other models. The limits of nuclear stability predicted by these models are discussed.

  3. Smuggling special nuclear materials

    International Nuclear Information System (INIS)

    Lazaroiu, Gheorghe

    1999-01-01

    Ever since the collapse of the former Soviet Union reports have circulated with increasing frequency concerning attempts to smuggle materials from that country's civil and military nuclear programs. Such an increase obviously raises a number of concerns (outlined in the author's introduction), chief among which is the possibility that these materials might eventually fall into the hands of proliferant states or terrorist groups. The following issues are presented: significance of materials being smuggled; sources and smuggling routes; potential customers; international efforts to reduce nuclear smuggling; long-term disposition of fissile materials. (author)

  4. Stability, Specialization and Social Recognition

    NARCIS (Netherlands)

    Gilles, R.P.; Lazarova, E.A.; Ruys, P.H.M.

    2006-01-01

    Yang s theory of economic specialization under increasing returns to scale (Yang 2001) is a formal development of the fundamental Smith-Young theorem on the extent of the market and the social division of labor.In this theory specialization and, thus, the social division of labor is firmly embedded

  5. Special issue: the nuclear industry in Europe

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    This special issue contains papers on the following topics: French nuclear policy; nuclear energy development in Europe; nuclear diversification; Alsthom-Atlantique in the nuclear field; 1981 nuclear electricity generation; EDF siting policy; the N4 model of the 1300 MW series; Creys-Malville; the nuclear industry in Europe; pumps in the nuclear industry [fr

  6. Special nuclear material simulation device

    Science.gov (United States)

    Leckey, John H.; DeMint, Amy; Gooch, Jack; Hawk, Todd; Pickett, Chris A.; Blessinger, Chris; York, Robbie L.

    2014-08-12

    An apparatus for simulating special nuclear material is provided. The apparatus typically contains a small quantity of special nuclear material (SNM) in a configuration that simulates a much larger quantity of SNM. Generally the apparatus includes a spherical shell that is formed from an alloy containing a small quantity of highly enriched uranium. Also typically provided is a core of depleted uranium. A spacer, typically aluminum, may be used to separate the depleted uranium from the shell of uranium alloy. A cladding, typically made of titanium, is provided to seal the source. Methods are provided to simulate SNM for testing radiation monitoring portals. Typically the methods use at least one primary SNM spectral line and exclude at least one secondary SNM spectral line.

  7. Nuclear reactor core stabilizing arrangement

    International Nuclear Information System (INIS)

    Jabsen, F.S.

    1976-01-01

    A nuclear reactor core stabilizing arrangement is described wherein a plurality of actuators, disposed in a pattern laterally surrounding a group of elongated fuel assemblies, press against respective contiguous fuel assemblies on the periphery of the group to reduce the clearance between adjacent fuel assemblies thereby forming a more compacted, vibration resistant core structure. 7 claims, 4 drawing figures

  8. Control of Nuclear Materials and Special Equipment (Nuclear Safety Regulations)

    International Nuclear Information System (INIS)

    Cizmek, A.; Prah, M.; Medakovic, S.; Ilijas, B.

    2008-01-01

    Based on Nuclear Safety Act (OG 173/03) the State Office for Nuclear Safety (SONS) in 2008 adopted beside Ordinance on performing nuclear activities (OG 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (OG 74/06) the new Ordinance on the control of nuclear material and special equipment (OG 15/08). Ordinance on the control of nuclear material and special equipment lays down the list of nuclear materials and special equipment as well as of nuclear activities covered by the system of control of production of special equipment and non-nuclear material, the procedure for notifying the intention to and filing the application for a license to carry out nuclear activities, and the format and contents of the forms for doing so. This Ordinance also lays down the manner in which nuclear material records have to be kept, the procedure for notifying the State administration organization (regulatory body) responsible for nuclear safety by the nuclear material user, and the keeping of registers of nuclear activities, nuclear material and special equipment by the State administration organization (regulatory body) responsible for nuclear safety, as well as the form and content of official nuclear safety inspector identification card and badge.(author)

  9. Safeguards for special nuclear materials

    International Nuclear Information System (INIS)

    Carlson, R.L.

    1979-12-01

    Safeguards, accountability, and nuclear materials are defined. The accuracy of measuring nuclear materials is discussed. The use of computers in nuclear materials accounting is described. Measures taken to physically protect nuclear materials are described

  10. Nuclear astrophysics away from stability

    International Nuclear Information System (INIS)

    Mathews, G.J.; Howard, W.M.; Takahashi, K.; Ward, R.A.

    1985-08-01

    Explosive astrophysical environments invariably lead to the production of nuclei away from stability. An understanding of the dynamics and nucleosynthesis in such environments is inextricably coupled to an understanding of the properties of the synthesized nuclei. In this talk a review is presented of the basic explosive nucleosynthesis mechanisms (s-process, r-process, n-process, p-process, and rp-process). Specific stellar model calculations are discussed and a summary of the pertinent nuclear data is presented. Possible experiments and nuclear-model calculations are suggested that could facilitate a better understanding of the astrophysical scenarios. 39 refs., 4 figs

  11. Special monitoring in nuclear medicine

    International Nuclear Information System (INIS)

    Beltran, C.C.; Puerta, J.A.; Morales, J.

    2006-01-01

    Colombia counts with around 56 centers of Nuclear Medicine, 70 Nuclear Doctors and more of 100 Technologists in this area. The radioisotopes more used are the 131 I and the 99m Tc. The radiological surveillance singular in the country is carried out for external dosimetry, being the surveillance by incorporation of radioactive materials very sporadic in our media. Given the necessity to implement monitoring programs in the incorporation of radionuclides of the occupationally exposed personnel, in the routine practice them routine of Nuclear Medicine, it was implemented a pilot program of Special Monitoring with two centers of importance in the city of Medellin. This program it was carried out with the purpose of educating, to stimulate and to establish a program of reference monitoring with base in the National Program of Monitoring in the radionuclides Incorporation that serves like base for its application at level of all the services of Nuclear Medicine in the country. This monitoring type was carried out with the purpose of obtaining information on the work routine in these centers, form of manipulation and dosage of the radionuclides, as well as the administration to the patient. The application of the program was carried out to define the frequency of Monitoring and analysis technique for the implementation of a program of routine monitoring, following the recommendations of the International Commission of Radiological Protection. For their application methods of activity evaluation were used in urine and in 7 workers thyroid, of those which only two deserve an analysis because they presented important activities. The measures were carried out during one month, every day by means in urine samples and to the most critic case is practiced two thyroid measures, one in the middle of the period and another when concluding the monitoring. To the other guy is practiced an activity count in thyroid when concluding the monitoring period. The obtained result of the

  12. Prospects for stability in a nuclear subcontinent

    International Nuclear Information System (INIS)

    Rajagopal, S; Chari, Sridhar K.

    2003-01-01

    This book explore the prospects for stability in a nuclear sub-continent. The nonproliferation regimes and nuclear threat reduction, nonproliferation regimes and south asia - is there a meeting point?; maintaining a threshold of strategic autonomy at least cost: continuity in the evolution of India's nuclear policies; role of nuclear doctrines and the state of the armed forces in South Asia; nuclear weapons, deterrence and stability in the international system: South Asian dynamics; assessing China's Asian role and security policies; Kargil war to current threat of war: prospects for stability; discussion; international terrorism and its impact on South Asian stability; a view from Bangladesh etc. are some of the topics covered

  13. Estimation methods for special nuclear materials holdup

    International Nuclear Information System (INIS)

    Pillay, K.K.S.; Picard, R.R.

    1984-01-01

    The potential value of statistical models for the estimation of residual inventories of special nuclear materials was examined using holdup data from processing facilities and through controlled experiments. Although the measurement of hidden inventories of special nuclear materials in large facilities is a challenging task, reliable estimates of these inventories can be developed through a combination of good measurements and the use of statistical models. 7 references, 5 figures

  14. Gamma spectrometric discrimination of special nuclear materials

    International Nuclear Information System (INIS)

    Dowdall, M.; Mattila, A.; Ramebaeck, H.; Aage, H.K.; Palsson, S.E.

    2012-12-01

    This report presents details pertaining to an exercise conducted as part of the NKS-B programme using synthetic gamma ray spectra to simulate the type of data that may be encountered in the interception of material potentially containing special nuclear materials. A range of scenarios were developed involving sources that may or may not contain special nuclear materials. Gamma spectral data was provided to participants as well as ancillary data and participants were asked, under time constraint, to determine whether or not the data was indicative of circumstances involving special nuclear materials. The situations varied such that different approaches were required in order to obtain the correct result in each context. In the majority of cases participants were able to correctly ascertain whether or not the situations involved special nuclear material. Although fulfilling the primary goal of the exercise, some participants were not in a position to correctly identify with certainty the material involved, Situations in which the smuggled material was being masked by another source proved to be the most challenging for participants. (Author)

  15. Gamma spectrometric discrimination of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Dowdall, M. [Norwegian Radiation Protection Authority (Norway); Mattila, A. [Radiation and Nuclear Safety Authority, Helsinki (Finland); Ramebaeck, H. [Swedish Defence Research Agency, Stockholm (Sweden); Aage, H.K. [Danish Emergency Management Agency, Birkeroed (Denmark); Palsson, S.E. [Icelandic Radiation Safety Authority, Reykjavik (Iceland)

    2012-12-15

    This report presents details pertaining to an exercise conducted as part of the NKS-B programme using synthetic gamma ray spectra to simulate the type of data that may be encountered in the interception of material potentially containing special nuclear materials. A range of scenarios were developed involving sources that may or may not contain special nuclear materials. Gamma spectral data was provided to participants as well as ancillary data and participants were asked, under time constraint, to determine whether or not the data was indicative of circumstances involving special nuclear materials. The situations varied such that different approaches were required in order to obtain the correct result in each context. In the majority of cases participants were able to correctly ascertain whether or not the situations involved special nuclear material. Although fulfilling the primary goal of the exercise, some participants were not in a position to correctly identify with certainty the material involved, Situations in which the smuggled material was being masked by another source proved to be the most challenging for participants. (Author)

  16. India-Pakistan: nuclear stability and diplomacy

    International Nuclear Information System (INIS)

    Mishra, Rajesh Kumar

    2005-01-01

    The conceptual discourse, contributed to in the main by Western scholars, on the security and strategic stability of new nuclear weapon states like India and Pakistan seems alarmist. In reality, however, India and Pakistan have been mutually deliberating on various aspects of nuclear confidence-building measures (CBMs). This article is an effort to identify the issues of nuclear security concerns in two spheres - academic and policy formulations. The emphasis is more on the nuclear thinking of the two countries and the diplomatic challenges ahead particularly on the nuclear CBMs. (author)

  17. 10 CFR 74.51 - Nuclear material control and accounting for strategic special nuclear material.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for strategic special nuclear material. 74.51 Section 74.51 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Formula Quantities of Strategic Special Nuclear...

  18. Some political issues related to future special nuclear materials production

    International Nuclear Information System (INIS)

    Peaslee, A.T. Jr.

    1981-08-01

    The Federal Government must take action to assure the future adequate supply of special nuclear materials for nuclear weapons. Existing statutes permit the construction of advanced defense production reactors and the reprocessing of commercial spent fuel for the production of special materials. Such actions would not only benefit the US nuclear reactor manufacturers, but also the US electric utilities that use nuclear reactors

  19. Preface: Special Topic on Nuclear Quantum Effects.

    Science.gov (United States)

    Tuckerman, Mark; Ceperley, David

    2018-03-14

    Although the observable universe strictly obeys the laws of quantum mechanics, in many instances, a classical description that either ignores quantum effects entirely or accounts for them at a very crude level is sufficient to describe a wide variety of phenomena. However, when this approximation breaks down, as is often the case for processes involving light nuclei, a full quantum treatment becomes indispensable. This Special Topic in The Journal of Chemical Physics showcases recent advances in our understanding of nuclear quantum effects in condensed phases as well as novel algorithmic developments and applications that have enhanced the capability to study these effects.

  20. Preface: Special Topic on Nuclear Quantum Effects

    Science.gov (United States)

    Tuckerman, Mark; Ceperley, David

    2018-03-01

    Although the observable universe strictly obeys the laws of quantum mechanics, in many instances, a classical description that either ignores quantum effects entirely or accounts for them at a very crude level is sufficient to describe a wide variety of phenomena. However, when this approximation breaks down, as is often the case for processes involving light nuclei, a full quantum treatment becomes indispensable. This Special Topic in The Journal of Chemical Physics showcases recent advances in our understanding of nuclear quantum effects in condensed phases as well as novel algorithmic developments and applications that have enhanced the capability to study these effects.

  1. Special nuclear material inventory sampling plans

    International Nuclear Information System (INIS)

    Vaccaro, H.; Goldman, A.

    1987-01-01

    Since their introduction in 1942, sampling inspection procedures have been common quality assurance practice. The U.S. Department of Energy (DOE) supports such sampling of special nuclear materials inventories. The DOE Order 5630.7 states, Operations Offices may develop and use statistically valid sampling plans appropriate for their site-specific needs. The benefits for nuclear facilities operations include reduced worker exposure and reduced work load. Improved procedures have been developed for obtaining statistically valid sampling plans that maximize these benefits. The double sampling concept is described and the resulting sample sizes for double sample plans are compared with other plans. An algorithm is given for finding optimal double sampling plans that assist in choosing the appropriate detection and false alarm probabilities for various sampling plans

  2. Radioactive decays at limits of nuclear stability

    DEFF Research Database (Denmark)

    Pfützner, M.; Karny, M.; Grigorenko, L. V.

    2012-01-01

    , and their relative probabilities. When approaching limits of nuclear stability, new decay modes set in. First, beta decays are accompanied by emission of nucleons from highly excited states of daughter nuclei. Second, when the nucleon separation energy becomes negative, nucleons start being emitted from the ground...

  3. Integrating the stabilization of nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Dalton, H.F. [Department of Energy, Washington, DC (United States)

    1996-05-01

    In response to Recommendation 94-1 of the Defense Nuclear Facilities Safety Board, the Department of Energy committed to stabilizing specific nuclear materials within 3 and 8 years. These efforts are underway. The Department has already repackaged the plutonium at Rocky Flats and metal turnings at Savannah River that had been in contact with plastic. As this effort proceeds, we begin to look at activities beyond stabilization and prepare for the final disposition of these materials. To describe the plutonium materials being stabilize, Figure 1 illustrates the quantities of plutonium in various forms that will be stabilized. Plutonium as metal comprises 8.5 metric tons. Plutonium oxide contains 5.5 metric tons of plutonium. Plutonium residues and solutions, together, contain 7 metric tons of plutonium. Figure 2 shows the quantity of plutonium-bearing material in these four categories. In this depiction, 200 metric tons of plutonium residues and 400 metric tons of solutions containing plutonium constitute most of the material in the stabilization program. So, it is not surprising that much of the work in stabilization is directed toward the residues and solutions, even though they contain less of the plutonium.

  4. Stability of nuclear crater slopes in rock

    International Nuclear Information System (INIS)

    Fleming, Robert W.; Frandsen, Alton D.; LaFrenz, Robert L.

    1970-01-01

    The United States Army Engineer Nuclear Cratering Group was established in 1962 to participate with the Atomic Energy Commission in a joint research and development program to develop nuclear engineering and construction technology. A major part of this research effort has been devoted to studies of the engineering properties of craters. The program to date has included field investigations of crater properties in various media over a broad range of chemical and nuclear explosive yields, studies of man-made and natural slopes, and studies directed toward the development of analytical and empirical methods of crater stability analysis. From this background, a general understanding has been developed of the effects of a cratering explosion on the surrounding medium and of physical nature of the various crater zones which are produced. The stability of nuclear crater slopes has been a subject of prime interest in the feasibility study being conducted for an Atlantic-Pacific sea-level canal. Based on experimental evidence assembled to date, nuclear crater slopes in dry dock and dry alluvium have an initially stable configuration. There have been five nuclear craters produced to date with yields of 0.4 kt or more on which observations are based and the initial configurations of these craters have remained stable for over seven years. The medium, yield, crater dimensions, and date of event for these craters are summarized. It is interesting to note that the Sedan Crater has been subjected to strong seismic motions from nearby detonations without adverse effects

  5. Stability of nuclear crater slopes in rock

    Energy Technology Data Exchange (ETDEWEB)

    Fleming, Robert W; Frandsen, Alton D; LaFrenz, Robert L [U.S. Army Engineer Nuclear Cratering Group, Lawrence Radiation Laboratory, Livermore, CA (United States)

    1970-05-15

    The United States Army Engineer Nuclear Cratering Group was established in 1962 to participate with the Atomic Energy Commission in a joint research and development program to develop nuclear engineering and construction technology. A major part of this research effort has been devoted to studies of the engineering properties of craters. The program to date has included field investigations of crater properties in various media over a broad range of chemical and nuclear explosive yields, studies of man-made and natural slopes, and studies directed toward the development of analytical and empirical methods of crater stability analysis. From this background, a general understanding has been developed of the effects of a cratering explosion on the surrounding medium and of physical nature of the various crater zones which are produced. The stability of nuclear crater slopes has been a subject of prime interest in the feasibility study being conducted for an Atlantic-Pacific sea-level canal. Based on experimental evidence assembled to date, nuclear crater slopes in dry dock and dry alluvium have an initially stable configuration. There have been five nuclear craters produced to date with yields of 0.4 kt or more on which observations are based and the initial configurations of these craters have remained stable for over seven years. The medium, yield, crater dimensions, and date of event for these craters are summarized. It is interesting to note that the Sedan Crater has been subjected to strong seismic motions from nearby detonations without adverse effects.

  6. Technology development for special nuclear components

    International Nuclear Information System (INIS)

    Sanatkumar, A.

    1994-01-01

    One of the attractive features of Candu Pressurised Heavy Water Reactor design which influenced the decision to make it the foundation of our nuclear power programme, is that its main components (calandria, end shields, coolant channel components) are relatively simple - in comparison with reactor pressure vessel and associated components of Boiling Water Reactors or Pressurised Water Reactors - and considered to be within the scope of manufacture of developing countries. Over the last two decades, India has been very successful in technology development in many important and critical areas. We are now about to launch the construction of the first 500 MWe PHWR project at Tarapur. In this context, this paper focuses attention on some of the aspects relating to self-reliance in design, engineering and manufacture of these special components as currently perceived. (author). 3 refs

  7. Nuclear responses in INTOR plasma stabilization elements

    International Nuclear Information System (INIS)

    Gohar, Y.; Gilligan, J.; Jung, J.; Mattas, R.F.; Miley, G.H.; Wiffen, F.W.; Yang, S.

    1985-01-01

    Nuclear responses in the plasma stabilization elements were studied in a parametric fashion as a part of the transient electromagnetics critical issue C of ETR/INTOR activity. The main responses are neutron fluence and radiation dose in the insulator material, induced resistivity and atomic displacement in the conductor material, nuclear heating and life analysis for the elements. Copper and aluminum conductors with either MgAl 2 O 4 or MgO insulating material were investigated. Radiation damage and life analysis for these elements were also discussed

  8. Current status and improvement of the nuclear physics experiment course for speciality of nuclear physics and nuclear technology

    International Nuclear Information System (INIS)

    Qu Guopu; Guo Lanying

    1999-01-01

    The author reviews the current status of the nuclear physics experiment course for speciality of nuclear physics and nuclear technology in higher education and expresses author's views on the future improvement of the nuclear physics experiment course

  9. Search for greater stability in nuclear regulation

    International Nuclear Information System (INIS)

    Asselstine, J.K.

    1985-01-01

    The need for greater stability in nuclear regulation is discussed. Two possible approaches for dealing with the problems of new and rapidly changing regulatory requirements are discussed. The first approach relies on the more traditional licensing reform initiatives that have been considered off and on for the past decade. The second approach considers a new regulator philosophy aimed at the root causes of the proliferation of new safety requirements that have been imposed in recent years. For the past few years, the concepts of deregulation and regulatory reform have been in fashion in Washington, and the commercial nuclear power program has not remained unaffected. Many look to these concepts to provide greater stability in the regulatory program. The NRC, the nuclear industry and the administration have all been avidly pursuing regulatory reform initiatives, which take the form of both legislative and administrative proposals. Many of these proposals look to the future, and, if adopted, would have little impact on currently operating nuclear power plants or plants now under construction

  10. Considerations about the licensing process of special nuclear industrial facilities

    Energy Technology Data Exchange (ETDEWEB)

    Talarico, M.A., E-mail: talaricomarco@hotmail.com [Marinha do Brasil, Rio de Janeiro, RJ (Brazil). Coordenacao do Porgrama de Submarino com Propulsao Nuclear; Melo, P.F. Frutuoso e [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2015-07-01

    This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

  11. Considerations about the licensing process of special nuclear industrial facilities

    International Nuclear Information System (INIS)

    Talarico, M.A.; Melo, P.F. Frutuoso e

    2015-01-01

    This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

  12. IAEA to hold special session on nuclear terrorism

    International Nuclear Information System (INIS)

    2001-01-01

    Experts from around the world are meeting at the IAEA this week for an international symposium on nuclear safeguards, verification, and security. A special session on 2 November focuses on the issue of combating nuclear terrorism. The Special Session, which will bring together experts on nuclear terrorism from around the world, will deal with the following issues: The Psychology of terrorism; Intelligence, police and border protection; Guarding nuclear reactors and material from terrorists and thieves; The threat of nuclear terrorism: Nuclear weapons or other nuclear explosive devices; The threat of nuclear terrorism: Intentional dispersal of radioactive material - Sabotage of fixed installations or transport systems; The Legal Framework: Treaties and Conventions, Laws; Regulations and Codes of Practice; IAEA Nuclear Security and Safety Programmes

  13. Do nuclear engineering educators have a special responsibility

    International Nuclear Information System (INIS)

    Weinberg, A.M.

    1977-01-01

    Each 1000 MW(e) reactor in equilibrium contains 15 x 10 9 Ci of radioactivity. To handle this material safety requires an extremely high level of expertise and commitment - in many respects, an expertise that goes beyond what is demanded of any other technology. If one grants that nuclear engineering is more demanding than other engineering because the price of failure is greater, one must ask how can we inculcate into the coming generations of nuclear engineers a full sense of the responsibility they bear in practising their profession. Clearly a first requirement is that all elements of the nuclear community -utility executives, equipment engineers, operating engineers, nuclear engineers, administrators - must recognize and accept the idea that nuclear energy is something special, and that therefore its practitioners must be special. This sense must be instilled into young nuclear engineers during their education. A special responsibility therefore devolves upon nuclear engineering educators: first, to recognize the special character of their profession, and second, to convey this sense to their students. The possibility of institutionalizing this sense of responsibility by establishing a nuclear Hippocratic Oath or special canon of ethics for nuclear engineers ought to be discussed within the nuclear community. (author)

  14. Special monitoring in nuclear medicine; Monitoreo especial en medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Beltran, C.C.; Puerta, J.A.; Morales, J. [Asociacion Colombiana de Proteccion Radiologica (Colombia)]. e-mail: ccbeltra@gmail.com

    2006-07-01

    Colombia counts with around 56 centers of Nuclear Medicine, 70 Nuclear Doctors and more of 100 Technologists in this area. The radioisotopes more used are the {sup 131} I and the {sup 99m} Tc. The radiological surveillance singular in the country is carried out for external dosimetry, being the surveillance by incorporation of radioactive materials very sporadic in our media. Given the necessity to implement monitoring programs in the incorporation of radionuclides of the occupationally exposed personnel, in the routine practice them routine of Nuclear Medicine, it was implemented a pilot program of Special Monitoring with two centers of importance in the city of Medellin. This program it was carried out with the purpose of educating, to stimulate and to establish a program of reference monitoring with base in the National Program of Monitoring in the radionuclides Incorporation that serves like base for its application at level of all the services of Nuclear Medicine in the country. This monitoring type was carried out with the purpose of obtaining information on the work routine in these centers, form of manipulation and dosage of the radionuclides, as well as the administration to the patient. The application of the program was carried out to define the frequency of Monitoring and analysis technique for the implementation of a program of routine monitoring, following the recommendations of the International Commission of Radiological Protection. For their application methods of activity evaluation were used in urine and in 7 workers thyroid, of those which only two deserve an analysis because they presented important activities. The measures were carried out during one month, every day by means in urine samples and to the most critic case is practiced two thyroid measures, one in the middle of the period and another when concluding the monitoring. To the other guy is practiced an activity count in thyroid when concluding the monitoring period. The obtained

  15. 78 FR 38739 - Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants

    Science.gov (United States)

    2013-06-27

    ... Systems for Nuclear Power Plants AGENCY: Nuclear Regulatory Commission. ACTION: Regulatory guide; issuance... Guide (RG) 5.29, ``Special Nuclear Material Control and Accounting Systems for Nuclear Power Plants... material control and accounting. This guide applies to all nuclear power plants. ADDRESSES: Please refer to...

  16. Report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1977-08-01

    Information concerning accounting for significant quantities of strategic special nuclear material (SSNM) in ERDA facilities is reported. Inventory difference data are provided for fiscal year 1976 for ERDA and ERDA contractor facilities that possessed significant quantities of SSNM

  17. Special nuclear material information, security classification guidance. Instruction

    International Nuclear Information System (INIS)

    Flickinger, A.

    1982-01-01

    The Instruction reissues DoD Instruction 5210.67, July 5, 1979, and provides security classification guidance for information concerning significant quantities of special nuclear material, other than that contained in nuclear weapons and that used in the production of energy in the reactor plant of nuclear-powered ships. Security classification guidance for these data in the latter two applications is contained in Joint DoE/DoD Nuclear Weapons Classification Guide and Joint DoE/DoD Classification Guide for the Naval Nuclear Propulsion Program

  18. Special requirements for bolting material for nuclear and other special applications

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    A specification that provides special requirements for bolting material for use in nuclear and other special applications is presented. The requirements of the specification are supplemental to the requirements of the basic material specifications and they include tempering, welding, elimination of surface defects, certification and identification, quality assurance and various examination methods

  19. 10 CFR 74.41 - Nuclear material control and accounting for special nuclear material of moderate strategic...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special nuclear material of moderate strategic significance. 74.41 Section 74.41 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIAL NUCLEAR MATERIAL Special Nuclear Material...

  20. Manufacture of the 300 MW steam generator and pressure stabilizer for Qinshan Nuclear Power Station

    International Nuclear Information System (INIS)

    Qian Yi; Miao Deming.

    1989-01-01

    A brief description of the manufacturing process of the steam generator and pressure stabilizer for 300 MWe Qinshan Nuclear Power Station in Shanghai Boiler Works is presented, with special emphasis on fabrication facilities, test procedures and technological evaluations during the manufaturing process-imcluding deep driling of tubesheets, welding of tubes to tube-sheets and tube rolling tests

  1. Annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1991-01-01

    This report of unclassified Inventory Difference (ID's) covers the twelve months from April 1, 1989 through March 31, 1990 for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear material. Classified information is not included in this report. This classified information includes data for the Rocky Flats and Y-12 nuclear weapons production facilities or facilities under ID investigation. However, classified ID data from such facilities receive the same scrutiny and analyses was the included data. The data in this report have been prepared and reviewed by DOE contractors, field offices, and Headquarters. When necessary, special investigations have been performed in addition to these reviews: This ID data, explanations, reviews, and any additional special investigations, together with the absence of physical indications of any theft attempt, support a finding that no theft or diversion of significant quantities of strategic special nuclear material has occurred in DOE facilities during the twelve-month period covered by this report

  2. Special nuclear material inventory sampling plans

    International Nuclear Information System (INIS)

    Vaccaro, H.S.; Goldman, A.S.

    1987-01-01

    This paper presents improved procedures for obtaining statistically valid sampling plans for nuclear facilities. The double sampling concept and methods for developing optimal double sampling plans are described. An algorithm is described that is satisfactory for finding optimal double sampling plans and choosing appropriate detection and false alarm probabilities

  3. Special feature article-very urgent nuclear energy personnel training

    International Nuclear Information System (INIS)

    Saito, Shinzo; Tsujikura, Yonezo; Kawahara, Akira

    2007-01-01

    Securing human resources is important for the sustainable development of research, development and utilization of nuclear energy. However, concerns have been raised over the maintenance of human resources due to the decline of public and private investment in research and development of nuclear energy in recent years. To that end, it is essential for the workplace in the field of nuclear energy to be engaging. This special feature article introduced the Government's fund program supporting universities and vocational colleges to develop human resources in the area of nuclear energy. Electric utilities, nuclear industries, nuclear safety regulators and related academia presented respective present status and issues of nuclear energy personnel training with some expectations to the program to secure human resources with professional qualifications. (T. Tanaka)

  4. Construction of special structures for nuclear power projects

    International Nuclear Information System (INIS)

    Raghavan, N.

    2003-01-01

    Construction is a very important stage in the course of realization of Nuclear Power Projects and as much care has be devoted to this stage as to the planning and engineering stages. While the setting up of nuclear power projects used to take over seven years in the past, the time period has now been considerably reduced to about five years with advancements in construction engineering, project management and design techniques, on the basis of new initiatives from the owner agency, Nuclear Power Corporation of India. In this article, the constructional aspects of the specialized structures for nuclear power generation are looked into. (author)

  5. Microchannel plate special nuclear materials sensor

    International Nuclear Information System (INIS)

    Feller, W.B.; White, P.L.; White, P.B.; Siegmund, O.H.W.; Martin, A.P.; Vallerga, J.V.

    2011-01-01

    Nova Scientific Inc., is developing for the Domestic Nuclear Detection Office (DNDO SBIR no. HSHQDC-08-C-00190), a solid-state, high-efficiency neutron detection alternative to 3 He gas tubes, using neutron-sensitive microchannel plates (MCPs) containing 10 B and/or Gd. This work directly supports DNDO development of technologies designed to detect and interdict nuclear weapons or illicit nuclear materials. Neutron-sensitized MCPs have been shown theoretically and more recently experimentally, to be capable of thermal neutron detection efficiencies equivalent to 3 He gas tubes. Although typical solid-state neutron detectors typically have an intrinsic gamma sensitivity orders of magnitude higher than that of 3 He gas detectors, we dramatically reduce gamma sensitivity by combining a novel electronic coincidence rejection scheme, employing a separate but enveloping gamma scintillator. This has already resulted in a measured gamma rejection ratio equal to a small 3 He tube, without in principle sacrificing neutron detection efficiency. Ongoing improvements to the MCP performance as well as the coincidence counting geometry will be described. Repeated testing and validation with a 252 Cf source has been underway throughout the Phase II SBIR program, with ongoing comparisons to a small commercial 3 He gas tube. Finally, further component improvements and efforts toward integration maturity are underway, with the goal of establishing functional prototypes for SNM field testing.

  6. Construction of nuclear special information service

    International Nuclear Information System (INIS)

    Oh, Jeong Hoon; Kim, Tae Whan; Lee, Kyu Jeong; Yi, Ji Ho; Chun, Young Choon; Yoo, Jae Bok; Yoo, An Na

    2009-02-01

    Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country,and technical assistance for domestic end-users using INIS database. Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB, INIS online database, INIS SDI service, and non-conventional literature delivery services. INIS2 DB Host site in Korea has serviced users of domestic and INIS member countries. In order to maintain the same data as Vienna center, the data update process has been performed. Also, publicity information activities were performed by many ways. To construct digital information infrastructure, we changed web server of NUCLIS21 and upgraded information management manager system and constructed full text DB on research and technical reports. Also we collected web DB, digital journals and so on and made an effort on operation of knowledge management system and research documents management. We have inputted over 3,000 records per year since 2002 and the input amount this year has reached 3,738 records. In order to input the comprehensive domestic publication related to nuclear energy, and rise in position of the national center, it is necessary to continue efforts and support budgets. We expect the INIS2 DB Host site will make a contribution to the improvement of productivity in the nuclear energy research as well as the diffusion of information about nuclear energy. We provided users with stable services changing web server of NUCLIS21. Also we contributed to the improvement of librarians' productivity by upgrading information management manager system and provided users with services of web DB, digital journals and so on

  7. Construction of nuclear special information service

    International Nuclear Information System (INIS)

    Oh, Jeong Hoon; Kim, Tae Whan; Yi, Ji Ho; Chun, Young Choon; Yoo, Jae Bok; Yoo, An Na; Choi, Heon Soo

    2012-01-01

    Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB, INIS online database, INIS SDI service, and non-conventional literature delivery services. INIS2 DB Host site in Korea has serviced users of domestic and INIS member countries. In order to maintain the same data as Vienna center, the data update process has been performed. Also, publicity information activities were performed by many ways. To construct digital information infrastructure, we changed web server of KORNIS21 and we reconstruct digital library system as separation of KAERI network system. We constructed patent trend analysis system and new SDI service system. Also we collected Web DB, digital journals and so on and made an effort on operation of knowledge management system and research documents management. We have inputted over 4,000 records per year since 2009 and the input amount this year has reached 4,284 records. In order to input the comprehensive domestic publication related to nuclear energy, and rise in position of the national center, it is necessary to continue efforts and support budgets. We expect the INIS2 DB Host site will make a contribution to the improvement of productivity in the nuclear energy research as well as the diffusion of information about nuclear energy. We provided users with stable services changing web server of KORNIS21. Also we contributed to the improvement of researcher's productivity by constructing patent trend analysis system, new SDI service system and provided users with services

  8. Build of virtual instrument laboratory related to nuclear species specialized

    International Nuclear Information System (INIS)

    Shan Jian; Zhao Guizhi; Zhao Xiuliang; Tang Lingzhi

    2009-01-01

    As rapid development of specialized related to nuclear science,the requirement of laboratory construct is analyzed in this article at first, One total conceive, One scheme deploy soft and hardware,three concrete characteristics targets and five different phases of put in practice of virtual instrument laboratory of specialized related to nuclear science are suggest in the paper,the concrete hardware structure and the headway of build of virtual instrument laboratory are described,and the first step effect is introduced.Lastly,the forward target and the further deliberateness that the virtual instrument laboratory construct are set forth in the thesis. (authors)

  9. Activities of the ANS special committee on nuclear nonproliferation

    Energy Technology Data Exchange (ETDEWEB)

    Buckner, M.R. [Westinghouse Savannah River Co., Aiken, SC (United States); Sanders, T.L. [Sandia National Labs., Albuquerque, NM (United States)

    2001-07-01

    The American Nuclear Society (ANS) Special Committee on Nuclear Nonproliferation (SCNN) believes that to reverse current trends, U.S. policy must revisit the fundamental premise of Atoms for Peace: A collaborative nuclear enterprise enhances rather than diminishes national security. To accomplish this, the U.S. Government must develop an integrated policy on energy, nuclear technology, and national security. The policy must recognize that these are interrelated and that an integrated policy will require substantial investments in nuclear research and development and in nuclear education. This paper describes the current activities of the SCNN to heighten awareness of nonproliferation issues for decision makers and ANS members, and alert them to the need for action to resolve these concerns. (author)

  10. Activities of the ANS special committee on nuclear nonproliferation

    International Nuclear Information System (INIS)

    Buckner, M.R.; Sanders, T.L.

    2001-01-01

    The American Nuclear Society (ANS) Special Committee on Nuclear Nonproliferation (SCNN) believes that to reverse current trends, U.S. policy must revisit the fundamental premise of Atoms for Peace: A collaborative nuclear enterprise enhances rather than diminishes national security. To accomplish this, the U.S. Government must develop an integrated policy on energy, nuclear technology, and national security. The policy must recognize that these are interrelated and that an integrated policy will require substantial investments in nuclear research and development and in nuclear education. This paper describes the current activities of the SCNN to heighten awareness of nonproliferation issues for decision makers and ANS members, and alert them to the need for action to resolve these concerns. (author)

  11. Physical protection of facilities and special nuclear materials in france

    International Nuclear Information System (INIS)

    Jeanpierre, G.

    1980-01-01

    Physical protection of nuclear facilities and special nuclear materials is subject in France to a national governmental regulation which provides for the basic principles to be taken into account and the minimal level of protection deemed necessary. But the responsibility of implementation is left to the facility management and the resulting decentralization allows for maximum efficiency. All safeguards measures comply with the commitments taken at the international level by the French government

  12. A Program to Stabilize Nuclear Materials as Managed by the Plutonium Focus Area

    International Nuclear Information System (INIS)

    Kenley, B.; Scott, B.; Seidel, B.; Knecht, D.; Southworth, F.; Osborne, K.; Chipman, N.; Creque, T.

    1999-01-01

    This paper describes the program to stabilize nuclear materials, consistent with the Department of Energy Office of Environmental Management (EM) plan, Accelerating Cleanup: Paths to Closure. The program is managed by the Plutonium Stabilization and Disposition Focus Area, which defines and manages technology development programs to stabilize nuclear materials and assure their subsequent safe storage and final disposition. The scope of the Plutonium Stabilization and Disposition Focus Area (PFA) activities includes non-weapons plutonium materials, special isotopes, and other fissile materials. The PFA provides solutions to site-specific and complex wide technology issues associated with plutonium remediation, stabilization, and preparation for disposition. Our paper describes an important programmatic function of the Department of Energy nuclear materials stabilization program, including the tie-in of policy to research needs and funding for the nuclear materials disposition area. The PFA uses a rigorous systems engineering determination of technology needs and gaps, under the guidance of a Technical Advisory Panel, consisting of complex-wide experts. The Research and Development planning provides an example for other waste areas and should be of interest to Research and Development managers. The materials disposition maps developed by the PFA and described in this paper provide an evaluation of research needs, data gaps and subsequent guidance for the development of technologies for nuclear materials disposition. This paper also addresses the PFA prioritization methodology and its ability to forecast actual time to implementation

  13. Semiannual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1987-07-01

    This twentieth periodic semiannual report of unclassified Inventory Differences (ID's) covers the second six months of fiscal year 1986 (April 1, 1986, through September 30, 1986) for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic special nuclear materials. Data for the Rocky Flats and Y-12 nuclear weapons production facilities are not included in the report in order to protect classified nuclear weapons information; however, classified ID data from these facilities receive the same scrutiny and analyses as the unclassified data

  14. 10 CFR 70.11 - Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory...

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Persons using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission contracts. 70.11 Section 70.11 Energy NUCLEAR... using special nuclear material under certain Department of Energy and Nuclear Regulatory Commission...

  15. Active and Passive Diagnostic Signatures of Special Nuclear Materials

    Energy Technology Data Exchange (ETDEWEB)

    Myers, William L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Karpius, Peter Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Myers, Steven Charles [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-05-26

    An overview will be given discussing signatures associated with special nuclear materials acquired using both active and passive diagnostic techniques. Examples of how technology advancements have helped improve diagnostic capabilities to meet the challenges of today’s applications will be discussed.

  16. Active neutron technique for detecting attempted special nuclear material diversion

    International Nuclear Information System (INIS)

    Smith, G.W.; Rice, L.G. III.

    1979-01-01

    The identification of special nuclear material (SNM) diversion is necessary if SNM inventory control is to be maintained at nuclear facilities. (Special nuclear materials are defined for this purpose as either 235 U of 239 Pu.) Direct SNM identification by the detection of natural decay or fission radiation is inadequate if the SNM is concealed by appropriate shielding. The active neutron interrogation technique described combines direct SNM identification by delayed fission neutron (DFN) detection with implied SNM detection by the identification of materials capable of shielding SNM from direct detection. This technique is being developed for application in an unattended material/equipment portal through which items such as electronic instruments, packages, tool boxes, etc., will pass. The volume of this portal will be 41-cm wide, 53-cm high and 76-cm deep. The objective of this technique is to identify an attempted diversion of at least 20 grams of SNM with a measurement time of 30 seconds

  17. Designing stability tests of nuclear instrumentation

    International Nuclear Information System (INIS)

    Viererbl, L.; Novakova, O.

    1981-01-01

    The stability tests used are described including the test of the peak maximum position differential measurement, the test of the pulse rate measurement using integral evaluation, the quality test, the chi 2 test, the 3σ test. The test of measuring pulse rate by integral evaluation was found to be the most accurate. Its modifications and generalization gave the proposed stability tests, viz., the A test and the B test. Examples are described of stability tests for a spectrometric system, the NRG 302 dose rate converter, a proportional counter. (H.S.)

  18. Assessment of specialized educational programs for licensed nuclear reactor operators

    International Nuclear Information System (INIS)

    Melber, B.D.; Saari, L.M.; White, A.S.; Geisendorfer, C.L.; Huenefeld, J.C.

    1986-02-01

    This report assesses the job-relatedness of specialized educational programs for licensed nuclear reactor operators. The approach used involved systematically comparing the curriculum of specialized educational programs for college credit, to academic knowledge identified as necessary for carrying out the jobs of licenses reactor operators. A sample of eight programs, including A.S. degree, B.S. degree, and coursework programs were studied. Subject matter experts in the field of nuclear operations curriculum and training determined the extent to which individual program curricula covered the identified job-related academic knowledge. The major conclusions of the report are: There is a great deal of variation among individual programs, ranging from coverage of 15% to 65% of the job-related academic knowledge. Four schools cover at least half, and four schools cover less than one-third of this knowledge content; There is no systematic difference in the job-relatedness of the different types of specialized educational programs, A.S. degree, B.S. degree, and coursework; and Traditional B.S. degree programs in nuclear engineering cover as much job-related knowledge (about one-half of this knowledge content) as most of the specialized educational programs

  19. Considerations for sampling nuclear materials for SNM accounting measurements. Special nuclear material accountability report

    International Nuclear Information System (INIS)

    Brouns, R.J.; Roberts, F.P.; Upson, U.L.

    1978-05-01

    This report presents principles and guidelines for sampling nuclear materials to measure chemical and isotopic content of the material. Development of sampling plans and procedures that maintain the random and systematic errors of sampling within acceptable limits for SNM(Special Nuclear Materials) accounting purposes are emphasized

  20. A valuation study of fuel supply stability of nuclear energy

    International Nuclear Information System (INIS)

    Nagano, Koji; Nagata, Yutaka; Hitomi, Kazumi; Hamagata, Sumio; Asaoka, Yoshiyuki

    2008-01-01

    In order to assess potential benefits of nuclear power with regard to its characteristics of fuel supply stability, the following three aspects are valuated under the Japanese energy and electricity mix: a) economic stability; i.e. nuclear power's contribution to the whole energy and electricity mix in terms of resistance to fluctuation and/or fuel price hikes, b) procurement stability; i.e. natural uranium, the raw fuel material for nuclear power generation, is being imported from more reliable sources through adequately diverse markets than in the cases of oil and natural gas, and, c) passive reserve effect; i.e. fuel materials as running stocks at power stations and fuel service facilities could maintain nuclear power generation running for a certain duration under unexpected disruption of fuel supply. (author)

  1. Development of the production of special steels for nuclear industries

    International Nuclear Information System (INIS)

    Vieillard-Baron, B.

    1977-01-01

    The development of electro-nuclear industries has a powerful impact on the production of special steels, although the quantity of material applied to the non-conventional parts of nuclear power plants is quite small as compared to the total production requirements in this industrial field. Evolution bears on the product research, development and testing methods, on the technical and marketing services - in particular the establishment of quality control teams and assurance manuals - and the implementation of high performance production equipments. Manufacturing must however take place under normal work load and productivity conditions of production tools, and thus ensure a satisfactory profitability on investments entailed [fr

  2. Stability of flow from a nuclear cavity. Final report

    International Nuclear Information System (INIS)

    Morrison, F.A. Jr.

    1977-07-01

    The stability of flow from a nuclear cavity was examined. The flow of interest consists of air and steam at high pressure and temperature moving through a porous medium. The steam condenses at a moving front. The stability of the flow was analyzed using the normal mode method and a program was written to perform the necessary calculations. Results of the computer calculations show that the flow of interest is stable and any instabilities that occur will decay slowly. Stability was influenced by gravity, fluid mobilities, and condensation. It was found that the stabilizing effect of conductivity is only important at negligibly small wavelengths

  3. Methods of Verification, Accountability and Control of Special Nuclear Material

    International Nuclear Information System (INIS)

    Stewart, J.E.

    1999-01-01

    This session demonstrates nondestructive assay (NDA) measurement, surveillance and analysis technology required to protect, control and account (MPC and A) for special nuclear materials (SNM) in sealed containers. These measurements, observations and analyses comprise state-of-the art, strengthened, SNM safeguards systems. Staff member specialists, actively involved in research, development, training and implementation worldwide, will present six NDA verification systems and two software tools for integration and analysis of facility MPC and A data

  4. Report from the Special Committee on Fukushima Nuclear Accident

    International Nuclear Information System (INIS)

    Ozawa, Mamoru

    2012-01-01

    The Special Committee on Fukushima Nuclear Accident was established in April 2011 under the Heat Transfer Society of Japan (HTSJ) and discussed (1) how had evolved heat transfer research in progress of nuclear technology, (2) role of expert group in the area of heat transfer academy and technology and (3) energy prospect in Japan after the Fukushima nuclear accident. This report was described by the chairman of the special committee summarizing one year discussions as (1) background of heat transfer research progress, (2) progression of Fukushima Daiichi Nuclear Power Plant accident, (3) energy problem in Japan after the Fukushima accident and (4) social role of the HTSJ. This HTSJ was a unique, nonprofit association in Japan of the people engaged in heat transfers research or in various engineering aspects related to heat transfer, which meant interdisciplinary or common platform of heat transfer as elementary technologies. Such actual complex problems could be discussed in the HTSJ from an overlooking viewpoint in order for the HTSJ to play a social role. (T. Tanaka)

  5. Neutron interrogation system using high gamma ray signature to detect contraband special nuclear materials in cargo

    Science.gov (United States)

    Slaughter, Dennis R [Oakland, CA; Pohl, Bertram A [Berkeley, CA; Dougan, Arden D [San Ramon, CA; Bernstein, Adam [Palo Alto, CA; Prussin, Stanley G [Kensington, CA; Norman, Eric B [Oakland, CA

    2008-04-15

    A system for inspecting cargo for the presence of special nuclear material. The cargo is irradiated with neutrons. The neutrons produce fission products in the special nuclear material which generate gamma rays. The gamma rays are detecting indicating the presence of the special nuclear material.

  6. Nuclear Hybrid Energy System Model Stability Testing

    Energy Technology Data Exchange (ETDEWEB)

    Greenwood, Michael Scott [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Cetiner, Sacit M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Fugate, David W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-04-01

    A Nuclear Hybrid Energy System (NHES) uses a nuclear reactor as the basic power generation unit, and the power generated is used by multiple customers as combinations of thermal power or electrical power. The definition and architecture of a particular NHES can be adapted based on the needs and opportunities of different localities and markets. For example, locations in need of potable water may be best served by coupling a desalination plant to the NHES. Similarly, a location near oil refineries may have a need for emission-free hydrogen production. Using the flexible, multi-domain capabilities of Modelica, Argonne National Laboratory, Idaho National Laboratory, and Oak Ridge National Laboratory are investigating the dynamics (e.g., thermal hydraulics and electrical generation/consumption) and cost of a hybrid system. This paper examines the NHES work underway, emphasizing the control system developed for individual subsystems and the overall supervisory control system.

  7. Nuclear astrophysics and nuclei far from stability

    International Nuclear Information System (INIS)

    Schatz, H.

    2003-01-01

    Unstable nuclei play a critical role in a number of astrophysical scenarios and are important for our understanding of the origin of the elements. Among the most important scenarios are the r-process (Supernovae), Novae, X-ray bursters, and Superbursters. For these astrophysical events I review the open questions, recent developments in astronomy, and how nuclear physics, in particular experiments with radioactive beams, needs to contribute to find the answers. (orig.)

  8. Nuclear structure/nuclei far from stability

    International Nuclear Information System (INIS)

    Casten, R.F.; Garrett, J.D.; Moller, P.; Bauer, W.W.; Brenner, D.S.; Butler, G.W.; Crawford, J.E.; Davids, C.N.; Dyer, P.L.; Gregorich, K.; Hagbert, E.G.; Hamilton, W.D.; Harar, S.; Haustein, P.E.; Hayes, A.C.; Hoffman, D.C.; Hsu, H.H.; Madland, D.G.; Myers, W.D.; Penttila, H.T.; Ragnarsson, I.; Reeder, P.L.; Robertson, G.H.; Rowley, N.; Schreiber, F.; Seifert, H.L.; Sherrill, B.M.; Siciliano, E.R.; Sprouse, G.D.; Stephens, F.S.; Subotic, K.; Talbert, W.; Toth, K.S.; Tu, X.L.; Vieira, D.J.; Villari, A.C.C.; Walters, W.B.; Wildenthal, B.H.; Wilhelmy, J.B.; Winger, J.A.; Wohn, F.K.; Wouters, J.M.; Zhou, X.G.; Zhou, Z.Y.

    1990-01-01

    This report outlines some of the nuclear structure topics discussed at the Los Alamos Workshop on the Science of Intense Radioactive Ion Beams (RIB). In it we also tried to convey some of the excitement of the participants for utilizing RIBs in their future research. The introduction of radioactive beams promises to be a major milestone for nuclear structure perhaps even more important than the last such advance in beams based on the advent of heavy-ion accelerators in the 1960's. RIBs not only will allow a vast number of new nuclei to be studies at the extremes of isospin, but the variety of combinations of exotic proton and neutron configurations should lead to entirely new phenomena. A number of these intriguing new studies and the profound consequences that they promise for understanding the structure of the atomic nucleus, nature's only many-body, strongly-inteacting quantum system, are discussed in the preceeding sections. However, as with any scientific frontier, the most interesting phenomena probably will be those that are not anticipated--they will be truly new

  9. A special purpose simulation language for nuclear power plants

    International Nuclear Information System (INIS)

    Saphier, D.

    1980-01-01

    A special purpose block-oriented simulation language, 'The Dynamic Simulator for Nuclear Power Plants' (DSNP), was developed at Argonne National Laboratory. The dominant feature of DSNP is the ability to transform a power plant flowchart or block diagram directly into a simulation program. The user is required to recognize the symbolic DSNP statements for the appropriate physical component, and list these statements in a logical sequence according to the flow of physical properties in the simulated power plant. At present most of the component models in DSNP are of the lumped parameter type. Although DSNP is a special purpose simulation language, it also has all the features of a general purpose simulation language, and in particular a powerful macro processor. The use of DSNP is demonstrated by a sample problem simulating a reactor startup accident. (Auth.)

  10. On possibility of vibrational stabilization in nuclear instable stationary regimes in nuclear reactors

    International Nuclear Information System (INIS)

    Trakhtenberg, A.M.

    1987-01-01

    A principle possibility of applying the vibrational stabilization method to nuclear reactors is studied. The problem of securing the stability of nuclear reactor operation steady-state regimes is one of the central ones in dynamics theory and nuclear reaction operation experience. In particular, the problem of xenon oscillation suppressing in a reactor, occuring as a result of steady-state regime instability is urgent. Investigation is conducted using the simpliest reactor model, repesenting it as a non-linear object with concentrated parameters. It is proved that vibrational stabilization is achieved by periodic fluctuations of the control rod positions in the reactor core and boric acid concentration in the coolant with period 1s 4 s. In practice stabilization is effective, when the steady-state regime is located near the stability boundary, which appears to be dangerous, i.e. self-oscillations with inadmissibly high amplitude occure in the reactor

  11. Stability and special solutions to the conducting dusty gas model

    International Nuclear Information System (INIS)

    Calmelet, C.J.

    1987-01-01

    Models of the flow of a dusty, conducting and non-conducting gas are examined. Exact solutions for a conducting dusty gas model in the presence of a magnetic field are developed for two different flow domains. The exact solutions are calculated in the cases of negligible and non-negligible induced magnetic field. Stability theorems are developed which depend on the flow parameters of the dusty gas and the magnetic field. In particular, a universal stability theorem is obtained when the dusty gas flow is electrically conducting in the presence of an applied magnetic field, and the dust particles are non-uniformly distributed

  12. Westinghouse Hanford Company special nuclear material vault storage study

    International Nuclear Information System (INIS)

    Borisch, R.R.

    1996-01-01

    Category 1 and 2 Special Nuclear Materials (SNM) require storage in vault or vault type rooms as specified in DOE orders 5633.3A and 6430.1A. All category 1 and 2 SNM in dry storage on the Hanford site that is managed by Westinghouse Hanford Co (WHC) is located in the 200 West Area at Plutonium Finishing Plant (PFP) facilities. This document provides current and projected SNM vault inventories in terms of storage space filled and forecasts available space for possible future storage needs

  13. Effect of special features of nuclear power plants

    International Nuclear Information System (INIS)

    Scharf, H.

    1986-01-01

    Special features of nuclear power plants are reported with the Muelheim-Kaerlich pressurized water reactor as the reference plant. This nuclear reactor uses 'Once Through Steam Generators (OTSG)' with 'Integrated Economizer' to provide the turbine with superheated steam. The implementation of OTSG allows to operate the plant with constant steam pressure over the entire power range, and with constant main coolant temperature over a power range from 15% power to 100% power. Control of the plant during power operation is provided by the 'Integrated Control System', which simultaneously sends signals to the plant's subsystems reactor, OTSG, and turbine to get optimum response of the plant during power transients. The characteristics of this 'Integrated Control System' and its different modes of operation are presented. (orig./GL)

  14. JENDL special purpose data files and related nuclear data

    International Nuclear Information System (INIS)

    Iijima, Shungo

    1989-01-01

    The objectives of JENDL Special Purpose Data Files under development are the applications of nuclear data to the evaluation of the fuel cycle, nuclear activation, and radiation damage. The files in plan consist of 9 types of data, viz., the actinide cross sections, the decay data, the activation cross sections, the (α,n) cross sections, the photo-reaction cross sections, the dosimetry cross sections, the gas production cross sections, the primary knock-on atom spectra and KERMA factors, and the data for standard. The status of the compilation and the evaluation of these data are briefly reviewed. In particular, the features of the data required for the evaluation of the activation cross sections, (α,n) cross sections, photo-reaction cross sections, and PKA data are discussed in some detail. The need for the realistic definition of the scope of the work is emphasized. (author)

  15. Nuclear symmetry energy and stability of matter in neutron stars

    International Nuclear Information System (INIS)

    Kubis, Sebastian

    2007-01-01

    It is shown that the nuclear symmetry energy is the key quantity in the stability consideration in neutron star matter. The symmetry energy controls the position of crust-core transition and also may lead to new effects in the inner core of neutron star

  16. Stability of Reshaping Breakwaters with Special Reference to Stone Durability

    DEFF Research Database (Denmark)

    Frigaard, Peter; Hald, Tue; Burcharth, H. F.

    1996-01-01

    inherently cause some breakage and abrasion of the individual stones and thereby also reduced stability. In order to avoid excessive abrasion a high stone quality is demanded or larger stones must be applied when constructed. To allow the designer to account for abrasion and armour stone breakage due...

  17. On evaluated nuclear data for beta-delayed gamma rays following of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Mencarini, Leonardo de H.; Caldeira, Alexandre D., E-mail: mencarini@ieav.cta.b, E-mail: alexdc@ieav.cta.b [Instituto de Estudos Avancados (IEAv/CTA), Sao Jose dos Campos, SP (Brazil)

    2011-07-01

    In this paper, a new type of information available in ENDF is discussed. During a consistency check of the evaluated nuclear data library ENDF/B-VII.0 performed at the Nuclear Data Subdivision of the Institute for Advanced Studies, the size of the files for some materials drew the attention of one of the authors. Almost 94 % of all available information for these special nuclear materials is used to represent the beta-delayed gamma rays following fission. This is the first time this information is included in an ENDF version. (author)

  18. On evaluated nuclear data for beta-delayed gamma rays following of special nuclear materials

    International Nuclear Information System (INIS)

    Mencarini, Leonardo de H.; Caldeira, Alexandre D.

    2011-01-01

    In this paper, a new type of information available in ENDF is discussed. During a consistency check of the evaluated nuclear data library ENDF/B-VII.0 performed at the Nuclear Data Subdivision of the Institute for Advanced Studies, the size of the files for some materials drew the attention of one of the authors. Almost 94 % of all available information for these special nuclear materials is used to represent the beta-delayed gamma rays following fission. This is the first time this information is included in an ENDF version. (author)

  19. 2 SDI, alliance coherence, and East-West nuclear stability

    International Nuclear Information System (INIS)

    Kolodzie, E.A.

    1988-01-01

    The nuclear modernization programme, offensive and defensive, now being implemented or seriously proposed by the Western nuclear states and the Soviet Union pose critical problems for the stability of the European and global nuclear balance. The Reagan administration's Strategic Defence Initiative (SDI) and the dramatic growth of British and French nuclear capabilities add new strains on the arms race now underway between the superpowers. Current and emerging instabilities must be addressed promptly along a broad political front, within and outside the framework of the Atlantic Alliance, before they further split the alliance and damage efforts---principally those being pursued at Geneva in the superpower arms control talks---to manage the nuclear balance and the conflicts that divide the two blocs in Europe and elsewhere. The first part of this paper diagnoses the disturbing elements of the evolving nuclear environment which promotes instability. The second suggests an approach -- complex bilateralism -- that might be employed to bring these destabilizing trends under control to promote the development of more coherent, cohesive, and mutually confident alliance strategic policies than exist today and to enhance East-West stability

  20. Stability of the slopes around nuclear power plants in earthquake

    International Nuclear Information System (INIS)

    Ito, Hiroshi

    1983-01-01

    The evaluation of the stability of the slopes around the buildings of nuclear power plants is important especially with respect to earthquakes. In this connection, the behavior of a slope up to its destruction and the phenomena of the destruction have been examined in the case of an earthquake by both experiment and numerical analysis. The purpose is to obtain the data for the establishment of a method for evaluating the seismic stability of a slope and of the slope design standards. The following results are described: the behavior of a slope and its destruction characteristics in the slope destruction experiment simulating the seismic coefficient method; the vibration of a slope and its destruction characteristics in vibration destruction experiment; the validity of the method of numerical simulation analysis and of stability evaluation for the slope destruction and the vibration destruction experiments, and quantitative destruction mechanism; the comparison of the various stability evaluation methods and the evaluation of seismic forces. (Mori, K.)

  1. Clinical Training of Medical Physicists Specializing in Nuclear Medicine

    International Nuclear Information System (INIS)

    2011-01-01

    The application of radiation in human health, for both diagnosis and treatment of disease, is an important component of the work of the IAEA. The responsibility for the increasingly technical aspects of this work is undertaken by the medical physicist. To ensure good practice in this vital area, structured clinical training programmes are required to complement academic learning. This publication is intended to be a guide to the practical implementation of such a programme for nuclear medicine. There is a general and growing awareness that radiation medicine is increasingly dependent on well trained medical physicists who are based in a clinical setting. However an analysis of the availability of medical physicists indicates a large shortfall of qualified and capable professionals. This is particularly evident in developing countries. While strategies to increase educational opportunities are critical to such countries, the need for guidance on structured clinical training was recognized by the members of the Regional Cooperative Agreement for Research, Development and Training related to Nuclear Science and Technology (RCA) for the Asia-Pacific region. Consequently, a technical cooperation regional project (RAS6038) under the RCA programme was formulated to address this need in this region by developing suitable material and establishing its viability. Development of a clinical training guide for medical physicists specialising in nuclear medicine was started in 2009 with the appointment of a core drafting committee of regional and international experts. The publication drew on the experience of clinical training in Australia, Croatia and Sweden and was moderated by physicists working in the Asian region. The present publication follows the approach of earlier IAEA publications in the Training Course Series, specifically Nos 37 and 47, Clinical Training of Medical Physicists Specializing in Radiation Oncology and Clinical Training of Medical Physicists

  2. Plans of reorganization of USA nuclear military complex and provision of military program by special nuclear materials

    International Nuclear Information System (INIS)

    Semenovskaya, I.V.

    1996-01-01

    Consideration is given to plans and implementation of the program of reorganization of USA nuclear military complex, related with conducted reduction of nuclear arsenal after concluding the Strategic Nuclear Armament Reduction Treaty. Particular attention is paid to problems of satisfying short-term and long-term requirements in special nuclear materials and in tritium in particular

  3. Detection of special nuclear materials with the associate particle technique

    International Nuclear Information System (INIS)

    Carasco, Cédric; Deyglun, Clément; Pérot, Bertrand; Eléon, Cyrille; Normand, Stéphane; Sannié, Guillaume; Boudergui, Karim; Corre, Gwenolé; Konzdrasovs, Vladimir; Pras, Philippe

    2013-01-01

    In the frame of the French trans-governmental R and D program against chemical, biological, radiological, nuclear and explosives (CBRN-E) threats, CEA is studying the detection of Special Nuclear Materials (SNM) by neutron interrogation with fast neutrons produced by an associated particle sealed tube neutron generator. The deuterium-tritium fusion reaction produces an alpha particle and a 14 MeV neutron almost back to back, allowing tagging neutron emission both in time and direction with an alpha particle position-sensitive sensor embedded in the generator. Fission prompt neutrons and gamma rays induced by tagged neutrons which are tagged by an alpha particle are detected in coincidence with plastic scintillators. This paper presents numerical simulations performed with the MCNP-PoliMi Monte Carlo computer code and with post processing software developed with the ROOT data analysis package. False coincidences due to neutron and photon scattering between adjacent detectors (cross talk) are filtered out to increase the selectivity between nuclear and benign materials. Accidental coincidences, which are not correlated to an alpha particle, are also taken into account in the numerical model, as well as counting statistics, and the time-energy resolution of the data acquisition system. Such realistic calculations show that relevant quantities of SNM (few kg) can be distinguished from cargo and shielding materials in 10 min acquisitions. First laboratory tests of the system under development in CEA laboratories are also presented.

  4. 75 FR 2163 - Constellation Energy; Notice of Docketing of Special Nuclear Material License SNM-2505 Amendment...

    Science.gov (United States)

    2010-01-14

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 72-8; NRC-2010-0011] Constellation Energy; Notice of Docketing of Special Nuclear Material License SNM-2505 Amendment Application for the Calvert Cliffs... Constellation Energy (Constellation) to amend its Special Nuclear Material License No. SNM-2505, under the...

  5. Nuclear beta decay far from stability and astrophysics

    International Nuclear Information System (INIS)

    Klapdor, H.V.

    1988-01-01

    Beta decay data of nuclei far from stability are one of the most important nuclear physics input for the understanding of the element systhesis in the universe and determination of the age of the universe from cosmochronometers and by the latter have implications also for cosmology. The present status of theoretical predictions of beta decay far from stability will be reviewed and the impact on the above astrophysical questions will be outlined. First results of second generation microscopic calculations of β F half lives, which are at present in progress, will be presented. (orig.)

  6. Real stabilization method for nuclear single-particle resonances

    International Nuclear Information System (INIS)

    Zhang Li; Zhou Shangui; Meng Jie; Zhao Enguang

    2008-01-01

    We develop the real stabilization method within the framework of the relativistic mean-field (RMF) model. With the self-consistent nuclear potentials from the RMF model, the real stabilization method is used to study single-particle resonant states in spherical nuclei. As examples, the energies, widths, and wave functions of low-lying neutron resonant states in 120 Sn are obtained. These results are compared with those from the scattering phase-shift method and the analytic continuation in the coupling constant approach and satisfactory agreements are found

  7. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    International Nuclear Information System (INIS)

    DeAnn Long; Michael Murphy

    2008-01-01

    Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program

  8. Special Nuclear Material Gamma-Ray Signatures for Reachback Analysts

    Energy Technology Data Exchange (ETDEWEB)

    Karpius, Peter Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Myers, Steven Charles [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-08-29

    These are slides on special nuclear material gamma-ray signatures for reachback analysts for an LSS Spectroscopy course. The closing thoughts for this presentation are the following: SNM materials have definite spectral signatures that should be readily recognizable to analysts in both bare and shielded configurations. One can estimate burnup of plutonium using certain pairs of peaks that are a few keV apart. In most cases, one cannot reliably estimate uranium enrichment in an analogous way to the estimation of plutonium burnup. The origin of the most intense peaks from some SNM items may be indirect and from ‘associated nuclides.' Indirect SNM signatures sometimes have commonalities with the natural gamma-ray background.

  9. Special nuclear material radiation monitors for the 1980's

    International Nuclear Information System (INIS)

    Fehlau, P.E.

    1985-01-01

    During the two decades that automatic gamma-radiation monitors have been applied to detecting special nuclear material (SNM), little attention has been devoted to how well the monitors perform in plant environments. Visits to 11 DOE facilities revealed poor information flow between developers, manufacturers, and maintainers of SNM radiation monitors. To help users achieve best performance from their monitors or select new ones, Los Alamos National Laboratory developed a hand-held monitor user's guide, calibration manuals for some commercial SNM pedestrian monitors, and an application guide for SNM pedestrian monitors. In addition, Los Alamos evaluated new commercial SNM monitors, considered whether to apply neutron detection to SNM monitoring, and investigated the problem of operating gamma-ray SNM monitors in variable plutonium gamma-radiation fields. As a result, the performance of existing SNM monitors will improve and alternative monitoring methods will become commerciallly available during the 1980s. 9 refs., 6 figs., 1 tab

  10. Detecting special nuclear material using muon-induced neutron emission

    Energy Technology Data Exchange (ETDEWEB)

    Guardincerri, Elena; Bacon, Jeffrey; Borozdin, Konstantin; Matthew Durham, J.; Fabritius II, Joseph [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Hecht, Adam [University of New Mexico, Albuquerque, NM 87131 (United States); Milner, Edward C. [Southern Methodist University, Dallas, TX 75205 (United States); Miyadera, Haruo; Morris, Christopher L. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Perry, John [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); University of New Mexico, Albuquerque, NM 87131 (United States); Poulson, Daniel [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)

    2015-07-21

    The penetrating ability of cosmic ray muons makes them an attractive probe for imaging dense materials. Here, we describe experimental results from a new technique that uses neutrons generated by cosmic-ray muons to identify the presence of special nuclear material (SNM). Neutrons emitted from SNM are used to tag muon-induced fission events in actinides and laminography is used to form images of the stopping material. This technique allows the imaging of SNM-bearing objects tagged using muon tracking detectors located above or to the side of the objects, and may have potential applications in warhead verification scenarios. During the experiment described here we did not attempt to distinguish the type or grade of the SNM.

  11. The Use of Nuclear Generation to Provide Power System Stability

    OpenAIRE

    Heather Wyman-Pain; Yuankai Bian; Furong Li

    2016-01-01

    The decreasing use of fossil fuel power stations has a negative effect on the stability of the electricity systems in many countries. Nuclear power stations have traditionally provided minimal ancillary services to support the system but this must change in the future as they replace fossil fuel generators. This paper explains the development of the four most popular reactor types still in regular operation across the world which have formed the basis for most reactor dev...

  12. LAPUR5 BWR stability analysis in Kuosheng nuclear power plant

    International Nuclear Information System (INIS)

    Kunlung Wu; Chunkuan Shih; Wang, J.R.; Kao, L.S.

    2005-01-01

    Full text of publication follows: Unstable oscillation of a nuclear power reactor core is one of the main reasons that causes minor core damage. Stability analysis needs to be performed to predict the potential problem as early as possible and to prevent core instability events from happening. Nuclear Regulatory Commission (NRC) requests all BWR licensees to examine each core reload and to impose operating limitations, as appropriate, to ensure compliance with GDC 10 and 12. GDC 10 requires that the reactor core be designed with appropriate margin to assure that specified acceptable fuel design limits will not be exceeded during any condition of normal operation, including anticipated operational occurrences. GDC 12 requires assurance that power oscillations which can result in conditions exceeding specified acceptable fuel design limits are either not possible or can be reliably and readily detected and suppressed. Therefore, the core instability is directly related to the fuel design limits. The core and channel DR (decay ratio) calculation are commonly performed to determine system's stability when new fuel designs are introduced in the core. In order to establish the independent analysis technology for BWR licensees and verifications, the Institute of Nuclear Energy Research (INER) has obtained agreement from NRC and implemented the 'Methodology and Procedure for Calculation of Core and Channel Decay Ratios with LAPUR', which was developed by the IBERINCO in 2001. LAPUR5 uses a multi-nodal description of the neutron dynamics, together with a distributed parameter model of the core thermal hydrodynamics to produce a space-dependent representation of the dynamics of a BWR in the frequency domain for small perturbations around a steady state condition. From the output of LAPUR5, the following results are obtained: global core decay ratio, out-of phase core decay ratio, and channel decay ratio. They are key parameters in the determination of BWR core stability

  13. Radiation stability of fluorite-type nuclear oxides

    Energy Technology Data Exchange (ETDEWEB)

    Garrido, Frederico [Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, CNRS-IN2P3-Universite Paris-Sud, Batiments 104-108, 91405 Orsay Campus (France)], E-mail: Frederico.Garrido@csnsm.in2p3.fr; Vincent, Laetitia [Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, CNRS-IN2P3-Universite Paris-Sud, Batiments 104-108, 91405 Orsay Campus (France); Nowicki, Lech [Andrzej Soltan Institute for Nuclear Studies, Hoza 69, 00-681 Warsaw (Poland); Sattonnay, Gael [Laboratoire d' Etudes des Materiaux Hors-Equilibre, Institut de Chimie Moleculaire et des Materiaux d' Orsay, UMR 8182, Universite Paris-Sud, Batiment 410, 91405 Orsay Cedex (France); Thome, Lionel [Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, CNRS-IN2P3-Universite Paris-Sud, Batiments 104-108, 91405 Orsay Campus (France)

    2008-06-15

    Oxides with the fluorite-type structure are radiation tolerant materials. They are widely used or envisaged in hostile nuclear environments, such as nuclear fuels or inert transmutation matrices for actinide burning. Study of the radiation stability of this class of solids in various radiative fields is of major importance. Two issues which may affect the stability of materials are considered in this work: the production of radiation damage (ballistic contribution); the modification of the matrix composition by doping (chemical contribution). Both contributions may drastically affect the solid stability. Urania and zirconia single crystals were chosen as fluorite-type canonical systems. They were implanted with low-energy inert gases (He or Xe). The damage in-growth, due to both ballistic and chemical contributions, was investigated by in situ RBS/C experiments in the channelling mode and TEM. Two main steps in the disordering kinetics were observed for both inert gases. Relevant key parameters were found to be: the number of displaced lattice atoms created by the slowing-down of energetic ions during the implantation process; the concentration of noble gas atoms in the solid which cause the formation of large stress fields surrounding gas aggregates.

  14. Special Radiation Protection Precautions in Therapeutic Nuclear Medicine

    Science.gov (United States)

    Stefanoyiannis, A. P.; Gerogiannis, J.

    2010-01-01

    Therapeutic Nuclear Medicine concerns the administration of appropriate amounts of radioactivity of certain isotopes, in order to achieve internal localized irradiation of neoplasmatic cells. Due to the increased level and the specific isotope characteristics of administered radioactivity, special Radiation Protection precautions must be taken. This study addresses such issues, based on national as well as international legislation and guidelines. Application of the principle of optimization is of outmost importance and is based on individual dose planning. The decision about the release of Nuclear Medicine patients after therapy is determined on an individual basis, taking into account patients' pattern of contact with other people, their age and that of persons in the home environment, in addition to other factors. Estimation of the absorbed dose given to the treated organ is based on uptake measurements and other biokinetic data, as well as on the mass of the treated tissue or organ. Concerning pregnant women, the rule of thumb is that they should not be treated, unless the radionuclide therapy is required to save their lives. In that case, the potential absorbed dose and risk to the foetus should be estimated and conveyed to the patient. After radionuclide therapy, a female should be advised to avoid pregnancy for the period of time depending on the specific radionuclide. This is to ensure that the dose to a conceptus/foetus would probably not exceed 1 mGy (the member of the public dose limit). The radiation risk for relatives and caregivers is small and unlikely to exceed the legal dose constraints during the period of the patient's treatment. Solid waste from the patient's stay in hospital is a different matter, and is normally incinerated or held for a period until radioactive decay brings the activity to an acceptable level.

  15. Estimation methods for process holdup of special nuclear materials

    International Nuclear Information System (INIS)

    Pillay, K.K.S.; Picard, R.R.; Marshall, R.S.

    1984-06-01

    The US Nuclear Regulatory Commission sponsored a research study at the Los Alamos National Laboratory to explore the possibilities of developing statistical estimation methods for materials holdup at highly enriched uranium (HEU)-processing facilities. Attempts at using historical holdup data from processing facilities and selected holdup measurements at two operating facilities confirmed the need for high-quality data and reasonable control over process parameters in developing statistical models for holdup estimations. A major effort was therefore directed at conducting large-scale experiments to demonstrate the value of statistical estimation models from experimentally measured data of good quality. Using data from these experiments, we developed statistical models to estimate residual inventories of uranium in large process equipment and facilities. Some of the important findings of this investigation are the following: prediction models for the residual holdup of special nuclear material (SNM) can be developed from good-quality historical data on holdup; holdup data from several of the equipment used at HEU-processing facilities, such as air filters, ductwork, calciners, dissolvers, pumps, pipes, and pipe fittings, readily lend themselves to statistical modeling of holdup; holdup profiles of process equipment such as glove boxes, precipitators, and rotary drum filters can change with time; therefore, good estimation of residual inventories in these types of equipment requires several measurements at the time of inventory; although measurement of residual holdup of SNM in large facilities is a challenging task, reasonable estimates of the hidden inventories of holdup to meet the regulatory requirements can be accomplished through a combination of good measurements and the use of statistical models. 44 references, 62 figures, 43 tables

  16. 10 CFR 70.20a - General license to possess special nuclear material for transport.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false General license to possess special nuclear material for transport. 70.20a Section 70.20a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) DOMESTIC LICENSING OF... transport. (a) A general license is issued to any person to possess formula quantities of strategic special...

  17. Project plan remove special nuclear material from PFP project plutonium finishing plant; TOPICAL

    International Nuclear Information System (INIS)

    BARTLETT, W.D.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove Special Nuclear Material (SNM) Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617,Rev. 0. This project plan is the top-level definitive project management document for PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Remove SNM Materials project. Any deviations to the document must be authorized through the appropriate change control process

  18. Project plan remove special nuclear material from PFP project plutonium finishing plant

    International Nuclear Information System (INIS)

    BARTLETT, W.D.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove Special Nuclear Material (SNM) Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617, Rev. 0. This project plan is the top-level definitive project management document for PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Remove SNM Materials project. Any deviations to the document must be authorized through the appropriate change control process

  19. Going Tactical: Pakistan's Nuclear Posture and Implications for Stability

    International Nuclear Information System (INIS)

    Khan, Feroz Hassan

    2015-09-01

    For decades, the Asian security environment has been characterized by multiple strategic rivalries with cascading effects. Due to its competition with China, India modernizes its armed forces, thus reinforcing its conventional advantage over Pakistan. In the subcontinent, geography, military imbalance, the legacy of past conflicts and infiltration of extremist groups considerably weaken strategic stability. To strengthen its deterrent capability against its stronger neighbour, Pakistan faces significant challenges in developing a conventional response to perceived threats from India. Islamabad thus committed to a 'full spectrum' build-up of its nuclear forces, which includes the development of tactical nuclear weapons. As Cold War experience informs, far from simply strengthening its deterrent vis-a-vis India, this move poses numerous operational dilemmas for Pakistan. The ongoing regional quantitative and qualitative arms race combines with continued political tensions between India and Pakistan to create a worrying strategic dynamic in South Asia. (author)

  20. Superheated emulsions for the detection of special nuclear material

    International Nuclear Information System (INIS)

    D’Errico, Francesco; Di Fulvio, Angela

    2011-01-01

    A novel solution for the detection and smuggling interdiction of special nuclear materials is presented here consisting of large detector modules which contain superheated emulsions and which are readout with an optical approach. The detectors can be produced to be fully sensitive to prompt fission neutrons and totally insensitive to the interrogation beam, whether X-rays or neutrons below a chosen energy threshold. Therefore, the detectors are able to operate while the selected interrogation beam is on and they will only pick up the signal from fission neutrons. A position-sensitive readout mechanism is used in our design, relying on the scattering of light by neutron-induced bubbles. A beam of coherent light crosses the active area of the detector, and local variations in scattered light due to the presence of bubbles are detected in real time by arrays of silicon planar photodiodes affixed along the whole length of the detector. The system may offer a variety of advantages compared to current approaches, such as the possibility of simultaneous irradiation and detection, i.e. a 100% duty cycle, without requiring complex signal analysis, and high signal-to-noise ratio, minimizing costly nuisance alarms, thanks to its inherent insensitivity to photons.

  1. Internal transfers of special nuclear material - March 1975

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    Paragraph 70.51(e) of 10 CFR Part 70 requires, with certain exceptions stated in the rule, that each licensee authorized to possess more than one effective kilogram of special nuclear material (SNM) maintain certain procedures. These procedures are to include: (1) records of the quantities of SNM added to or removed from the process; (2) documentation of all transfers of SNM between material-balance areas to show the identity and quantity of SNM transferred; (3) requirements for authorized signatures on each document used to record the transfer of SNM between material-balance areas; and (4) means for control of and accounting for internal transfer documents. Paragraph 70.58(e) requires licensees to establish, maintain, and follow a system for measuring the SNM transferred between material-balance areas and item-control areas. Paragraph 70.58(f) requires that licensees have a program that evaluates and controls the quality of their measurement system. Additionally, all licensees authorized to possess SNM must comply with paragraph 70.51(b) of 10 CFR Part 70. That rule requires licensees to keep records showing, among other things, the inventory of all SNM in their possession and its location. This guide sets forth acceptable methods for controlling and documenting transfers of SNM within a plant site in order to meet the requirements listed above

  2. Tamper and radiation resistant instrumentation for safeguarding special nuclear materials

    International Nuclear Information System (INIS)

    Parsons, B.B.; Wells, J.L.

    1977-01-01

    A tamper-resistant liquid level/accountability instrumentation system for safeguards use has been developed and tested. The tests demonstrate the accuracy of liquid level measurement using TDR (Time Domain Reflectometry) techniques and the accuracy of differential pressure and temperature measurements utilizing a custom designed liquid level sensor probe. The calibrated liquid level, differential pressure, and temperature data provide sufficient information to accurately determine volume, density, and specific gravity. Test solutions used include ordinary tap water, diluted nitric acid in varying concentrations, and diluted uranium trioxide also in varying concentrations. System operations and preliminary test results conducted at the General Electric Midwest Fuel Recovery Plant and the National Bureau of Standards, respectively, suggest that the system will provide the safeguards inspector with an additional tool for real-time independent verification of normal operations and special nuclear materials accountancy data for chemical reprocessing plants. This paper discusses the system design concepts, including a brief description of the tamper and radiation resistant features, the preliminary test results, and the significance of the work

  3. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    International Nuclear Information System (INIS)

    Mike Murphy

    2008-01-01

    In the past, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site has been performed by the Radiological Health Instrumentation Department. Calibration and performance tests on the PM-700 personnel portal monitor were performed but there was no test program for the VM-250 vehicle portal monitor because it had never been put into service. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no program in place to test them quarterly. In April of 2007, the Material Control and Accountability (MC and A) Manager at the time decided that the program needed to be strengthened and MC and A took over performance testing of all SNM portal monitoring equipment. This paper will discuss the following activities associated with creating a performance testing program: changing the culture, learning the systems, writing procedures, troubleshooting/repairing, validating the process, control of equipment, acquisition of new systems, and running the program

  4. Selected topics in special nuclear materials safeguard system design

    International Nuclear Information System (INIS)

    King, L.L.; Thatcher, C.D.; Clarke, J.D.; Rodriguez, M.P.

    1991-01-01

    During the past two decades the improvements in circuit integration have given rise to many new applications in digital processing technology by continuously reducing the unit cost of processing power. Along with this increase in processing power a corresponding decrease in circuit volume has been achieved. Progress has been so swift that new classes of applications become feasible every 2 or 3 years. This is especially true in the application of proven new technology to special nuclear materials (SNM) safeguard systems. Several areas of application were investigated in establishing the performance requirements for the SNM safeguard system. These included the improvements in material control and accountability and surveillance by using multiple sensors to continuously monitor SNM inventory within the selected value(s); establishing a system architecture to provide capabilities needed for present and future performance requirements; and limiting operating manpower exposure to radiation. This paper describes two selected topics in the application of state-of-the-art, well-proven technology to SNM safeguard system design

  5. Special Nuclear Material Detection with a Water Cherenkov based Detector

    International Nuclear Information System (INIS)

    Sweany, M.; Bernstein, A.; Bowden, N.; Dazeley, S.; Svoboda, R.

    2008-01-01

    Fission events from Special Nuclear Material (SNM), such as highly enriched uranium or plutonium, produce a number of neutrons and high energy gamma-rays. Assuming the neutron multiplicity is approximately Poissonian with an average of 2 to 3, the observation of time correlations between these particles from a cargo container would constitute a robust signature of the presence of SNM inside. However, in order to be sensitive to the multiplicity, one would require a high total efficiency. There are two approaches to maximize the total efficiency; maximizing the detector efficiency or maximizing the detector solid angle coverage. The advanced detector group at LLNL is investigating one way to maximize the detector size. We are designing and building a water Cerenkov based gamma and neutron detector for the purpose of developing an efficient and cost effective way to deploy a large solid angle car wash style detector. We report on our progress in constructing a larger detector and also present preliminary results from our prototype detector that indicates detection of neutrons

  6. Special nuclear materials cutoff exercise: Issues and lessons learned. Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    Libby, R.A.; Segal, J.E.; Stanbro, W.D.; Davis, C.

    1995-08-01

    This document is appendices D-J for the Special Nuclear Materials Cutoff Exercise: Issues and Lessons Learned. Included are discussions of the US IAEA Treaty, safeguard regulations for nuclear materials, issue sheets for the PUREX process, and the LANL follow up activity for reprocessing nuclear materials.

  7. Special nuclear materials cutoff exercise: Issues and lessons learned. Volume 3

    International Nuclear Information System (INIS)

    Libby, R.A.; Segal, J.E.; Stanbro, W.D.; Davis, C.

    1995-08-01

    This document is appendices D-J for the Special Nuclear Materials Cutoff Exercise: Issues and Lessons Learned. Included are discussions of the US IAEA Treaty, safeguard regulations for nuclear materials, issue sheets for the PUREX process, and the LANL follow up activity for reprocessing nuclear materials

  8. Special safety requirements applied to Brazilian nuclear power plant

    International Nuclear Information System (INIS)

    Lepecki, W.P.S.; Hamel, H.J.E.; Koenig, N.; Vieira, P.C.R.; Fritzsche, J.C.

    1981-01-01

    Some safety aspects of the Angra 2 and 3 nuclear power plants are presented. An analysis of the civil and mechanical project of these nuclear power plant having in view a safety analysis is done. (E.G.) [pt

  9. Nolinear stability analysis of nuclear reactors : expansion methods for stability domains

    International Nuclear Information System (INIS)

    Yang, Chae Yong

    1992-02-01

    coefficient is positive, it is not necessarily true that an (linearly stable) operating power level is absolutely stable (unconditionally stable or stable in the large). In this situation, the stability region of the operating power level of the reactor is bounded and hence the reactor may experience sudden changes in power level for large perturbations. Furthermore, when mass flow rate decreases, the size of the stability region gradually decreases. The extent of stability (the stability region) of an operating state is dependent on the values of the reactor parameters. In the parameter space of the reactivity feedback coefficients, the reactor feedback system has three partitions: unconditionally stable (stable in the large), conditionally stable, and unstable regions. These partitions of course change as the state of the reactor, e.g., design and operating conditions, changes. It is desired that the reactor always operate in the unconditionally stable region; the reactor should be stable for any perturbation, by taking suitable values of the reactivity feedback coefficients. As a result of nonlinear stability analysis using the methods in this thesis, a desirable range of the reactivity feedback coefficients can be obtained for stable operation of a nuclear reactor

  10. Nuclear energy: the real cost. A special report

    Energy Technology Data Exchange (ETDEWEB)

    Spencer, K.; Marshall, R.; Sweet, C.; Prior, M.; Welsh, I.; Bunyard, P.; Goldsmith, E.; Hildyard, N.; Jeffery, J.W. (Committee for the Study of the Economics of Nuclear Electricity, Camelford (UK))

    1981-12-01

    This report on the discussions within a small group of academics falls under the headings: chairman's foreword; summary and recommendations; the government's nuclear power programme and its implications; the CEGB's planning record; the past performance of Britain's nuclear power stations - a guide for the future (query); nuclear power -early uncertainties; historic costs - 'the fraud inherent in all inflationary finance'; current cost accounting; fuel costs - coal stays steady, nuclear rises; net effective cost and the rationale for nuclear power; reinterpreting net effective costs; other considerations; conclusions and recommendations; references.

  11. Uncovering Special Nuclear Materials by Low-energy Nuclear Reaction Imaging.

    Science.gov (United States)

    Rose, P B; Erickson, A S; Mayer, M; Nattress, J; Jovanovic, I

    2016-04-18

    Weapons-grade uranium and plutonium could be used as nuclear explosives with extreme destructive potential. The problem of their detection, especially in standard cargo containers during transit, has been described as "searching for a needle in a haystack" because of the inherently low rate of spontaneous emission of characteristic penetrating radiation and the ease of its shielding. Currently, the only practical approach for uncovering well-shielded special nuclear materials is by use of active interrogation using an external radiation source. However, the similarity of these materials to shielding and the required radiation doses that may exceed regulatory limits prevent this method from being widely used in practice. We introduce a low-dose active detection technique, referred to as low-energy nuclear reaction imaging, which exploits the physics of interactions of multi-MeV monoenergetic photons and neutrons to simultaneously measure the material's areal density and effective atomic number, while confirming the presence of fissionable materials by observing the beta-delayed neutron emission. For the first time, we demonstrate identification and imaging of uranium with this novel technique using a simple yet robust source, setting the stage for its wide adoption in security applications.

  12. Future global manpower shortages in nuclear industries with special reference to india including remedial measures

    International Nuclear Information System (INIS)

    Ghosh Hazra, G.S.

    2008-01-01

    Full text: The Radiation Protection Program of the Environmental Protection Agencies of countries employ scientists, engineers, statisticians, economists, lawyers, policy analysts, and public affairs professionals amongst others. These professionals aim to protect workers, the general public, and the environment from harmful radiation exposures and to provide the technical basis for radiation protection policies and regulations. Professionals include Health physicists, Bio statistician, Radio chemist, Radio ecologist, Radio biologist etc. With a large proportion of the population of the nuclear workforce of many countries now approaching retirement age, existing power plants of these countries will be hard pressed to find enough qualified professionals to support their operations. The potential shortage of skilled manpower not only affects utilities, but also impacts the entire nuclear infrastructure, including national laboratories, federal and state agencies, nuclear technology vendors and manufacturing companies, nuclear construction companies, and university nuclear engineering departments. Manpower requirements exist in the nuclear power industry, universities and research establishments, hospitals, government departments, general industry e.g. radiography, transport, instrumentation etc., specialist contractors, agencies and consultancies serving radiation protection. India is no exception. India has the world's 12 th largest economy. Assuming India's average growth rate p.a. of more than 5%, total GDP by 2050 will increase substantially which will require proportionate increase of manpower for all industries. Also chance of brain drain is very high from developing countries e.g. from India to developed countries because of much higher pay and better lifestyle as there will be shortage of manpower in developed countries as explained above. With population growth to be stabilized in future in India, the working age population may not increase in the year 2030

  13. Safety, Security, and Stability: The Role of Nuclear Control Regimes in a Proliferated World

    National Research Council Canada - National Science Library

    Collins, James

    1995-01-01

    ... with developing and deploying nuclear weapons. The US, in the past, has refused to provide technical assistance to enhance the safety, security, and stability of proliferating countries' nuclear arsenals-we believe this policy...

  14. Technical criteria for terminating or reducing domestic safeguards on low-grade special nuclear material

    International Nuclear Information System (INIS)

    Crawford, D.W.

    1996-01-01

    A graded table for terminating or reducing domestic safeguards has been developed for use by programs and facilities within the Department of Energy in decisions regarding the need for or levels of protection of low-grade nuclear materials. Contained in this table are technical criteria which can allow for complete removal of safeguards over many special nuclear material forms and concentrations of typical low-grade materials either currently located at generating or processing sites and materials which may arise from processing operations related to stabilization and disposition activities. In addition, these criteria include higher concentration levels which may warrant maintaining some level of (albeit reduced) security on low-grade materials while allowing reductions in materials control and accountability requirements. These reductions can range from complete removal of these materials from materials control and accountability requirements such as measurements, physical inventories and recordkeeping, to deferring these measurements and physical inventories until a time that either the material is removed from the site or resubmitted for processing. It is important to note that other conditions contained in current Departmental safeguards and security policy be met prior to safeguards termination or reduction

  15. Defense Special Weapons Agency Advisory Panel on the Nuclear Weapon Effects Program

    National Research Council Canada - National Science Library

    1998-01-01

    We performed the audit in response to allegations made to the Defense Hotline concerning conflicts of interest among members of the Defense Special Weapons Agency Advisory Panel on the Nuclear Weapon Effects Program...

  16. Improved design for vibration-proof platinum RTD in special position of nuclear power plant

    International Nuclear Information System (INIS)

    Liu Zhuo; Ma Jinna; Wu Bin

    2014-01-01

    In accordance with the actual situation for the vibration of violence in a special position of nuclear power plant, an improved design for platinum RTD was proposed. The structure design is verified to meet the measure requirement in the special position. (authors)

  17. Design of stability-guaranteed fuzzy logic controller for nuclear steam generators

    International Nuclear Information System (INIS)

    Cho, B.H.; No, H.C.

    1996-01-01

    A fuzzy logic controller (FLC) and a fuzzy logic filter (FLF), which have a special type of fuzzifier, inference engine, and defuzzifier, are applied to the water level control of a nuclear steam generator (S/G). It is shown that arbitrary two-input, single-output linear controllers can be adequately expressed by this FLC. A procedure to construct stability-guaranteed FLC rules is proposed. It contains the following steps: (1) the stable sector of linear feedback gains is obtained from the suboptimal concept based on LQR theory and the Lyapunov's stability criteria; (2) the stable sector of linear gains is mapped into two linear rule tables that are used as limits for the FLC rules; and (3) the construction of an FLC rule table is done by choosing certain rules that lie between these limits. This type of FLC guarantees asymptotic stability of the control system. The FLF generates a feedforward signal of S/G feedwater from the steam flow measurement using a fuzzy concept. Through computer simulation, it is found that the FLC with the FLF works better than a well-tuned PID controller with variable gains to reduce swell/shrink phenomena, especially for the water level deviation and abrupt steam flow disturbances that are typical in the existing power plants

  18. Postural Stability of Special Warfare Combatant-Craft Crewmen With Tactical Gear.

    Science.gov (United States)

    Morgan, Paul M; Williams, Valerie J; Sell, Timothy C

    The US Naval Special Warfare's Special Warfare Combatant-Craft Crewmen (SWCC) operate on small, high-speed boats while wearing tactical gear (TG). The TG increases mission safety and success but may affect postural stability, potentially increasing risk for musculoskeletal injury. Therefore, the purpose of this study was to examine the effects of TG on postural stability during the Sensory Organization Test (SOT). Eight SWCC performed the SOT on NeuroCom's Balance Manager with TG and with no tactical gear (NTG). The status of gear was performed in randomized order. The SOT consisted of six different conditions that challenge sensory systems responsible for postural stability. Each condition was performed for three trials, resulting in a total of 18 trials. Overall performance, each individual condition, and sensory system analysis (somatosensory, visual, vestibular, preference) were scored. Data were not normally distributed therefore Wilcoxon signed-rank tests were used to compare each variable (ρ = .05). No significant differences were found between NTG and TG tests. No statistically significant differences were detected under the two TG conditions. This may be due to low statistical power, or potentially insensitivity of the assessment. Also, the amount and distribution of weight worn during the TG conditions, and the SWCC's unstable occupational platform, may have contributed to the findings. The data from this sample will be used in future research to better understand how TG affects SWCC. The data show that the addition of TG used in our study did not affect postural stability of SWCC during the SOT. Although no statistically significant differences were observed, there are clinical reasons for continued study of the effect of increased load on postural stability, using more challenging conditions, greater surface perturbations, dynamic tasks, and heavier loads. 2016.

  19. Accounting systems for special nuclear material control. Technical report

    International Nuclear Information System (INIS)

    Korstad, P.A.

    1980-05-01

    Nuclear material accounting systems were examined and compared to financial double-entry accounting systems. Effective nuclear material accounting systems have been designed using the principles of double-entry financial accounting. The modified double-entry systems presently employed are acceptable if they provide adequate control over the recording and summarizing of transactions. Strong internal controls, based on principles of financial accounting, can help protect nuclear materials and produce accurate, reliable accounting data. An electronic data processing system can more accurately maintain large volumes of data and provide management with more current, reliable information

  20. Pyrochlore as nuclear waste form. Actinide uptake and chemical stability

    Energy Technology Data Exchange (ETDEWEB)

    Finkeldei, Sarah Charlotte

    2015-07-01

    Radioactive waste is generated by many different technical and scientific applications. For the past decades, different waste disposal strategies have been considered. Several questions on the waste disposal strategy remain unanswered, particularly regarding the long-term radiotoxicity of minor actinides (Am, Cm, Np), plutonium and uranium. These radionuclides mainly arise from high level nuclear waste (HLW), specific waste streams or dismantled nuclear weapons. Although many countries have opted for the direct disposal of spent fuel, from a scientific and technical point of view it is imperative to pursue alternative waste management strategies. Apart from the vitrification, especially for trivalent actinides and Pu, crystalline ceramic waste forms are considered. In contrast to glasses, crystalline waste forms, which are chemically and physically highly stable, allow the retention of radionuclides on well-defined lattice positions within the crystal structure. Besides polyphase ceramics such as SYNROC, single phase ceramics are considered as tailor made host phases to embed a specific radionuclide or a specific group. Among oxidic single phase ceramics pyrochlores are known to have a high potential for this application. This work examines ZrO{sub 2} based pyrochlores as potential nuclear waste forms, which are known to show a high aqueous stability and a high tolerance towards radiation damage. This work contributes to (1) understand the phase stability field of pyrochlore and consequences of non-stoichiometry which leads to pyrochlores with mixed cationic sites. Mixed cationic occupancies are likely to occur in actinide-bearing pyrochlores. (2) The structural uptake of radionuclides themselves was studied. (3) The chemical stability and the effect of phase transition from pyrochlore to defect fluorite were probed. This phase transition is important, as it is the result of radiation damage in ZrO{sub 2} based pyrochlores. ZrO{sub 2} - Nd{sub 2}O{sub 3} pellets

  1. Pyrochlore as nuclear waste form. Actinide uptake and chemical stability

    International Nuclear Information System (INIS)

    Finkeldei, Sarah Charlotte

    2015-01-01

    Radioactive waste is generated by many different technical and scientific applications. For the past decades, different waste disposal strategies have been considered. Several questions on the waste disposal strategy remain unanswered, particularly regarding the long-term radiotoxicity of minor actinides (Am, Cm, Np), plutonium and uranium. These radionuclides mainly arise from high level nuclear waste (HLW), specific waste streams or dismantled nuclear weapons. Although many countries have opted for the direct disposal of spent fuel, from a scientific and technical point of view it is imperative to pursue alternative waste management strategies. Apart from the vitrification, especially for trivalent actinides and Pu, crystalline ceramic waste forms are considered. In contrast to glasses, crystalline waste forms, which are chemically and physically highly stable, allow the retention of radionuclides on well-defined lattice positions within the crystal structure. Besides polyphase ceramics such as SYNROC, single phase ceramics are considered as tailor made host phases to embed a specific radionuclide or a specific group. Among oxidic single phase ceramics pyrochlores are known to have a high potential for this application. This work examines ZrO 2 based pyrochlores as potential nuclear waste forms, which are known to show a high aqueous stability and a high tolerance towards radiation damage. This work contributes to (1) understand the phase stability field of pyrochlore and consequences of non-stoichiometry which leads to pyrochlores with mixed cationic sites. Mixed cationic occupancies are likely to occur in actinide-bearing pyrochlores. (2) The structural uptake of radionuclides themselves was studied. (3) The chemical stability and the effect of phase transition from pyrochlore to defect fluorite were probed. This phase transition is important, as it is the result of radiation damage in ZrO 2 based pyrochlores. ZrO 2 - Nd 2 O 3 pellets with pyrochlore and defect

  2. Real-Time Characterization of Special Nuclear Materials

    Energy Technology Data Exchange (ETDEWEB)

    Walston, Sean [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Candy, Jim [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chambers, Dave [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chandrasekaran, Hema [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Snyderman, Neal [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-09-04

    When confronting an item that may contain nuclear material, it is urgently necessary to determine its characteristics. Our goal is to provide accurate information with high-con dence as rapidly as possible.

  3. Nuclear Coexistence: Rethinking U.S. Policy to Promote Stability in an Era of Proliferation

    Science.gov (United States)

    1994-04-01

    into the effects of Israel’s nuclear weapons on regional stability. 25. See David Albright and Mark Hibbs, "Iraq’s Bomb: Blueprints and Artifacts...Foreign Minister Andrei V. Kozyrev warned Ukraine that the possession of deteriorating nuclear warheads could lead to an accident.32 Sovereign Control and...longstanding political disputes. By the standard of nuclear bipolarity, the nuclear politics on the subcontinent are largely a mirror of the U.S.-Soviet nuclear

  4. Legislation for the countermeasures on special issues of nuclear safety regulations

    International Nuclear Information System (INIS)

    Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Heon Jin; Oh, Ho Chul

    2004-02-01

    Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation

  5. Legislation for the countermeasures on special issues of nuclear safety regulations

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Heon Jin; Oh, Ho Chul [Chongju Univ., Cheongju (Korea, Republic of)

    2004-02-15

    Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation.

  6. A method for assay of special nuclear material in high level liquid waste streams

    International Nuclear Information System (INIS)

    Venkata Subramani, C.R.; Swaminathan, K.; Asuvathraman, R.; Kutty, K.V.G.

    2003-01-01

    The assay of special nuclear material in the high level liquid waste streams assumes importance as this is the first stage in the extraction cycle and considerable losses of plutonium could occur here. This stream contains all the fission products as also the minor actinides and hence normal nuclear techniques cannot be used without prior separation of the special nuclear material. This paper presents the preliminary results carried out using wavelength dispersive x-ray fluorescence as part of the developmental efforts to assay SNM in these streams by instrumental techniques. (author)

  7. Special role of scientists as citizens in a nuclear age

    International Nuclear Information System (INIS)

    Masperi, L.

    1999-01-01

    We are living in an age dominated by science and technology. There are probably at present more scientists alive than all those that passed away through the history of humankind. It is certain that science and technology have the possibility of solving the problems of society. However, these problems have not so far been satisfactorily treated and some scientifically ordered society which might be envisaged should hurt the common humanitarian feeling. These are probably the reasons for which a part of the public opinion has lost its trust in science and many people try to find a relief for their anguish in esoteric religions. It seems therefore necessary for a change of attitude on the part of scientists to restore the positive consideration from the society and to be able to contribute to the future evolution of humankind according to a peaceful and harmonious pattern. This short essay will start describing the historical search for solutions through science, will continue by attempting to define the values which should he added to science in the present time, and will end with possible recommendations for scientists in their connection with society, with particular emphasis on the nuclear issue. All that will be considered here refers mainly to natural sciences. Trying to find which are the attitudes of scientists that could contribute to the benefit of society, one may start with the need of feeling love for the scientific achievements they are able to make. Concerning the specific nuclear issue, both civilian and military applications must be considered. The military applications of nuclear energy should be completely prohibited. Scientists may play a relevant role in the elimination of the nuclear weapon possibility in regions of threshold states or with undeclared arsenals. On the way to nuclear-weapon-free world, it will be crucial to convince all or some of the nuclear powers to dismantle their nuclear arsenals. Scientists may make contribution to the

  8. Nuclear materials stabilization and packaging end-of-year status report, April 1--September 30, 1996

    International Nuclear Information System (INIS)

    Rink, N.A.; Aguino, V.T.

    1997-02-01

    This report documents progress on the Los Alamos Nuclear Materials Stabilization and Packaging projects for the third and fourth quarters of fiscal year 1996. It covers development and production activities for the Plutonium Packaging project, the Plutonium Recovery and Stabilization project, and the Uranium Recovery and Stabilization project. In addition, it reports on quality assurance activities for the Plutonium Packaging project

  9. Stability of special ionizing chambers for using in programs of quality control in radiotherapy and radiodiagnostic

    International Nuclear Information System (INIS)

    Afonso, Luciana C.; Caldas, Linda V.E.; Costa, Alessandro M. da

    2004-01-01

    In this work the response stability of two special parallel-plate ionization chambers, developed at the Calibration Laboratory of IPEN, were tested. The chambers are face doubled, with internal collecting electrodes of different materials (graphite and aluminium), in tandem system, and with air volumes of 0.6 cm 3 and 2.5 cm 3 , for radiotherapy and diagnostic radiology levels, respectively. The results showed that the chambers kept constant their metrological characteristics presenting their usefulness for quality control programs in radiotherapy and diagnostic radiology. (author)

  10. Global physical and numerical stability of a nuclear reactor core

    International Nuclear Information System (INIS)

    Morales-Sandoval, Jaime; Hernandez-Solis, Augusto

    2005-01-01

    Low order models are used to investigate the influence of integration methods on observed power oscillations of some nuclear reactor simulators. The zero-power point reactor kinetics with six-delayed neutron precursor groups are time discretized using explicit, implicit and Crank-Nicholson methods, and the stability limit of the time mesh spacing is exactly obtained by locating their characteristic poles in the z-transform plane. These poles are the s to z mappings of the inhour equation roots and, except for one of them, they show little or no dependence on the integration method. Conditions for stable power oscillations can be also obtained by tracking when steady state output signals resulting from reactivity oscillations in the s-Laplace plane cross the imaginary axis. The dynamics of a BWR core operating at power conditions is represented by a reduced order model obtained by adding three ordinary differential equations, which can model void and Doppler reactivity feedback effects on power, and collapsing all delayed neutron precursors in one group. Void dynamics are modeled as a second order system and fuel heat transfer as a first order system. This model shows rich characteristics in terms of indicating the relative importance of different core parameters and conditions on both numerical and physical oscillations observed by large computer code simulations. A brief discussion of the influence of actual core and coolant conditions on the reduced order model is presented

  11. The Thermos program for nuclear reactors specialized in district heating

    International Nuclear Information System (INIS)

    Lerouge, B.

    1976-01-01

    Many studies have been made in France on the use of nuclear heat for district heating. After a brief account of the problems raised by the use of thermal waste from big nuclear power stations, the quantitative and qualitative needs of heating networks are analyzed and the Thermos project described. This is a very robust reactor of the pool type, with an output of 100MW, supplying low-pressure water at 100 deg C. The advantages from the aspects of safety and economy are described, and the present state of the project and its possible developments summarized [fr

  12. Introduction to Special Edition (of the Journal of Nuclear Materials Management) on Reducing the Threat from Radioactive Materials

    International Nuclear Information System (INIS)

    Mladineo, Stephen V.

    2007-01-01

    Introductory article for special edition of the JOURNAL OF NUCLEAR MATERIALS MANAGEMENT outlining the Institute of Nuclear Materials Management Nonproliferation and Arms Control Technical Division. In particular the International Nuclear and Radiological Security Standing Committee and its initial focus covering four topical areas--Radiological Threat Reduction, Nuclear Smuggling and Illicit Trafficking, Countering Nuclear Terrorism, and Radiological Terrorism Consequence Management

  13. 10 CFR 73.25 - Performance capabilities for physical protection of strategic special nuclear material in transit.

    Science.gov (United States)

    2010-01-01

    ... strategic special nuclear material in transit. 73.25 Section 73.25 Energy NUCLEAR REGULATORY COMMISSION... Transit § 73.25 Performance capabilities for physical protection of strategic special nuclear material in transit. (a) To meet the general performance objective and requirements of § 73.20 an in-transit physical...

  14. Nuclear waste disposal: achieving adequate financing - special study

    International Nuclear Information System (INIS)

    Quasebarth, M.V.

    1984-01-01

    An analysis by the Congressional Budget Office (CBO) evaluates whether the current one mill fee now charged to nuclear-electricity consumers will adequately finance the waste disposal program. The CBO found that, if the fee is adjusted annually for inflation, it should provide enough revenues to cover all program costs under all nuclear growth forecasts. If the fee is unchanged, however, the fees will be inadequate if inflation exceeds 3% annually. The report suggests two alternatives for fee revision, but makes no recommendations. The alternatives are to increase the fee only at specific intervals or to automatically adjust the fee through indexation. The report examines the effect of delaying the program, cost overruns, and alternative inflation rate and interest rate assumptions. 3 figures, 12 tables

  15. Seismic stability of unanchored spent nuclear fuel storage casks

    International Nuclear Information System (INIS)

    Ofoegbu, G. I.; Gute, G. D.; Chowdhury, A. H.

    2003-01-01

    Dynamic soil-structure interaction analyses were performed to examine the effects of a potential earthquake on the stability of unanchored cylindrical spent nuclear fuel casks for an above-ground storage installation. The casks would be placed on a cluster of reinforced concrete pads founded on a deep sequence of clays and silts underlain by sandstones. The analyses focused on evaluating the geometric stability of the casks during an earthquake with respect to a design concept that a cask should not tip over, slide off the storage pad, or collide with another cask. The analyses were performed using LS-DYNA with a three-dimensional explicit finite element model representing the site soil and a fully loaded storage pad. Three statistically independent acceleration time histories were applied simultaneously at the base of the model to generate a free-field ground motion time history representing the design-basis earthquake. Sensitivity studies were performed to examine the effects of the interface conditions between the storage pad and the surrounding soil, and between the base of the storage casks and the top surface of the pad. The results indicate that ground motion from the design-basis earthquake would not cause any cask to tip over, slide off the pad, or collide with another cask. The contact conditions at the cask-to-pad and pad-to-soil interfaces have a strong effect on potential cask motions during an earthquake. If the cask-base friction coefficient is small, the casks may slide, but would not experience any significant rocking. If the cask-base friction is large enough to permit a significant transfer of earthquake lateral motions across the cask-to-pad interface, a design with bonded pad-to-soil interfaces would produce larger cask motions than a design with frictional pad-to-soil interfaces. Furthermore, a cask strage design in which the cask motions are essentially isolated from the motions of the pad-soil system, which can be accomplished if the cask

  16. EEC energy policy guidelines with special reference to nuclear energy

    International Nuclear Information System (INIS)

    Brunner, G.

    1978-01-01

    The possibility of a new oil boycott is continuing threat to the European countries: a new oil crisis would put to a severe test not only the economic but also the social system within the community. In the major part of the community power stations cannot be supplied by solar energy and coal fired power stations present a significant environmental burden so that Europe cannot forgo, under any circumstances, the further development of nuclear energy. (orig.) [de

  17. Nuclear and energy. Special issue on the Fukushima power plant

    International Nuclear Information System (INIS)

    2011-01-01

    This issue analyses the first consequences of the Fukushima accident at the world level, i.e. impacts which are either already noticeable or predictable. A first article proposes a portrait of Japan (its historical relationship with nature, the cultural education, the role of its bureaucracy, the Japanese business and political worlds) and evokes the nuclear safety organization at the institutional level. It also evokes the different companies involved in nuclear energy production. The second article discusses and comments the environmental and radiological impact of the accident (protection of the inhabitants, environment monitoring, comparison with Chernobyl, main steps of degradation of the reactors, releases in the sea, total release assessment, soil contamination, food contamination, radiation protection). A third article discusses the international impact, notably for the existing or projected power plants in different countries, in terms of public opinion, and with respect to negotiations on climate. The fourth article discusses the reactions of different countries possessing nuclear reactors. The last article questions the replacement of the lost production (that of Fukushima and maybe another power plant) by renewable energies

  18. 10 CFR 74.31 - Nuclear material control and accounting for special nuclear material of low strategic significance.

    Science.gov (United States)

    2010-01-01

    ... and maintain a measurement system which assures that all quantities in the material accounting records...) In each inventory period, control total material control and accounting measurement uncertainty so... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special...

  19. Design of stability-guaranteed neurofuzzy logic controller for nuclear steam generators

    International Nuclear Information System (INIS)

    Cho, B.H.; No, H.C.

    1996-01-01

    A neurofuzzy logic controller (NFLC), which is implemented by using a multilayer neural network with special types of fuzzifier, inference engine and defuzzifier, is applied to the water level control of a nuclear steam generator (SG). This type of NFLC has the structural advantage that arbitrary two-input, single-output linear controllers can be adequately mapped into a set of specific control rules of the NFLC. In order to design a stability-guaranteed NFLC, the stable sector of the given linear gain is obtained from Lyapunov's stability criteria. Then this sector is mapped into two linear rule tables that are used as the limits of NFLC control rules. The automatic generation of NFLC rule tables is accomplished by using the back-error-propagation (BEP) algorithm. There are two separate paths for the error back propagation in the SG. One considers the level dynamics depending on the tank capacity and the other takes into account the reverse dynamics of the SG. The amounts of error back propagated through these paths show opposite effects in the BEP algorithm from each other for the swell-shrink phenomenon. Through computer simulation it is found that the BEP algorithm adequately generates NFLC rule tables according to given learning parameters. (orig.)

  20. Fault Frictional Stability in a Nuclear Waste Repository

    Science.gov (United States)

    Orellana, Felipe; Violay, Marie; Scuderi, Marco; Collettini, Cristiano

    2016-04-01

    Exploitation of underground resources induces hydro-mechanical and chemical perturbations in the rock mass. In response to such disturbances, seismic events might occur, affecting the safety of the whole engineering system. The Mont Terri Rock Laboratory is an underground infrastructure devoted to the study of geological disposal of nuclear waste in Switzerland. At the site, it is intersected by large fault zones of about 0.8 - 3 m in thickness and the host rock formation is a shale rock named Opalinus Clay (OPA). The mineralogy of OPA includes a high content of phyllosilicates (50%), quartz (25%), calcite (15%), and smaller proportions of siderite and pyrite. OPA is a stiff, low permeable rock (2×10-18 m2), and its mechanical behaviour is strongly affected by the anisotropy induced by bedding planes. The evaluation of fault stability and associated fault slip behaviour (i.e. seismic vs. aseismic) is a major issue in order to ensure the long-term safety and operation of the repository. Consequently, experiments devoted to understand the frictional behaviour of OPA have been performed in the biaxial apparatus "BRAVA", recently developed at INGV. Simulated fault gouge obtained from intact OPA samples, were deformed at different normal stresses (from 4 to 30 MPa), under dry and fluid-saturated conditions. To estimate the frictional stability, the velocity-dependence of friction was evaluated during velocity steps tests (1-300 μm/s). Slide-hold-slide tests were performed (1-3000 s) to measure the amount of frictional healing. The collected data were subsequently modelled with the Ruina's slip dependent formulation of the rate and state friction constitutive equations. To understand the deformation mechanism, the microstructures of the sheared gouge were analysed. At 7 MPa normal stress and under dry conditions, the friction coefficient decreased from a peak value of μpeak,dry = 0.57 to μss,dry = 0.50. Under fluid-saturated conditions and same normal stress, the

  1. Actomyosin drives cancer cell nuclear dysmorphia and threatens genome stability.

    Science.gov (United States)

    Takaki, Tohru; Montagner, Marco; Serres, Murielle P; Le Berre, Maël; Russell, Matt; Collinson, Lucy; Szuhai, Karoly; Howell, Michael; Boulton, Simon J; Sahai, Erik; Petronczki, Mark

    2017-07-24

    Altered nuclear shape is a defining feature of cancer cells. The mechanisms underlying nuclear dysmorphia in cancer remain poorly understood. Here we identify PPP1R12A and PPP1CB, two subunits of the myosin phosphatase complex that antagonizes actomyosin contractility, as proteins safeguarding nuclear integrity. Loss of PPP1R12A or PPP1CB causes nuclear fragmentation, nuclear envelope rupture, nuclear compartment breakdown and genome instability. Pharmacological or genetic inhibition of actomyosin contractility restores nuclear architecture and genome integrity in cells lacking PPP1R12A or PPP1CB. We detect actin filaments at nuclear envelope rupture sites and define the Rho-ROCK pathway as the driver of nuclear damage. Lamin A protects nuclei from the impact of actomyosin activity. Blocking contractility increases nuclear circularity in cultured cancer cells and suppresses deformations of xenograft nuclei in vivo. We conclude that actomyosin contractility is a major determinant of nuclear shape and that unrestrained contractility causes nuclear dysmorphia, nuclear envelope rupture and genome instability.

  2. Real-time inventory system for special nuclear material

    Energy Technology Data Exchange (ETDEWEB)

    Kuckertz, T.H.; Ethridge, C.D.; Nicholson, N.

    1979-01-01

    This paper describes a special purpose peripheral device for a minicomputer that can monitor SNM in vault storage in real time and give timely indication of any tampering with the material. This device, called a shelf monitor, is designed around a single-chip microcomputer, and can be manufactured in quantity for about $100. A typical system of shelf monitors controlled by a minicomputer is described. The minicomputer is used to acquire data associated with the weight and gamma activity of the sample of SNM under observation. Significant deviations in the weight and gamma activity are cause for a tampering alarm.

  3. Real-time inventory system for special nuclear material

    International Nuclear Information System (INIS)

    Kuckertz, T.H.; Ethridge, C.D.; Nicholson, N.

    1979-01-01

    This paper describes a special purpose peripheral device for a minicomputer that can monitor SNM in vault storage in real time and give timely indication of any tampering with the material. This device, called a shelf monitor, is designed around a single-chip microcomputer, and can be manufactured in quantity for about $100. A typical system of shelf monitors controlled by a minicomputer is described. The minicomputer is used to acquire data associated with the weight and gamma activity of the sample of SNM under observation. Significant deviations in the weight and gamma activity are cause for a tampering alarm

  4. Microcomputer based shelf system to monitor special nuclear materials in storage

    International Nuclear Information System (INIS)

    Nicholson, N.; Kuckertz, T.H.; Ethridge, C.D.

    1980-01-01

    Diversion of special nuclear material has become a matter of grave concern in recent years. Large quantities of this material are kept in long-term storage and must be inventoried periodically, resulting in a time-consuming activity that exposes personnel to additional radiation. A system that provides continuous surveillance of stored special nuclear materials has been developed. A shelf monitor has been designed using a single component microcomputer to collect data from a Geiger Muller tube that monitors gamma emissions and a scale that monitors the total weight of the special nuclear material and its container. A network of these shelf monitors reports their acquired data to a minicomputer for analysis and storage. Because a large number of these monitors is likely to be needed in most storage facilities, one objective of this program has been to develop a low cost but reliable monitor

  5. Semi-annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1981-08-01

    This eighth periodic semiannual report of inventory differences covers the second six months of fiscal year 1980 (April 1, 1980, through September 30, 1980), for the Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of strategic special nuclear material. Strategic special nuclear material is plutonium or uranium-233 or uranium-235 in material whose uranium-235 content is 20 percent or greater (known as highly enriched uranium). A significant quantity is either 2 kilograms of plutonium or uranium-233 or 5 kilograms of uranium-235 in highly enriched uranium or the appropriate weighted combination. All Inventory Differences reported here have been analyzed, investigated when necessary, and resolved. These data and explanations, together with the absences of physical indications of any theft attempt, support a finding that during this period no theft or diversion of strategic special nuclear material has occurred

  6. Land contamination. Technical guidance on special sites: nuclear sites

    International Nuclear Information System (INIS)

    Hill, M.; Steeds, J.; Slade, N.

    2001-01-01

    Part IIA of the Environmental Protection Act 1990 sets out a regulatory regime for the identification and remediation of land where contamination is causing unacceptable risks to defined receptors. The Environment Agency has a number of regulatory roles under this regime. Where land is designated as a Special Site, as defined in the Contaminated Land (England) Regulations 2000, the Agency will act as the enforcing authority. It is expected that a similar regime will be introduced in Wales during 2001, but the reader should check whether definitions of Special Sites in the Welsh regulations are the same as in the English ones. The Environment Agency's approach to carrying out its regulatory responsibilities is set out in its Part RA Process Documentation,, available on the Agency website (www.environment-agency. gov.uk). This documentation sets out how the Agency intends to carry out its responsibilities under Part IIA of the Environmental Protection Act 1990, which came into force in England on 1 April 2000

  7. Vulnerability Analysis Considerations for the Transportation of Special Nuclear Material

    International Nuclear Information System (INIS)

    Nicholson, Lary G.; Purvis, James W.

    1999-01-01

    The vulnerability analysis methodology developed for fixed nuclear material sites has proven to be extremely effective in assessing associated transportation issues. The basic methods and techniques used are directly applicable to conducting a transportation vulnerability analysis. The purpose of this paper is to illustrate that the same physical protection elements (detection, delay, and response) are present, although the response force plays a dominant role in preventing the theft or sabotage of material. Transportation systems are continuously exposed to the general public whereas the fixed site location by its very nature restricts general public access

  8. Cover gases in nuclear reactors with special reference to argon

    International Nuclear Information System (INIS)

    Jose, C.J.; Shah, G.C.; Prabhu, L.H.; Vartak, D.G.

    1975-01-01

    The report describes the specifications of an ideal cover gas for the smooth operation of a nuclear reactor. The advantages of using helium as cover gas, the sources of impurities in helium cover gas and the methods of purification of helium are given in detail. Various problems associated with the use of argon as cover gas and methods to purify and decontaminate argon cover gas are discussed on the basis of experimental data collected. A laboratory model of the system which can be used to evaluate the performance of the gas purification adsorbents is also described. (author)

  9. Special report: the Reagan administration, Congress, and nuclear power

    International Nuclear Information System (INIS)

    Nichols, T.A.; Bink, B.H.

    1982-01-01

    One year ago, the Reagan administration set out to invigorate the light-water-reactor industry; to reactivate the breeder-reactor program; to encourage private reprocessing; and to expedite waste management. The authors feel that, to this end, Congress and the administration are on the brink of major regulatory reforms, a sweeping nuclear-waste-disposal program, and tightening guidelines for burial of low-level waste, all of which are vital to the industry's continued health. This report covers the status of their efforts

  10. Summaries of special research project on nuclear fusion 1980

    International Nuclear Information System (INIS)

    Uchida, Taijiro

    1981-09-01

    This is a report of the research project entitled ''Nuclear fusion'', supported by the grant in aid for fusion research from the Ministry of Education in the fiscal year 1980. The research project was started in April, 1980, and comprises the following seventeen subjects of nuclear fusion research. 1) Heavy irradiation effects, 2) plasma-wall interaction, 3) neutronics, 4) welding engineering, 5) science and technology of tritium, 6) biological effects of tritium, 7) diagnostics of high temperature plasma, 8) new lasers, 9) fundamentals of plasma heating, 10) high efficiency energy conversion, 11) theory and computer simulation, 12) superconducting materials, 13) fundamental phenomena of superconductivity, 14) magnet technology, 15) heat transfer and structural engineering, 16) system design, and 17) resources and assessment of fusion energy. 43 summaries concerning reactor materials and plasma-wall interaction, 29 summaries concerning the science, technology and biological effects of tritium, 41 summaries concerning the fundamentals of reactor plasma control, 15 summaries concerning the technology of superconducting magnets, and 14 summaries concerning the design of fusion reactors and its evaluation are collected in this report, and their results and progress can be known. (Kako, I.)

  11. Improving Industry-Relevant Nuclear-Knowledge Development through Special Partnerships

    International Nuclear Information System (INIS)

    Cilliers, A.

    2016-01-01

    Full text: South African Network for Nuclear Education Science and Technology (SAN NEST) has the objective to develop the nuclear education system in South Africa to a point where suitably qualified and experienced nuclear personnel employed by nuclear science and technology programmes in South Africa are predominantly produced by the South African education system. This is done to strengthen the nuclear science and technology education programmes to better meet future demands in terms of quality, capacity and relevance. To ensure sustainable relevance, it is important to develop special partnerships with industry. This paper describes unique partnerships that were developed with nuclear industry partners. The success of these partnerships has ensured more industry partners to embrace the model which has proven to develop relevant knowledge, support research and provide innovative solutions for industry. (author

  12. The SNM Scanner: A Non-invasive Protocol for Effective Monitoring of Special Nuclear Material Inventories

    International Nuclear Information System (INIS)

    Lanier, R G; Dauffy, L S; Hodge, A M

    2004-01-01

    We suggest a system of monitoring special nuclear material inventories which uses simple mathematical techniques to compare the gross features of emitted gamma-ray spectra. In this report we develop the techniques necessary to make such spectral comparisons and describe their application. We also apply these ideas and develop inventory confirmation results using a room-temperature CdTe detector in a real nuclear-material inventory environment

  13. Intelligent data-acquisition instrumentation for special nuclear material assay data analysis

    International Nuclear Information System (INIS)

    Ethridge, C.D.

    1980-01-01

    The Detection, Surveillance, Verification, and Recovery Group of the Los Alamos Scientific Laboratory Energy Division/Nuclear Safeguards Programs is now utilizing intelligent data-acquisition instrumentation for assay data analysis of special nuclear material. The data acquisition and analysis are enabled by the incorporation of a number-crunching microprocessor sequenced by a single component microcomputer. Microcomputer firmware establishes the capability for processing the computation of several selected functions and also the ability of instrumentation self-diagnostics

  14. A stability identification system for boiling water nuclear reactors

    International Nuclear Information System (INIS)

    Belblidia, L.A.; Chevrier, A.

    1994-01-01

    Boiling water reactors are subject to instabilities under low-flow, high-power operating conditions. These instabilities are a safety concern and it is therefore important to determine stability margins. This paper describes a method to estimate a measure of stability margin, called the decay ratio, from autoregressive modelling of time series data. A phenomenological model of a boiling water reactor with known stability characteristics is used to generate time series to validate the program. The program is then applied to signals from local power range monitors from the cycle 7 stability tests at the Leibstadt plant. (author) 7 figs., 2 tabs., 12 refs

  15. Decree 2805 by means of which the National Accounting and Control of Basic Nuclear Materials and Special Fusionable Materials System, is established

    International Nuclear Information System (INIS)

    1979-01-01

    This Decree has for object to establish a National Accounting and Control of Basic Nuclear Materials and Special Fusionable Materials System, under the supervision of the National Council for the Nuclear Industry Development. Its aims are to account nuclear materials, to control nuclear activities, to preserve and control nuclear information, to keep technical relationship with specialized organizations, and to garant nuclear safeguards [es

  16. Special course for global nuclear human resource development in cooperation with Hitachi-GE nuclear energy in Tokyo institute of technology

    International Nuclear Information System (INIS)

    Ujita, H.; Futami, T.; Saito, M.; Murata, F.; Shimizu, M.

    2012-01-01

    Many Asian countries are willing to learn Japanese nuclear power plants experiences, and are interested in introducing nuclear power generation to meet their future energy demand. Special course for Global Nuclear Human Resource Development was established in April, 2011 in the Department of Nuclear Engineering at Graduate School of Tokyo Institute of Technology in cooperation with Hitachi-GE Nuclear Energy. Purpose of the special course is to develop global nuclear engineers and researchers not only in the Tokyo Institute of Technology but also in the educational institutes of Southeast Asian countries

  17. Stability versus neuronal specialization for STDP: long-tail weight distributions solve the dilemma.

    Directory of Open Access Journals (Sweden)

    Matthieu Gilson

    Full Text Available Spike-timing-dependent plasticity (STDP modifies the weight (or strength of synaptic connections between neurons and is considered to be crucial for generating network structure. It has been observed in physiology that, in addition to spike timing, the weight update also depends on the current value of the weight. The functional implications of this feature are still largely unclear. Additive STDP gives rise to strong competition among synapses, but due to the absence of weight dependence, it requires hard boundaries to secure the stability of weight dynamics. Multiplicative STDP with linear weight dependence for depression ensures stability, but it lacks sufficiently strong competition required to obtain a clear synaptic specialization. A solution to this stability-versus-function dilemma can be found with an intermediate parametrization between additive and multiplicative STDP. Here we propose a novel solution to the dilemma, named log-STDP, whose key feature is a sublinear weight dependence for depression. Due to its specific weight dependence, this new model can produce significantly broad weight distributions with no hard upper bound, similar to those recently observed in experiments. Log-STDP induces graded competition between synapses, such that synapses receiving stronger input correlations are pushed further in the tail of (very large weights. Strong weights are functionally important to enhance the neuronal response to synchronous spike volleys. Depending on the input configuration, multiple groups of correlated synaptic inputs exhibit either winner-share-all or winner-take-all behavior. When the configuration of input correlations changes, individual synapses quickly and robustly readapt to represent the new configuration. We also demonstrate the advantages of log-STDP for generating a stable structure of strong weights in a recurrently connected network. These properties of log-STDP are compared with those of previous models. Through

  18. Applying programmatic risk assessment to nuclear materials stabilization R and D planning

    International Nuclear Information System (INIS)

    Kenley, C.R.; Brown-van Hoozer, S.A.

    1997-01-01

    A systems engineering approach to programmatic risk assessment, derived from the aerospace industry, was applied to various stabilization technologies to assess their relative maturity and availability for use in stabilizing nuclear materials. The assessment provided valuable information for trading off available technologies and identified the at-risk technologies that will require close tracking by the Department of Energy (DOE) to mitigate programmatic risks

  19. Special conditions for the application of coating materials in nuclear power plants

    International Nuclear Information System (INIS)

    Boetius, I.

    1980-01-01

    Proceeding from the special conditions for the application of coating materials in nuclear power plants the following factors influencing the decontamination of surface coatings are discussed from the point of view of radiation protection: abrasion resistance, waterproofness, mechanical and adhesion strength, and permeability. For practical use it is recommended to test the surface tightness of coatings with radiation-exposed specimens

  20. Semi-annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1983-07-01

    This report covers data for the period from April 1, 1982, through September 30, 1982, and includes accounting corrections for data from earlier periods. These data and explanations, together with the absences of physical indications of any theft attempt, support a finding that during this period no theft or diversion of strategic special nuclear material has occurred

  1. Some considerations on the seismic stability of large slopes surrounding the nuclear power plant

    International Nuclear Information System (INIS)

    Ito, Hiroshi; Watanabe, Hiroyuki

    1982-01-01

    As a series of the research on the seismic stabilities of a large scale slope surrounding the Nuclear Power Plant, the numerical simulation and analytical stability calculation are conducted in order to clarify the applicability of static stability evaluation method (conventional circular arc slip method, static non-linear F.E. analysis) and dynamic one (2-dimensional dynamic F.E. analysis). The discussions on these slope stability methods are done and the followings are clarified, i) The results of numerical simulation by dynamic F.E. analysis concerning the response property and the failure mode are qualitatively corresponded with the behaviour of dynamic failure test. ii) From the results of static and dynamic stability analysis, it is concluded that the conventional circular arc slip method gives the severest evaluation for slope stability. iii) It is proposed that the seismic coefficient for static slope stability analysis should be used the value of the equivalent instant acceleration. (author)

  2. Special feature article. Nuclear new age. Towards reform of laws and regulations

    International Nuclear Information System (INIS)

    Madarame, Haruki; Morokuzu, Muneo; Shiroyama, Hideaki; Nishiwaki, Yoshihiro; Marumo, Syunji; Suzuki, Takahiro; Hariyama, Hideo

    2007-01-01

    Since about half a century passes after the peaceful use of nuclear energy began in Japan, the safety laws and regulations of the nuclear energy becomes difficult to cope enough with the current situation without regulation structure changing. In March 2007, Tokyo University set up nuclear energy legislation study meeting' consisting of members from regulatory bodies, electric utilities, nuclear industries and others. The special feature introduces five opinions obtained through the argument in the meeting. As an example, Law for the Regulations of Nuclear Sources Material, Nuclear Fuel Material and Reactors is applied to basic design about the commercial reactors, but Electric Utilities Industry Law is applied to a detailed design, and different licensing standard is applied in each. Taking the adjustment of licensing standard with unifying these is necessary for efficiency. In addition, current law for the Regulations of Nuclear Sources Material, Nuclear Fuel Material and Reactors regulates according to the businesses such as reactor facilities, fuel fabrication plants and radioactive waste disposal. As for plural businesses, a low procedure and safety measures are demanded every each business. It is also necessary to include structure of the comprehensive licensing that assumed an enterprise running plural businesses. (T. Tanaka)

  3. Equation of state and stability of hot asymmetric nuclear matter

    International Nuclear Information System (INIS)

    Samaddar, S.K.

    1989-01-01

    The nuclear incompressibility as obtained from different sources, from nuclei, high energy nuclear collisions, supernova and neutron stars are briefly reviewed. All these data in general favour a compression modulus, K α ∼ 300 Mev with a minimum uncertainty ∼ 50 MeV. Using a finite rang e density and momentum dependent two-body effective interaction, variation of nucl ear incompressibility with temperature, asymmetry and density is discussed in a non-relativistic mean field approach. The same formalism has also been used to study the limiting temperatures of infinite as well as finite nuclear systems in the astrophysical context as well as in high energy heavy ion collisions. (autho r). 16 refs., 6 figs., 1 tab

  4. Semi-annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1979-01-01

    This report provides and explains the generally small differences between the amounts of nuclear materials charged to DOE facilities and the amounts that could be physically inventoried. This report covers data for the period from October 1, 1977, through March 31, 1978, and includes accounting corrections for data from earlier periods. The data and explanations, together with the absence of physical indications of any theft attempt, support a finding that during this period no theft or diversion of a significant amount of strategic special nuclear material has occurred

  5. Report on {open_quotes}audit of internal controls over special nuclear materials{close_quotes}

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    The Department of Energy (Department) is responsible for safeguarding a significant amount of plutonium, uranium-233 and enriched uranium - collectively referred to as special nuclear materials - stored in the United States. The Department`s office of Nonproliferation and National Security has overall management cognizance for developing policies for safeguarding these materials, while other Headquarters program offices have {open_quotes}landlord{close_quotes} responsibilities for the sites where the materials are stored, and the Department`s operations and field offices provide onsite management of contractor operations. The Department`s management and operating contractors, under the direction of the Department, safeguard and account for the special nuclear material stored at Department sites.

  6. Thermal hydraulic stability in a pressure tube nuclear reactor

    International Nuclear Information System (INIS)

    Villani, A.; Ravetta, R.; Mansani, L.

    1986-01-01

    The CIRENE plant which will undergo preoperational tests in the near future is equipped with a 40 MW(e) Heavy Water moderated Boiling Light Water cooled Reactor (HWBLWR); at the start-up and up to about 30 % of nominal power, the necessary low coolant density is obtained injecting into the core a mixture of liquid and steam. To verify the thermal-hydraulic stability of the plant in this situation, tests have been carried out in a facility simulating two full scale power channels; the system stability has been confirmed in the reference conditions, and is not reduced by even a significant reduction of the liquid flowrate, where a decrease in liquid temperature has some negative effect and steam flowrate has a small influence. (author)

  7. Survey of special nuclear material vehicle monitors for domestic and international safeguards

    International Nuclear Information System (INIS)

    Fehlau, P.E.; Atwater, H.F.; Caldwell, J.T.; Shunk, E.R.

    1979-01-01

    Special nuclear materials vehicle monitors, including gateside vehicle monitors, hand-held personnel-vehicle monitors, and a new tunnel monitor concept for very large vehicles, are discussed. The results of a comparison of effectiveness of monitors for domestic application are presented. The results of calculations and small scale prototype measurements are given for a tunnel-like neutron monitor for monitoring at the perimeter of an enrichment plant subjected to International Safeguards

  8. Specialized medical sections for the treatment of radiation injuries from accidents in nuclear power plants

    International Nuclear Information System (INIS)

    Deanovic, Z.; Boranic, M.; Vitale, B.

    1980-01-01

    Presented is the organization of the final, highly specialized treatment (diagnostic and therapeutic) of persons that have been severely injured in a radiation or nuclear accident. In this organizational scheme, the leading idea was to group and establish suitable medical sections for the acceptance, diagnosic work-up, and treatment of radiation casualties, around a strong medical center in which the different specialists would be available

  9. Impact of nuclear fuel cycle centers on shipping special nuclear materials and wastes

    International Nuclear Information System (INIS)

    Blomeke, J.O.

    1975-01-01

    The impact of integrated nuclear fuel cycle facilities on the transportation sector appears from this admittedly rather narrow study to be of only marginal significance. However, there are other factors which must be taken into account such as nuclear safeguards, economics, and radiological, ecological, institutional, and sociological impacts. Unless more clear-cut advantages can be shown by on-going studies for some of these other considerations, the regimentation and control of industry that would result from the imposition of the integrated fuel cycle facility concept probably could not be justified. (auth)

  10. Low temperature nuclear orientation studies of nuclei far from stability

    International Nuclear Information System (INIS)

    Brown, D.E.

    1990-01-01

    One of the major current interests in nuclear physics is to study transitional nuclei which lie between well known regions of spherical and deformed nuclei. The neutron deficient Tellurium and Iodine isotopes are examples of such nuclei. In both cases, the influence of a πg 9/2 intruder orbital is expected to be strong at low excitation energies and at A ∼120. The 120 Te decay scheme has been investigated in detail by LTNO supported by γ-γ coincidences and conversion electron spectroscopy. An interaction of the level scheme using an IBM-2 calculation which allows for mixing between the ground state and a (4p-2h) intruder state is made. The success of this calculation provides strong evidence for the existence of the intruder configuration in 120 Te. In addition, the relative electric quadrupole moments of the ground states in 120-123 I have been measured. The light Platinum isotopes are also transitional nuclei. The ground state magnetic dipole and electric quadrupole moments have been measured for 185,187 Pt which lie inside the region in which the shape transition is known to occur. An interpretation of nuclear moments and level structures in the range 179≤A≤193 using a particle plus triaxial core shows that the shape change takes place gradually via a broad region in which the nuclear shape is triaxial. (author)

  11. 2008 Special NSREC Issue of the IEEE Transactions on Nuclear Science Comments by the Editors

    Science.gov (United States)

    Schwank, Jim; Buchner, Steve; Marshall, Paul; Duzellier, Sophie; Brown, Dennis; Poivey, Christian; Pease, Ron

    2008-12-01

    The December 2008 special issue of the IEEE Transactions on Nuclear Science contains selected papers from the 45th annual IEEE International Nuclear and Space Radiation Effects Conference (NSREC) held in Tucson, Arizona, July 14 - 18, 2008. Over 115 papers presented at the 2008 NSREC were submitted for consideration for this year's special issue. Those papers that appear in this special issue were able to successfully complete the review process before the deadline for the December issue. A few additional papers may appear in subsequent issues of the TRANSACTIONS. This publication is the premier archival journal for research on space and nuclear radiation effects in materials, devices, circuits, and systems. This distinction is the direct result of the conscientious efforts of both the authors, who present and document their work, and the reviewers, who selflessly volunteer their time and talent to help review the manuscripts. Each paper in this journal has been reviewed by experts selected by the editors for their expertise and knowledge of the particular subject areas.

  12. Stability of transition to a world without nuclear weapons: Technical problems of verification

    International Nuclear Information System (INIS)

    Zhigalov, V.

    1998-01-01

    A serious psychological barrier to acceptance of the concept for achieving the nuclear-weapon-free world is fear of facing the prospect that one or more nations or extremist political groups might develop their own nuclear weapons. Actually this is a question of stability of the nuclear-weapon-free world. From this point of view the most effective system of verification is an absolute necessity. This system must ensure detection of so called undeclared nuclear activity at early stage. Scientists of Russian nuclear centers are working today on solving this problem. This paper is considered to be a comprehensive attempt to analyze the technical and organizational aspects of the problems of transition to a nuclear-weapons-free world, setting aside the difficulties of resolving purely political problems

  13. Evaluation of seismic stability of nuclear power plants on weathered soft rocks

    International Nuclear Information System (INIS)

    Ogata, Nobuhide; Nishi, Koichi; Honsho, Shizumitsu

    1991-01-01

    Soft rocks such as weathered rocks or low cemented sedimentary rocks spread all over the country. If it is possible to construct nuclear power plants on such soft rocks, there will be more available sites for nuclear power plants. The investigation on the following research items was carried out. (1) Geological survey and the application of test methods on soft rocks. (2) Methods and application of laboratory and in-situ tests on soft rocks. (3) Response analysis of a reactor building and foundation ground during earthquake. (4) Stability analysis of soft rock ground as the foundation of a nuclear power plant regarding both earthquake and long-term settlement. From the results of the investigation, it became evident that the seismic stability of a nuclear power plant on weathered soft rocks can be assured enough. (author)

  14. Optical-coupling nuclear spin maser under highly stabilized low static field

    Energy Technology Data Exchange (ETDEWEB)

    Yoshimi, A., E-mail: yoshimi@ribf.riken.jp [RIKEN Nishina Center (Japan); Inoue, T.; Uchida, M.; Hatakeyama, N.; Asahi, K. [Tokyo Institute of Technology, Department of Physics (Japan)

    2008-01-15

    A nuclear spin maser of a new type, that employs a feedback scheme based on optical nuclear spin detection, has been fabricated. The spin maser is operated at a low static field of 30 mG by using the optical detection method. The frequency stability and precision of the spin maser have been improved by a highly stabilized current source for the static magnetic field. An experimental setup to search for an electric dipole moment (EDM) in {sup 129}Xe atom is being developed.

  15. Detecting special nuclear materials in suspect containers using high-energy gamma rays emitted by fission products

    Science.gov (United States)

    Norman, Eric B [Oakland, CA; Prussin, Stanley G [Kensington, CA

    2009-01-27

    A method and a system for detecting the presence of special nuclear materials in a suspect container. The system and its method include irradiating the suspect container with a beam of neutrons, so as to induce a thermal fission in a portion of the special nuclear materials, detecting the gamma rays that are emitted from the fission products formed by the thermal fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the special nuclear materials using the comparison.

  16. Rattling nucleons: New developments in active interrogation of special nuclear material

    International Nuclear Information System (INIS)

    Runkle, Robert C.; Chichester, David L.; Thompson, Scott J.

    2012-01-01

    Active interrogation is a vigorous area of research and development due to its promise of offering detection and characterization capabilities of special nuclear material in environments where passive detection fails. The primary value added by active methods is the capability to penetrate shielding - special nuclear material itself, incidental materials, or intentional shielding - and advocates hope that active interrogation will provide a solution to the problem of detecting shielded uranium, which is at present the greatest obstacle to interdiction efforts. The technique also provides a unique benefit for quantifying nuclear material in high background-radiation environments, an area important for nuclear material safeguards and material accountancy. Progress has been made in the field of active interrogation on several fronts, most notably in the arenas of source development, systems integration, and the integration and exploitation of multiple fission and non-fission signatures. But penetration of interrogating radiation often comes at a cost, not only in terms of finance and dose but also in terms of induced backgrounds, system complexity, and extended measurement times (including set up and acquisition). These costs make the calculus for deciding to implement active interrogation more subtle than may be apparent. The purpose of this review is thus to examine existing interrogation methods, compare and contrast their attributes and limitations, and identify missions where active interrogation may hold the most promise.

  17. Commissioning of calorimeter in radiochemical laboratory for non-destructive assay of special nuclear materials

    International Nuclear Information System (INIS)

    Patra, S.; Mhatre, A.M.; Agarwal, C.; Chaudhury, S.; Pujari, P.K.

    2017-01-01

    Accounting of special nuclear materials (SNM) in every stages of nuclear fuel cycle is a necessity where one needs the quantitative estimation of SNM in variety of samples like sealed containers or finished products without altering its physical and chemical form. Non-destructive assay (NDA) techniques are capable of assaying such samples by the way of measuring passive/active neutrons/gamma rays or by the measurement of decay heat. Radiochemistry Division has been actively involved in the development and deployment of various NDA methodologies for meeting the demand of nuclear material accounting as and when required. Recently a radiometric calorimeter, developed by Reactor Control Division, E and I Group, BARC, has been installed in Lab C-33, Radiochemistry Division

  18. Study of nuclear power plant stability. Trip criteria

    International Nuclear Information System (INIS)

    Beato Castro, D.; Iturbe Uriarte, R.; Wilhelmi Ayza, J.R.

    1993-01-01

    The influence that nuclear power plants and high voltage power systems have on each other when confronted by disturbances in the offsite network may lead, due to dynamic effects, to plant trip. It is therefore necessary to study the disturbances in the network and the effects on plant equipment by means of dynamic simulations which evaluate the unit protection system and the auxiliary services so as to obtain maximum unit availability without jeopardizing its safety. These studies can be conducted since there are models and software tools capable of simulating dynamic behaviour of the electric system, including the excitation systems and specific speed governors obtainment of valid. (author)

  19. 2012 Special NSREC Issue of the IEEE Transactions on Nuclear Science Comments by the Editors

    Science.gov (United States)

    Schwank, Jim; Brown, Dennis; Girard, Sylvain; Gouker, Pascale; Gerardin, Simone; Quinn, Heather; Barnaby, Hugh

    2012-12-01

    The December 2012 special issue of the IEEE Transactions on Nuclear Science contains selected papers from the 49th annual IEEE International Nuclear and Space Radiation Effects Conference (NSREC) held July 16-20, 2012, in Miami, Florida USA. 95 papers presented at the 2012 NSREC were submitted for consideration for this year’s special issue. Those papers that appear in this special issue were able to successfully complete the review process before the deadline for the December issue. A few additional papers may appear in subsequent issues of the TRANSACTIONS. This publication is the premier archival journal for research on space and nuclear radiation effects in materials, devices, circuits, and systems. This distinction is the direct result of the conscientious efforts of both the authors, who present and document their work, and the reviewers, who selflessly volunteer their time and talent to help review the manuscripts. Each paper in this journal has been reviewed by experts selected by the editors for their expertise and knowledge of the particular subject areas. The peer review process for a typical technical journal generally takes six months to one year to complete. To publish this special issue of the IEEE Transactions on Nuclear Science (in December), the review process, from initial submission to final form, must be completed in about 10 weeks. Because of the short schedule, both the authors and reviewers are required to respond very quickly. The reviewers listed on the following pages contributed vitally to this quick-turn review process.We would like to express our sincere appreciation to each of them for accepting this difficult, but critical role in the process. To provide consistent reviews of papers throughout the year, the IEEE Transactions on Nuclear Science relies on a year-round editorial board that manages reviews for submissions throughout the year to the TRANSACTIONS in the area of radiation effects. The review process is managed by a Senior

  20. Stabilization of the Electron-Nuclear Spin Orientation in Quantum Dots by the Nuclear Quadrupole Interaction

    Science.gov (United States)

    Dzhioev, R. I.; Korenev, V. L.

    2007-07-01

    The nuclear quadrupole interaction eliminates the restrictions imposed by hyperfine interaction on the spin coherence of an electron and nuclei in a quantum dot. The strain-induced nuclear quadrupole interaction suppresses the nuclear spin flip and makes possible the zero-field dynamic nuclear polarization in self-organized InP/InGaP quantum dots. The direction of the effective nuclear magnetic field is fixed in space, thus quenching the magnetic depolarization of the electron spin in the quantum dot. The quadrupole interaction suppresses the zero-field electron spin decoherence also for the case of nonpolarized nuclei. These results provide a new vision of the role of the nuclear quadrupole interaction in nanostructures: it elongates the spin memory of the electron-nuclear system.

  1. Special duties of paints in nuclear environment in India with examples of application

    International Nuclear Information System (INIS)

    Singha Roy, P.K.; Subbaratnam, T.

    1978-01-01

    Any process involving nuclear interactions gives rise to radioactivity and radiation in various degrees apart from conventional effects like heat, pressure, etc. Vessels and structures containing such processes are subject to various degrees of radioactivity and contamination by liquid, gaseous or particulate radioactive materials coming in contact with the substrate. Thus, in any nuclear environment surfaces require protection against both radioactive contamination and normal corrosion forces. The protective coating should be able to resist the radiation field in which it is placed and also withstand decontamination process for removal of radioactive contamination from the surface as and when required. Radioactive contamination due to any radiochemical operation is objectionable for two reasons: (i) it constitutes a potential radiation hazard to occupants of the facility, and (ii) cross contamination jeoparadizes the validity of the experimental data. The difficulty experienced in decontaminating many materials used in construction of such nuclear or radiochemical facilities has therefore given emphasis to the search for suitable coating matetials. This paper deals with the two special duties expected of paints in such environment, viz., radiation resistance and decontaminability tests in this regard in BARC and examples of actual selections and applications in an Indian nuclear power station. Some areas requiring investigations and serious attention for industrial painting in general and nuclear painting work in particular have been also identified. (author)

  2. Observation of enhanced nuclear stability near the 162 neutron shell

    Energy Technology Data Exchange (ETDEWEB)

    Lougheed, R.W.; Moody, K.J.; Wild, J.F.; Hulet, E.K.; McQuaid, J.H. [Lawrence Livermore National Lab., CA (United States); Lazarev, Yu.A.; Lobanov, Yu.V.; Oganessian, Yu.Ts.; Utyonkov, V.K.; Abdullin, F.Sh.; Buklanov, G.V.; Gikal, B.N.; Iliev, S.; Mezentsev, A.N.; Polyakov, A.N.; Sedykh, I.M.; Shirokovsky, I.V.; Subbotin, V.G.; Sukhov, A.M.; Tsyganov, Yu.S.; Zhuchko, V.E. [Joint Inst. for Nuclear Research, Dubna (Russian Federation)

    1993-09-22

    In bombardments of {sup 248}Cm with {sup 22}Ne the authors discovered two new isotopes, {sup 265}106 and {sup 266}106, by establishing genetic links between {alpha} decays of the 106 nuclides and SF or {alpha} decays of the daughter (grand-daughter) nuclides. For {sup 266}106 they measured E{sub {alpha}}=8.62{+-}0.06 MeV followed by the SF decay of {sup 262}104 for which they measured a half-life value of 1.2{sup +1.0}{sub {minus}0.5} s. For {sup 265}106 they measured E{sub {alpha}}=8.82{+-}0.06 MeV. They estimated {alpha} half-lives of 10-30 s for {sup 266}106 and 2-30 s for {sup 265}106 with SF branches of {approximately}50% or less. The decay properties of {sup 266}106 indicate a large enhancement in the SF stability of this N=160 nuclide and confirm the existence of the predicted neutron-deformed shell N=162.

  3. Clinical Training of Medical Physicists Specializing in Nuclear Medicine (Spanish Edition); Capacitacion clinica de fisicos medicos especialistas en medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-07-15

    The application of radiation in human health, for both diagnosis and treatment of disease, is an important component of the work of the IAEA. The responsibility for the increasingly technical aspects of this work is undertaken by the medical physicist. To ensure good practice in this vital area, structured clinical training programmes are required to complement academic learning. This publication is intended to be a guide to the practical implementation of such a programme for nuclear medicine. There is a general and growing awareness that radiation medicine is increasingly dependent on well trained medical physicists who are based in a clinical setting. However an analysis of the availability of medical physicists indicates a large shortfall of qualified and capable professionals. This is particularly evident in developing countries. While strategies to increase educational opportunities are critical to such countries, the need for guidance on structured clinical training was recognized by the members of the Regional Cooperative Agreement for Research, Development and Training related to Nuclear Science and Technology (RCA) for the Asia-Pacific region. Consequently, a technical cooperation regional project (RAS6038) under the RCA programme was formulated to address this need in this region by developing suitable material and establishing its viability. Development of a clinical training guide for medical physicists specialising in nuclear medicine was started in 2009 with the appointment of a core drafting committee of regional and international experts. The publication drew on the experience of clinical training in Australia, Croatia and Sweden and was moderated by physicists working in the Asian region. The present publication follows the approach of earlier IAEA publications in the Training Course Series, specifically Nos 37 and 47, Clinical Training of Medical Physicists Specializing in Radiation Oncology and Clinical Training of Medical Physicists

  4. Stabilization Operations Through Military Capacity Building-Integration Between Danish Conventional Forces and Special Operations Forces

    Science.gov (United States)

    2016-12-01

    INTENTIONALLY LEFT BLANK v ABSTRACT Due to instability in Africa and the Middle East, Denmark’s political commitment to deploy troops to stabilize ...Denmark’s political commitment to deploy troops to stabilize fragile regions is not expected to decrease in the near future. The political ambition for...fragile regions is not expected to decrease in the near future. The political ambition for Denmark is to conduct stabilization efforts through

  5. 10 CFR 73.73 - Requirement for advance notice and protection of export shipments of special nuclear material of...

    Science.gov (United States)

    2010-01-01

    ... shipments of special nuclear material of low strategic significance. 73.73 Section 73.73 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF PLANTS AND MATERIALS Records and Reports § 73.73... Incident Response, using any appropriate method listed in § 73.4; (2) Assure that the notification will be...

  6. Study of special challenges for NDT-methods on nuclear structures

    Energy Technology Data Exchange (ETDEWEB)

    Maack, Stefan; Wiggenhauser, Herbert [BAM Bundesanstalt fuer Materialforschung und -pruefung, Berlin (Germany); Thunell, Bjoern [Scanscot Technology AB, Lund (Sweden)

    2015-07-01

    The special design of buildings, constructed for nuclear power plants is a particular challenge for the nondestructive testing in the building industry. In particular the major component thicknesses, the degree of reinforcement and surface coating systems make the application of NDT methods difficult. The studies first steps were undertaken to determine to which extent established applications of these techniques are useable in the field of infrastructure buildings. Methods have been evaluated that are already state of the art. So for example the ground penetrating radar was used for locating metallic mounting parts. Furthermore, the low-lying internal structure of the containment was investigated with the ultrasonic method.

  7. U.S. N.R.C. special safeguards study on nuclear material control and accounting

    International Nuclear Information System (INIS)

    Smith, G.D.

    1976-01-01

    In Feb. 1975, NRC directed that an effort be made to determine a safeguards program for Pu recycle. This paper summarizes results of individual contractor evaluations of upgrading material control and accounting concepts as applied to strategically important special nuclear material and describes staff interpretations of these results as applied to future high-throughput fuel-cycle facilities. Real-time material control, design for physical inventory, Pu isotopics control and calorimetry, and material control and accounting for highly enriched uranium fuel materials were the concepts studied. 1 table, 15 references

  8. Computer-based accountability system (Phase I) for special nuclear materials at Argonne-West

    International Nuclear Information System (INIS)

    Ingermanson, R.S.; Proctor, A.E.

    1982-05-01

    An automated accountability system for special nuclear materials (SNM) is under development at Argonne National Laboratory-West. Phase I of the development effort has established the following basic features of the system: a unique file organization allows rapid updating or retrieval of the status of various SNM, based on batch numbers, storage location, serial number, or other attributes. Access to the program is controlled by an interactive user interface that can be easily understood by operators who have had no prior background in electronic data processing. Extensive use of structured programming techniques make the software package easy to understand and to modify for specific applications. All routines are written in FORTRAN

  9. A magnet without a magnetic circuit, of high homogeneity, specially for nuclear magnetic resonance images

    International Nuclear Information System (INIS)

    Barjhoux, Yves.

    1981-01-01

    This invention concerns a high homogeneity, double access magnet without a magnetic circuit. It is specially adapted for nuclear magnetic resonance (N.M.R.) imagery. Another advantage worth stressing resides in the possibilities of NMR in biochemical analysis which will enable, for instance, cancerous tumours to be detected in vivo. In order to increase the NMR signal ratio over background noise, it is necessary to increase the homogeneity of the B 0 orientating magnetic field. This magnetic field must orientate the nuclear magnetic moments of the elementary particles which compose the body being examined and in particular the protons. It must therefore be relatively constant in intensity and direction in the entire domain of the examination [fr

  10. Glass fiber sensors for detecting special nuclear materials at portal and monitor stations

    International Nuclear Information System (INIS)

    Hull, C.D.; Seymour, R.; Crawford, T.; Bliss, M.; Craig, R.A.

    2001-01-01

    Nuclear Safeguards and Security Systems LLC (NucSafe) participated in the Illicit Trafficking Radiation Assessment Program (ITRAP) recently conducted by the Austrian Research Center, Seibersdorf (ARCS) for IAEA, INTERPOL, and the World Customs Organization (IAEA, in press). This presentation reviews ITRAP test results of NucSafe instrumentation. NucSafe produces stationary, mobile, and hand-held systems that use neutron and gamma ray sensors to detect Special Nuclear Materials (SNM). Neutron sensors are comprised of scintillating glass fibers (trade name 'PUMA' for Pu Materials Analysis), which provide several advantages over 3 He and 10 BF 3 tubes. PUMA 6 Li glass fiber sensors offer greater neutron sensitivity and dynamic counting range with significantly less microphonic susceptibility than tubes, while eliminating transport and operational hazards. PUMA sensors also cost less per active area than gas tubes, which is important since rapid neutron detection at passenger, freight, and vehicle portals require large sensor areas to provide the required sensitivity

  11. Semi-annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1984-07-01

    This fourteenth periodic semiannual report of Inventory Differences (ID) covers the last six months of fiscal year 1983 (April 1, 1983 through September 30, 1983), for the Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of strategic special nuclear material (SSNM). Inventory Differences are expected in nuclear material processing and are not, in and of themselves, evidence of lost or stolen material. On the other hand, ID analysis provides valuable information on the effectiveness of the safeguards system's physical protection and material control measures as well as a check on the process controls and material management procedures. ID's outside safeguards control limits or involving a missing SSNM discrete item are investigated. If necessary, an operation may be shut down until an ID is resolved

  12. Nuclear Deterrence in South Asia - an Assessment of Deterrence and Stability in the India-Pakistan Conflict

    OpenAIRE

    Westh, Mark; Juel Giorgio, Maia; Wiegersma, Jakob; Madsen, Tina

    2011-01-01

    This paper offers a coherent assessment of the stability created by nuclear deterrence between India and Pakistan. Our examination posits the neorealist understanding of the stability created by nuclear deterrence in relation to alternative frameworks. To unfold the varying theoretical presuppositions upon which the concept of stability is based, three logically constructed analyses will be undertaken where the theories are explored in relation to empirical data. The Kargil Crisis in 1999 and...

  13. Special committee review of the Nuclear Regulatory Commission's severe accident risks report (NUREG--1150)

    International Nuclear Information System (INIS)

    Kouts, H.J.C.; Apostolakis, G.; Kastenberg, W.E.; Birkhofer, E.H.A.; Hoegberg, L.G.; LeSage, L.G.; Rasmussen, N.C.; Teague, H.J.; Taylor, J.J.

    1990-08-01

    In April 1989, the Nuclear Regulatory Commission's (NRC) Office of Nuclear Regulatory Research (RES) published a draft report ''Severe Accident Risks: An Assessment for Five US Nuclear Power Plants,'' NUREG-1150. This report updated, extended and improved upon the information presented in the 1974 ''Reactor Safety Study,'' WASH-1400. Because the information in NUREG-1150 will play a significant role in implementing the NRC's Severe Accident Policy, its quality and credibility are of critical importance. Accordingly, the Commission requested that the RES conduct a peer review of NUREG-1150 to ensure that the methods, safety insights and conclusions presented are appropriate and adequately reflect the current state of knowledge with respect to reactor safety. To this end, RES formed a special committee in June of 1989 under the provisions of the Federal Advisory Committee Act. The Committee, composed of a group of recognized national and international experts in nuclear reactor safety, was charged with preparing a report reflecting their review of NUREG-1150 with respect to the adequacy of the methods, data, analysis and conclusions it set forth. The report which precedes reflects the results of this peer review

  14. Simulation for transient stability study of the Taiwan power system - a nuclear majority system

    International Nuclear Information System (INIS)

    Huang, J.C.C.

    1984-01-01

    A transient stability program was developed for the Taiwan Power Company, which has a high proportion of nuclear generation in its power system. This program offers a new territory to investigate nuclear plant effects on the power system transient stability. This program also provides a high speed tool for the Taipower system operational planning. A generalized procedure of synchronous machine modeling for a large-scale stability study is presented. The merits and weaknesses of machine modeling can be comprehended through each item of this procedure. Three types of nonlinear synchronous machine modeling implemented into this stability program are derived by following this procedure. A robust subroutine was derived to perform the fourth order Runge-Kutta integration method, making the software programming neat and systematical. For simulating the nuclear plant influence on the system, this program implemented an additional four functions: load-limit operation simulated by a low-value gate in the governor model, bypass valve capacity monitored by sending out a warning message, rotor overspeed protection relay, and generator anti-motoring relay

  15. The ''nuclear car wash'': a scanner to detect illicit special nuclear material in cargo containers

    International Nuclear Information System (INIS)

    Slaughter, D. R.; Accatino, M. R.; Bernstein, A.; Dougan, A. D.; Hall, J. M.; Loshak, A.; Manatt, D. R.; Pohl, B. A.; Prussin, S. G.; Walling, R. S.; Weirup, D. L.

    2004-01-01

    There is an urgent need to improve the reliability of screening cargo containers for illicit nuclear material that may be hidden there for terrorist purposes. A screening system is described for detection of fissionable material hidden in maritime cargo containers. The system makes use of a low intensity neutron beam for producing fission; and the detection of the abundant high-energy γ rays emitted in the β-decay of short-lived fission products and β-delayed neutrons. The abundance of the delayed γ rays is almost an order of magnitude larger than that of the delayed neutrons normally used to detect fission and they are emitted on about the same time scale as the delayed neutrons, i.e., ∼1 min. The energy and temporal distributions of the delayed γ rays provide a unique signature of fission. Because of their high energy, these delayed γ rays penetrate loW--Z cargoes much more readily than the delayed neutrons. Coupled with their higher abundance, the signal from the delayed γ rays escaping from the container is predicted to be as much as six decades more intense than the delayed neutron signal, depending upon the type and thickness of the intervening cargo. The γ rays are detected in a large array of scintillators located along the sides of the container as it is moved through them. Measurements have confirmed the signal strength in somewhat idealized experiments and have also identified one interference when 14.5 MeV neutrons from the D, T reaction are used for the interrogation. The interference can be removed easily by the appropriate choice of the neutron source

  16. A data communications systems for tamper-protected special nuclear materials (SNM) inventory management

    International Nuclear Information System (INIS)

    Hurkamp, A.C.

    1995-01-01

    The Department of Energy (D.O.E.) is responsible for the long term storage and protection of large quantities of Special Nuclear Material (SNM). This material is stored within individual containers located in vaults. Security measures are required to ensure that the SNM remains within the canisters where it is stored and that it is not disturbed in any manner. Conventional security and inventory techniques are manpower intensive and often require exposure to radiation hazards. The Purpose of this D.O.E sponsored project is to develop a cost effective system to monitor Special Nuclear Materials that, when fielded, would result in an extension of manual inventory cycles at a wide variety of SNM storage locations. The system consists of a computer, radio frequency interrogator, and individual miniaturized radio frequency transponders (tags) that are co-located with individual SNM containers. Each tag can perform SNM inventory, tamper alarm, and multiple sensor data transmission to the interrogator under the control of software designed by the user. SNM custodians can customize the system by their choice of packaging, software, and sensors. When implemented in accordance with current department of energy (D.O.E.) Policy on SNM inventory extension, the system has the potential to qualify for maximum extension times thus saving considerable resources through reduction of radiation exposure

  17. A novel method to assay special nuclear materials by measuring prompt neutrons from polarized photofission

    Energy Technology Data Exchange (ETDEWEB)

    Mueller, J.M., E-mail: mueller@tunl.duke.edu [Triangle Universities Nuclear Laboratory, Durham, NC 27710 (United States); Department of Physics, Duke University, Durham, NC 27708 (United States); Ahmed, M.W. [Triangle Universities Nuclear Laboratory, Durham, NC 27710 (United States); Department of Physics, Duke University, Durham, NC 27708 (United States); Department of Mathematics and Physics, North Carolina Central University, Durham, NC 27707 (United States); Weller, H.R. [Triangle Universities Nuclear Laboratory, Durham, NC 27710 (United States); Department of Physics, Duke University, Durham, NC 27708 (United States)

    2014-08-01

    A novel method of measuring the enrichment of special nuclear material is presented. Recent photofission measurements using a linearly polarized γ-ray beam were performed on samples of {sup 232}Th, {sup 233,235,238}U, {sup 237}Np, and {sup 239,240}Pu. Prompt neutron polarization asymmetries, defined to be the difference in the prompt neutron yields parallel and perpendicular to the plane of beam polarization divided by their sum, were measured. It was discovered that the prompt neutron polarization asymmetries differed significantly depending on the sample. Prompt neutrons from photofission of even–even (non-fissile) targets had significant polarization asymmetries (∼0.2 to 0.5), while those from odd-A (generally fissile) targets had polarization asymmetries close to zero. This difference in the polarization asymmetries could be exploited to measure the fissile versus non-fissile content of special nuclear materials, and potentially to detect the presence of fissile material during active interrogation. The proposed technique, its expected performance, and its potential applicability are discussed.

  18. Physical protection of special nuclear materials in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Rossnagel, A.

    1987-01-01

    Measures to protect special nuclear materials in West Germany are based on a relatively likely average threat and not on the less-likely but maximum credible threat. The reason is to avoid the costs of maintaining a very high level of security that is seldom needed. The concept of delayed action, which divides the responsibility for security between private protection forces and local police forces, would be insufficient in the event of the maximum credible threat. In principle, sufficient security is possible only when the facilities and transports are constantly protected by a police force large enough to deal with the maximum credible threat without assistance from outside. They must also be adequately armed to avert all possible attackers, and they must be paid by the licensees. The threat of an insider(s) diverting special nuclear material can be addressed only by strengthening the scope and depth of the checks on applicants and employees and the permanent work controls. It is recognized, however, that such security measures may not be compatible with constitutional civil liberties

  19. A novel method to assay special nuclear materials by measuring prompt neutrons from polarized photofission

    International Nuclear Information System (INIS)

    Mueller, J.M.; Ahmed, M.W.; Weller, H.R.

    2014-01-01

    A novel method of measuring the enrichment of special nuclear material is presented. Recent photofission measurements using a linearly polarized γ-ray beam were performed on samples of 232 Th, 233,235,238 U, 237 Np, and 239,240 Pu. Prompt neutron polarization asymmetries, defined to be the difference in the prompt neutron yields parallel and perpendicular to the plane of beam polarization divided by their sum, were measured. It was discovered that the prompt neutron polarization asymmetries differed significantly depending on the sample. Prompt neutrons from photofission of even–even (non-fissile) targets had significant polarization asymmetries (∼0.2 to 0.5), while those from odd-A (generally fissile) targets had polarization asymmetries close to zero. This difference in the polarization asymmetries could be exploited to measure the fissile versus non-fissile content of special nuclear materials, and potentially to detect the presence of fissile material during active interrogation. The proposed technique, its expected performance, and its potential applicability are discussed

  20. Nuclear AMPK regulated CARM1 stabilization impacts autophagy in aged heart

    International Nuclear Information System (INIS)

    Li, Chen; Yu, Lu; Xue, Han; Yang, Zheng; Yin, Yue; Zhang, Bo; Chen, Mai; Ma, Heng

    2017-01-01

    Senescence-associated autophagy downregulation leads to cardiomyocyte dysfunction. Coactivator-associated arginine methyltransferase 1 (CARM1) participates in many cellular processes, including autophagy in mammals. However, the effect of CARM1 in aging-related cardiac autophagy decline remains undefined. Moreover, AMP-activated protein kinase (AMPK) is a key regulator in metabolism and autophagy, however, the role of nuclear AMPK in autophagy outcome in aged hearts still unclear. Hers we identify the correlation between nuclear AMPK and CARM1 in aging heart. We found that fasting could promote autophagy in young hearts but not in aged hearts. The CARM1 stabilization is markedly decrease in aged hearts, which impaired nucleus TFEB-CARM1 complex and autophagy flux. Further, S-phase kinase-associated protein 2(SKP2), responsible for CARM1 degradation, was increased in aged hearts. We further validated that AMPK dependent FoxO3 phosphorylation was markedly reduced in nucleus, the decreased nuclear AMPK-FoxO3 activity fails to suppress SKP2-E3 ubiquitin ligase. This loss of repression leads to The CARM1 level and autophagy in aged hearts could be restored through AMPK activation. Taken together, AMPK deficiency results in nuclear CARM1 decrease mediated in part by SKP2, contributing to autophagy dysfunction in aged hearts. Our results identified nuclear AMPK controlled CARM1 stabilization as a new actor that regulates cardiac autophagy. - Highlights: • AMPK-dependent CARM1 stabilization is an important nuclear mechanism in cardiac autophagy. • AMPK deficiency lead to SKP2-mediated decrease in CARM1. • AMPK–SKP2–CARM1 in the regulation of autophagy dysfunction in aged heart.

  1. Applying programmatic risk assessment to nuclear materials stabilization R and D planning

    International Nuclear Information System (INIS)

    Brown-Van Hoozer, S.A.; Kenley, C.R.

    1997-01-01

    A systems engineering approach to programmatic risk assessment, derived from the aerospace industry, was applied to various stabilization technologies to assess their relative maturity and availability for use in stabilizing nuclear materials. The assessment provided valuable information for trading off available technologies and identified the at-risk technologies that will require close tracking by the Department of Energy (DOE) to mitigate programmatic risks. This paper presents the programmatic risk assessment methodology developed for the 1995 R and D Plan and updated for the 1996 R and D Plan. Results of the 1996 assessment also are presented (DOE/ID-10561, 1996)

  2. Cell Cycle Regulates Nuclear Stability of AID and Determines the Cellular Response to AID.

    Directory of Open Access Journals (Sweden)

    Quy Le

    2015-09-01

    Full Text Available AID (Activation Induced Deaminase deaminates cytosines in DNA to initiate immunoglobulin gene diversification and to reprogram CpG methylation in early development. AID is potentially highly mutagenic, and it causes genomic instability evident as translocations in B cell malignancies. Here we show that AID is cell cycle regulated. By high content screening microscopy, we demonstrate that AID undergoes nuclear degradation more slowly in G1 phase than in S or G2-M phase, and that mutations that affect regulatory phosphorylation or catalytic activity can alter AID stability and abundance. We directly test the role of cell cycle regulation by fusing AID to tags that destabilize nuclear protein outside of G1 or S-G2/M phases. We show that enforced nuclear localization of AID in G1 phase accelerates somatic hypermutation and class switch recombination, and is well-tolerated; while nuclear AID compromises viability in S-G2/M phase cells. We identify AID derivatives that accelerate somatic hypermutation with minimal impact on viability, which will be useful tools for engineering genes and proteins by iterative mutagenesis and selection. Our results further suggest that use of cell cycle tags to regulate nuclear stability may be generally applicable to studying DNA repair and to engineering the genome.

  3. The stability of nuclear matter in the Nambu-Jona-Lasinio model

    Energy Technology Data Exchange (ETDEWEB)

    Bentz, W. E-mail: bentz@keyaki.cc.u-tokai.ac.jp; Thomas, A.W. E-mail: athomas@physics.adelaide.edu.au

    2001-12-17

    Using the Nambu-Jona-Lasinio model to describe the nucleon as a quark-diquark state, we discuss the stability of nuclear matter in a hybrid model for the ground state at finite nucleon density. It is shown that a simple extension of the model to simulate the effects of confinement leads to a scalar polarizability of the nucleon. This, in turn, leads to a less attractive effective interaction between the nucleons, helping to achieve saturation of the nuclear matter ground state. It is also pointed out that that the same effect naturally leads to a suppression of 'Z-graph' contributions with increasing scalar potential.

  4. Interim report on the special research project 'exposure to environmental radiation due to nuclear facilities'

    International Nuclear Information System (INIS)

    1981-03-01

    This special research project was started in 1978 as five-year plan. The purposes are to clarify the aspect of radiation exposure in human bodies due to the radioactive substances brought into the environment regarding the utilization of atomic energy, its mechanism and various factors affecting it, and to contribute to the evaluation of exposure dose, the reduction of radiation exposure, the conditions of locating nuclear facilities and the improvement of the method of disposing radioactive wastes. In addition to the fields treated in the previous special research project, the experimental research concerning the metabolism of environmental radioactive nuclides in bodies, namely the problem of the peculiarity of radioactive nuclide kinetics in infants and fetuses different from adults and the possibility of causing the changes in the intake and metabolism of nuclides in foods by the difference in their states of existence, was newly included. Also the research concerning the method of evaluating the absorbed dose in human organs at the time of irradiation outside and inside bodies in a new subject. Accordingly, this special research project is composed of (1) the research concerning the radionuclide kinetics in the environment, (2) the research concerning the radionuclide kinetics in bodies, (3) the research concerning the measurement and evaluation of dose absorbed in internal organs due to environmental radiation, and (4) the research concerning the monitoring of low level environmental radiation. The results obtained so far are reported. (Kako, I.)

  5. Clinical Training of Medical Physicists Specializing in Nuclear Medicine (Spanish Edition)

    International Nuclear Information System (INIS)

    2013-01-01

    The application of radiation in human health, for both diagnosis and treatment of disease, is an important component of the work of the IAEA. The responsibility for the increasingly technical aspects of this work is undertaken by the medical physicist. To ensure good practice in this vital area, structured clinical training programmes are required to complement academic learning. This publication is intended to be a guide to the practical implementation of such a programme for nuclear medicine. There is a general and growing awareness that radiation medicine is increasingly dependent on well trained medical physicists who are based in a clinical setting. However an analysis of the availability of medical physicists indicates a large shortfall of qualified and capable professionals. This is particularly evident in developing countries. While strategies to increase educational opportunities are critical to such countries, the need for guidance on structured clinical training was recognized by the members of the Regional Cooperative Agreement for Research, Development and Training related to Nuclear Science and Technology (RCA) for the Asia-Pacific region. Consequently, a technical cooperation regional project (RAS6038) under the RCA programme was formulated to address this need in this region by developing suitable material and establishing its viability. Development of a clinical training guide for medical physicists specialising in nuclear medicine was started in 2009 with the appointment of a core drafting committee of regional and international experts. The publication drew on the experience of clinical training in Australia, Croatia and Sweden and was moderated by physicists working in the Asian region. The present publication follows the approach of earlier IAEA publications in the Training Course Series, specifically Nos 37 and 47, Clinical Training of Medical Physicists Specializing in Radiation Oncology and Clinical Training of Medical Physicists

  6. Clinical Training of Medical Physicists Specializing in Nuclear Medicine (French Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    The application of radiation in human health, for both diagnosis and treatment of disease, is an important component of the work of the IAEA. The responsibility for the increasingly technical aspects of this work is undertaken by the medical physicist. To ensure good practice in this vital area, structured clinical training programmes are required to complement academic learning. This publication is intended to be a guide to the practical implementation of such a programme for nuclear medicine. There is a general and growing awareness that radiation medicine is increasingly dependent on well trained medical physicists who are based in a clinical setting. However an analysis of the availability of medical physicists indicates a large shortfall of qualified and capable professionals. This is particularly evident in developing countries. While strategies to increase educational opportunities are critical to such countries, the need for guidance on structured clinical training was recognized by the members of the Regional Cooperative Agreement for Research, Development and Training related to Nuclear Science and Technology (RCA) for the Asia-Pacific region. Consequently, a technical cooperation regional project (RAS6038) under the RCA programme was formulated to address this need in this region by developing suitable material and establishing its viability. Development of a clinical training guide for medical physicists specialising in nuclear medicine was started in 2009 with the appointment of a core drafting committee of regional and international experts. The publication drew on the experience of clinical training in Australia, Croatia and Sweden and was moderated by physicists working in the Asian region. The present publication follows the approach of earlier IAEA publications in the Training Course Series, specifically Nos 37 and 47, Clinical Training of Medical Physicists Specializing in Radiation Oncology and Clinical Training of Medical Physicists

  7. Special problems of setting up nuclear medicine in a developing country

    International Nuclear Information System (INIS)

    Ganatra, R.D.

    1992-01-01

    There are some special problems in setting up nuclear medicine in a developing country. They can be briefly described in the form of the following general rules. 1) Impossible triangle. For the practice of nuclear medicine, three things are needed: Instrument, Radiopharmaceutical and a Patient. In a developing country, these three become three sides of an impossible triangle. When the radiopharmaceutical is available, the instrument may not be working; when the instrument is functioning, the radiopharmaceutical may not have been obtained from the foreign supplier; and when both are there, the patient might no longer be in the hospital. Three sides of this triangle never join to become a congruent whole. 2) Reverse square law. Further away one is from the source of supply of instruments and radiopharmaceuticals, the problems multiply by the square of this distance. 3) Future of nuclear medicine is tied to the electrical supply available in a developing country. These problems related to power supply are described in the Chapter on maintenance of instruments

  8. Sheathed electrical resistance heaters for nuclear or other specialized service - approved 1973

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    This specification presents the requirements for cylindrical metal-sheathed, electrical resistance heaters with compacted mineral-oxide insulation for nuclear or other specialized service. The intended use of a sheathed heater in a specific nuclear or general application will require an evaluation by the purchaser of the compatibility of the heater assembly in the proposed application including the effects of the integrated proposed application including the effects of the integrated neutron flux, temperature, and atmosphere on the properties of the materials of construction. This specification does not include all possible specifications, standards, etc. for materials that may be used in sheathing, insulation, resistance wire, or conductors wire in nuclear environments. The requirements of this specification include only the austenitic stainless steels and nickel-based alloys for sheathing; magnesium oxide, aluminum oxide, beryllium oxide for insulation; and nickel-chromium or iron-chromium-aluminum heater elements with or without low-resistance connecting wires. The intent of this specification is to present the requirements for heaters capable of operating at sheath temperatures and heat fluxes that will limit the maximum internal heater-element temperature to 1050 0 C

  9. Special problems of setting up nuclear medicine in a developing country

    Energy Technology Data Exchange (ETDEWEB)

    Ganatra, R D

    1993-12-31

    There are some special problems in setting up nuclear medicine in a developing country. They can be briefly described in the form of the following general rules. 1) Impossible triangle. For the practice of nuclear medicine, three things are needed: Instrument, Radiopharmaceutical and a Patient. In a developing country, these three become three sides of an impossible triangle. When the radiopharmaceutical is available, the instrument may not be working; when the instrument is functioning, the radiopharmaceutical may not have been obtained from the foreign supplier; and when both are there, the patient might no longer be in the hospital. Three sides of this triangle never join to become a congruent whole. 2) Reverse square law. Further away one is from the source of supply of instruments and radiopharmaceuticals, the problems multiply by the square of this distance. 3) Future of nuclear medicine is tied to the electrical supply available in a developing country. These problems related to power supply are described in the Chapter on maintenance of instruments

  10. Strategic special nuclear material Inventory Differences. Semiannual report, April 1-September 30, 1984

    International Nuclear Information System (INIS)

    1985-07-01

    This sixteenth periodic semiannual report of Inventory Differences (ID) covers the last six months of fiscal year 1984 (April 1, 1984, through September 30, 1984), for the Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of strategic special nuclear material (SSNM). Inventory Differences are simply the differences between the amount of material shown in the accounting records and the amount of material reported in the physical inventory. These differences are generally due to errors in estimating material in unmeasurable form at the time of an inventory, unmeasurable holdup in equipment, measurement imprecisions, inaccuracies in initial determinations of SSNM produced or used in nuclear reactors, and inventory or bookkeeping errors. Both DOE and contractors operating DOE facilities carefully maintain, analyze, and investigate ID data. Inventory Differences are expected in nuclear material processing and are not, in and of themselves, evidence of lost or stolen material. On the other hand, ID analysis provides valuable information on the effectiveness of the safeguards system's physical protection and material control measures as well as a check on the process controls and material management procedures. ID's outside safeguards control limits or involving a missing SSNM discrete item are investigated. If necessary, an operation may be shut down until an ID is resolved

  11. Stabilities of nuclear waste forms and their geochemical interactions in repositories

    International Nuclear Information System (INIS)

    White, W.B.

    1980-01-01

    The stabilities of high-level nuclear waste forms in a repository environment are briefly discussed. The advantages and disadvantages of such waste forms as borosilicate glass, supercalcine ceramics, and synthetic minerals are presented in context with the different rock types which have been proposed as possible host rocks for repositories. It is concluded that the growing geochemical evidence favors the use of a silicate rock repository because of the effectiveness of aluminosilicate rocks as chemical barriers for most radionuclides

  12. Proceedings of the workshop nuclear structure of light nuclei far from stability experiment and theory

    International Nuclear Information System (INIS)

    Klotz, G.

    1991-01-01

    The volume discuss nuclear structure of light and nuclei far from stability. The discussions took place in five sessions. In session 1 β decay, in session 2 nuclei near N=20, in session 3 radioactive ion beams' study with help of electromagnetic separators, in session 4 beta decay of light nuclei, in session 5 further papers were discussed in shell models, binding energy and chart of nuclides. (G.P.)

  13. Strategic Stability Reconsidered: Prospects for Escalation and Nuclear War in the Middle East

    Energy Technology Data Exchange (ETDEWEB)

    Russell, J.A.

    2009-07-01

    for survival'. The paper first draws upon Thomas Schelling's ideas to assess the regional strategic framework, and finds systemic uncertainties which suggest that escalation by various parties - state and non-state actors - is a possible outcome. Both near-term and long-term scenarios are considered. The near-term nuclear use scenarios are all predicated on the assumption that nuclear use will occur within the context of escalation to or within war. As dangerous as these circumstances are, longer-term scenarios for nuclear use will also be proposed, which, like the alarming near-term scenarios, flow from the same unstable regional dynamics. The Middle East's unstable dynamics occur within a global environment characterized by a general sense of insecurity about various nuclear issues. Reflecting this situation, the Bulletin of Atomic Scientists recently moved its 'Doomsday Clock' from seven- to five minutes to midnight - the most advanced setting since 1981. Citing Iran's nuclear ambitions, North Korea's test of a nuclear weapon, the failure to secure nuclear materials, a controversial U.S. nuclear doctrine that some argue suggests an expanded role for nuclear weapons, and the continued presence of 26,000 nuclear weapons in the United States and Russia, the Bulletin expressed new concerns about global strategic stability. These developments occurred against a backdrop of the collapse of the 2005 Nonproliferation Treaty Review conference due, among other things, to disinterest in the global community in supporting the spread of nonproliferation norms. (author)

  14. Strategic Stability Reconsidered: Prospects for Escalation and Nuclear War in the Middle East

    International Nuclear Information System (INIS)

    Russell, J.A.

    2009-01-01

    Thomas Schelling's ideas to assess the regional strategic framework, and finds systemic uncertainties which suggest that escalation by various parties - state and non-state actors - is a possible outcome. Both near-term and long-term scenarios are considered. The near-term nuclear use scenarios are all predicated on the assumption that nuclear use will occur within the context of escalation to or within war. As dangerous as these circumstances are, longer-term scenarios for nuclear use will also be proposed, which, like the alarming near-term scenarios, flow from the same unstable regional dynamics. The Middle East's unstable dynamics occur within a global environment characterized by a general sense of insecurity about various nuclear issues. Reflecting this situation, the Bulletin of Atomic Scientists recently moved its 'Doomsday Clock' from seven- to five minutes to midnight - the most advanced setting since 1981. Citing Iran's nuclear ambitions, North Korea's test of a nuclear weapon, the failure to secure nuclear materials, a controversial U.S. nuclear doctrine that some argue suggests an expanded role for nuclear weapons, and the continued presence of 26,000 nuclear weapons in the United States and Russia, the Bulletin expressed new concerns about global strategic stability. These developments occurred against a backdrop of the collapse of the 2005 Nonproliferation Treaty Review conference due, among other things, to disinterest in the global community in supporting the spread of nonproliferation norms. (author)

  15. Climatic effects of nuclear war: The role of atmospheric stability and ground heat fluxes

    International Nuclear Information System (INIS)

    Mitchell, J.F.B.; Slingo, A.

    1988-01-01

    Most studies of the climatic effects of nuclear war have used atmospheric models with simple representations of important physical processes. In this work, a model is used which treats the diurnal cycle of insolation, and includes surface and boundary layer parameterizations which take into account static stability and a four-layer soil model. Three idealized experiments are described in which a band of smoke is prescribed over northern mid-latitudes in In the experiment, the standard model is used, in the second the effect of deep soil layers is ignored and in the third the stability dependence in the surface and boundary layer processes is removed. It is found that the inclusion of deep soil layers decreases the surface cooling by about 20%, whereas the inclusion of stability effects increases the cooling by about the same amount, though conclusions will depend to some extent on the model used. copyright American Geophysical Union 1988

  16. A Remedy to Crises: Danish Special Operations Forces in Whole-of-Government Stabilization Engagements

    Science.gov (United States)

    2016-06-01

    special operations forces, capacity building, state building 15. NUMBER OF PAGES 89 16. PRICE CODE 17. SECURITY CLASSIFICATION OF REPORT... psychology , beliefs (such as religion), and behaviors.”66 This knowledge is essential for decision makers who maneuver not only against adversaries, but...To further influence and inform target audiences, the military uses a variety of information-operation capabilities, including psychological

  17. Design criteria development for the structural stability of nuclear waste repository

    Energy Technology Data Exchange (ETDEWEB)

    Yun, C H [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Yu, T S [Daewoo Engineering Company, Sungnam (Korea, Republic of); Ko, H M [Seoul National Univ., Seoul (Korea, Republic of)

    1990-11-15

    The objective of the present project is to develop design criteria for the structural stability of rock cavity for the underground repository are defined, according to which detailed descriptions for design methodologies, design stages and stability analysis of the cavity are made. The proposed criteria can be used as a guide for the preparation of design codes which are to be established as the site condition and technical emplacement procedure are fixed. The present report first reviews basic safety requirements and criteria of the underground disposal of nuclear wastes for the establishment of design concepts and stability analysis of the rock cavity. Important factors for the design are also described by considering characteristics of the wastes and underground facilities. The present project has investigated technical aspects on the design of underground structures based on the currently established underground construction technologies, and presented a proposal for design criteria for the structural stability of the nuclear waste repository. The proposed criteria consist of general provisions, geological exploration, rock classification, design process and methods, supporting system, analyses and instrumentation.

  18. Direct reactions in inverse kinematics for nuclear structure studies far off stability at low incident energies

    International Nuclear Information System (INIS)

    Egelhof, P.

    1997-02-01

    The investigation of light-ion induced direct reactions with exotic beams in inverse kinematics gives access to a wide field of nuclear structure studies in the region far off stability. The present contribution will focus on the investigation of few-nucleon transfer reactions, which turn out to be most favourably studied with good-quality low-energy radioactive beams, as provided by the new generation of radioactive beam facilities presently planned or under construction at Caen, Grenoble, Munich, and elsewhere. An overview on the physics motivation, basically concerning nuclear structure and nuclear astrophysics questions, is given. Of particular interest are the nuclear shell model in the region far off stability, the two-body residual interaction in nuclei, the structure of halo nuclei, as well as the understanding of the r-process scenario. The experimental conditions, along with the experimental concept, for such measurements are discussed with particular emphasis on the kinematical conditions, the observables, as well as the appropriate detection schemes. The concept of a large solid angle TPC ionization chamber as an active target for experiments with low-energy radioactive beams is presented. It turns out to be a highly effective detection scheme, well suited for the present experimental conditions, at least for light exotic beams up to Z∼20. (orig.)

  19. Nuclear structure far from stability: the neutron-rich 69-79Cu isotopes

    International Nuclear Information System (INIS)

    Franchoo, Serge

    2015-01-01

    Far from stability, the nuclear structure that is predicted by the shell model is evolving. Old magic numbers disappear, while new ones appear. Our understanding of the underlying nuclear force that drives these changes is still incomplete. After a short overview across the nuclear chart, we discuss the strength functions of the shell-model orbitals in the neutron-rich copper isotopes towards the 78 Ni doubly-magic nucleus. These were measured in a 72 Zn(d, 3 He) 71 Cu proton pick-up reaction in inverse kinematics with a radioactive beam at the Ganil laboratory in France. We also present the latest results from a 80 Zn(p,2p) 79 Cu knockout experiment at Riken in Japan, leading to selective population of hole states in 79 Cu. Our findings show that the Z=28 shell gap in the neutron-rich copper isotopes is surprisingly steady against the addition of neutrons beyond N=40. (author)

  20. Stability and special metrics for complex vector bundles with global sections

    International Nuclear Information System (INIS)

    Xi Zhang

    2004-07-01

    In this paper, we study one kind of vortex equations on complex vector bundles over almost Hermitian manifolds and prove a Hitchin-Kobayashi type correspondence relating the existence of solutions of these vortex equations to a certain stability condition. (author)

  1. Mechanical stability of the cell nucleus: roles played by the cytoskeleton in nuclear deformation and strain recovery.

    Science.gov (United States)

    Wang, Xian; Liu, Haijiao; Zhu, Min; Cao, Changhong; Xu, Zhensong; Tsatskis, Yonit; Lau, Kimberly; Kuok, Chikin; Filleter, Tobin; McNeill, Helen; Simmons, Craig A; Hopyan, Sevan; Sun, Yu

    2018-05-18

    Extracellular forces transmitted through the cytoskeleton can deform the cell nucleus. Large nuclear deformation increases the risk of disrupting the nuclear envelope's integrity and causing DNA damage. Mechanical stability of the nucleus defines its capability of maintaining nuclear shape by minimizing nuclear deformation and recovering strain when deformed. Understanding the deformation and recovery behavior of the nucleus requires characterization of nuclear viscoelastic properties. Here, we quantified the decoupled viscoelastic parameters of the cell membrane, cytoskeleton, and the nucleus. The results indicate that the cytoskeleton enhances nuclear mechanical stability by lowering the effective deformability of the nucleus while maintaining nuclear sensitivity to mechanical stimuli. Additionally, the cytoskeleton decreases the strain energy release rate of the nucleus and might thus prevent shape change-induced structural damage to chromatin. © 2018. Published by The Company of Biologists Ltd.

  2. An evaluation of some special techniques for nuclear waste disposal in space

    Science.gov (United States)

    Mackay, J. S.

    1973-01-01

    A preliminary examination is reported of several special ways for space disposal of nuclear waste material which utilize the radioactive heat in the waste to assist in the propulsion for deep space trajectories. These include use of the wastes in a thermoelectric generator (RTG) which operates an electric propulsion device and a radioisotope - thermal thruster which uses hydrogen or ammonia as the propellant. These propulsive devices are compared to the space tug and the space tug/solar electric propulsion combination for disposal of waste on a solar system escape trajectory. Such comparisons indicate that the waste-RTG approach has considerable potential provided the combined specific mass of the waste container - RTG system does not exceed approximately 150 kg/kw sub e. Several exploratory numerical calculations have been made for high earth orbit and Earth escape destinations.

  3. Checking the special professional qualification of selected personnel of Czechoslovak nuclear power facilities

    International Nuclear Information System (INIS)

    Kovar, P.; Bahnova, V.

    1990-01-01

    The system of examinations of selected staff members of Czechoslovak nuclear power plants for their special professional quanlification is described in detail. This selected personnel includes secondary circuit operators, primary circuit operators, graduate shift leaders as well as reactor unit managers. Attention is paid to the structure, methodology, contents and criteria of evaluation of the written, oral and practical parts of the examination, which is sat for before the State Examination Commission. Based on the results of the examinations, the Czechoslovak Atomic Energy Commission grants, prolongs or cancels licenses for the particular functions. Over the period from 1985 to March 1989, 394 new licenses were issued, 93 licenses were prolonged and 4 were withdrawn. (Z.M.). 7 figs., 3 tabs., 3 refs

  4. Special issue on start of construction of the Ohma nuclear power plant of J-Power

    International Nuclear Information System (INIS)

    Takahashi, Taizo

    2008-01-01

    The Electric Power Development Co., Ltd. (J-Power) started construction of its Ohma nuclear power plant - a 1383 MWe Advanced Boiling Water Reactor (ABWR) - in Aomori prefecture on May 2008. The reactor of the Ohma plant will be the first to load MOX fuels in all of its reactor cores. It will be able to consume a quarter of all the recycled MOX fuels produced at Rokkasho reprocessing plant and hence make a major contribution to Japan's policy of recycling plutonium recovered from spent fuels. Special issue reviewed history and overview of the Ohma plant as well as its significance to enhance power generation portfolio in corresponding with national interests. Local governor's expectations and present state of the Ohma plant were also described. After preparation works, construction began on excavation of foundation for the service building, proceeding as always with safety the foremost priority during construction. (T. Tanaka)

  5. An activated barrier for protection of special nuclear materials in vital areas

    International Nuclear Information System (INIS)

    Timm, R.E.; Miranda, J.E.

    1984-01-01

    The Argonne National Laboratory and Sandia National Laboratory have recently installed an activated barrier, the Access Denial System (ADS) for the upgrade of safeguards of special nuclear materials. The technology of this system was developed in the late 70's by Sandia National Laboratory-Albuquerque. The installation was the first for the Department of Energy. Subsequently, two additional installations have been completed. The Access Denial System, combined with physical restraints, provide the system delay. The principal advantages of the activated barrier are: (1) it provides an order of magnitude improvement in delay over that of a fixed barrier, (2) it can be added to existing vital areas with a minimum of renovations, (3) existing operations are minimally impacted, and (4) health and safety risks are virtually nonexistent. Hardening of the vital areas using the ADS was accomplished in a costeffective manner

  6. Evaluating safeguards effectiveness against protracted theft of special nuclear material by insiders

    International Nuclear Information System (INIS)

    Al-Ayat, R.A.; Sicherman, A.

    1991-01-01

    The new draft DOE Material Control and Accountability Order 5633.3 requires that facilities handling special nuclear material (SNM) evaluate their effectiveness against protracted theft of SNM. Protracted theft means repeated thefts of small quantities of material to accumulate a goal quantity. In this paper the authors discuss issues regarding the evaluation of safeguards and describe how we are augmenting the Analytic System and Software for Evaluating Safeguards and Security (ASSESS) to provide the user with a tool for evaluating effectiveness against protracted theft. Currently, the Insider module of ASSESS focuses on evaluating the timely detection of abrupt theft attempts by various types of single nonviolent insiders. In this paper we describe the approach we're implementing to augment ASSESS to handle various cases of protracted theft attempts

  7. Activated barrier for protection of special nuclear materials in vital areas

    International Nuclear Information System (INIS)

    Timm, R.E.; Miranda, J.E.; Reigle, D.L.; Valente, A.D.

    1984-01-01

    The Argonne National Laboratory and Sandia National Laboratory have recently installed an activated barrier, the Access Denial System (ADS) for the upgrade of safeguards of special nuclear materials. The technology of this system was developed in the late 70's by Sandia National Laboratory-Albuquerque. The installation was the first for the Department of Energy. Subsequently, two additional installations have been completed. The Access Denial System, combined with physical restraints, provide the system delay. The principal advantages of the activated barrier are: (1) it provides an order of magnitude improvement in delay over that of a fixed barrier, (2) it can be added to existing vital areas with a minimum of renovations, (3) existing operations are minimally impacted, and (4) health and safety risks are virtually nonexistent. Hardening of the vital areas using the ADS was accomplished in a cost-effective manner. 3 references, 1 figure, 1 table

  8. Pressure Distribution Tests on a Series of Clark Y Biplane Cellules with Special Reference to Stability

    Science.gov (United States)

    Noyes, Richard W

    1933-01-01

    The pressure distribution data discussed in this report represents the results of part of an investigation conducted on the factors affecting the aerodynamic safety of airplanes. The present tests were made on semispan, circular-tipped Clark Y airfoil models mounted in the conventional manner on a separation plane. Pressure readings were made simultaneously at all test orifices at each of 20 angles of attack between -8 degrees and +90 degrees. The results of the tests on each wing arrangement are compared on the bases of maximum normal force coefficient, lateral stability at a low rate of roll, and relative longitudinal stability. Tabular data are also presented giving the center of pressure location of each wing.

  9. Guide for the preparation of applications for special nuclear material licenses of less than critical mass quantities - July 1976

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    This guide describes the type of information needed to evaluate an application for a specific license for receipt, possession, use, and transfer of special nuclear material. It is intended for applicants requesting authorization to possess and use up to 2000 grams of plutonium, total, in the form of sealed plutonium-beryllium neutron sources, and any special nuclear material in quantities and forms not sufficient to form a critical mass. The latter quantities are considered to be 350 grams of contained uranium-235, 200 grams of uranium-233, 200 grams of plutonium (in any form other than plutonium-beryllium neutron sources) or any combination of them

  10. Effects of stabilizers on the heat transfer characteristics of a nuclear waste canister

    International Nuclear Information System (INIS)

    Vafai, K.; Ettefagh, J.

    1986-07-01

    This report summarizes the feasibility and the effectiveness of using stabilizers (internal metal structural components) to augment the heat transfer characteristics of a nuclear waste canister. The problem was modeled as a transient two-dimensional heat transfer in two physical domains - the stabilizer and the wedge (a 30-degree-angle canister segment), which includes the heat-producing spent-fuel rods. This problem is solved by a simultaneous and interrelated numerical investigation of the two domains in cartesian and polar coordinate systems. The numerical investigations were performed for three cases. In the first case, conduction was assumed to be the dominant mechanism for heat transfer. The second case assumed that radiation was the dominant mechanism, and in the third case both radiation and conduction were considered as mechanisms of heat transfer. The results show that for typical conditions in a waste package design, the stabilizers are quite effective in reducing the overall temperature in a waste canister. Furthermore, the results show that increasing the stabilizer thickness over the thickness specified in the present design has a negligible effect on the temperature distribution in the canister. Finally, the presence of the stabilizers was found to shift the location of the peak temperature areas in the waste canister

  11. Design of stability-guaranteed fuzzy logic controller for nuclear steam generators

    International Nuclear Information System (INIS)

    Cho, Byung Hak

    1996-02-01

    A fuzzy logic controller(FLC) and a fuzzy logic filter(FLF), which have a special type of fuzzifier, inference engine, and defuzzifier, are applied to the water level control of a nuclear steam generator (S/G). It is shown that arbitrary two-input, single-output linear state feedback controllers can be adequately expressed by this FLC. A procedure to construct stability-guaranteed FLC rules is proposed. It contains the following steps: (1) The stable sector of linear feedback gains is obtained from the suboptimal concept based on LQR theory and the Lyapunov's stability criteria: (2) The stable sector of linear gains is mapped into two linear rule tables that are used as limits for the FLC rules: (3) The construction of an FLC rule table is done by choosing certain rules that lie between these limits. This type of FLC guarantees asymptotic stability of the control system. The FLF generates a feedforward signal of S/G feedwater from the steam flow measurement using a fuzzy concept. Through computer simulation, it is found that the FLC with the FLF works better than well-tuned PID controller with variable gains to reduce swell/shrink phenomena especially for the water level deviation and abrupt steam flow disturbances that are typical in the existing power plants. A neurofuzzy logic controller (NFLC), that is implemented by using multi-layered neural network to have the same function as the FLC discussed above, is designed. The automatic generation of NFLC rule table is accomplished by using back-error-propagation (BEP) algorithm. There are two separated paths at the error back-propagation in the S/G. One is to consider the level dynamics depending on the tank capacity, and the other is to take into account the reverse dynamics of S/G. The amounts of error back-propagated through these paths show opposite effects to the BEP algorithm each other at the swell/shrink phenomena. Through the computer simulation, it is found that the BEP algorithm adequately generates NFLC

  12. Very small HTGR nuclear power plant concepts for special terrestrial applications

    International Nuclear Information System (INIS)

    McDonald, C.F.; Goodjohn, A.J.

    1983-01-01

    The role of the very small nuclear power plant, of a few megawatts capacity, is perceived to be for special applications where an energy source as required but the following prevail: 1) no indigenous fossil fuel source, in long transport distances that add substantially to the cost of oil, coal in gas, and 3) secure long-term power production for defense applications with freedom from fuel supply lines. A small High Temperature Gas-Cooled reactor (HTGR) plant could provide the total energy needs for 1) a military installation, 2) an island base of strategic significance, 3) an industrial community or 4) an urban area. The small HTGR is regarded as a fixed-base installation (as opposed to a mobile system). All of the major components would be factory fabricated and transported to the site where emphasis would be placed on minimizing the construction time. The very small HTGR plant, currently in an early stage of design definition, has the potential for meeting the unique needs of the small energy user in both the military and private sectors. The plant may find acceptance for specialized applications in the industrialized nations and to meet the energy needs of developing nations. Emphasis in the design has been placed on safety, simplicity and compactness

  13. Special Purpose Nuclear Reactor (5 MW) for Reliable Power at Remote Sites Assessment Report

    Energy Technology Data Exchange (ETDEWEB)

    Sterbentz, James William [Idaho National Lab. (INL), Idaho Falls, ID (United States). Nuclear Science and Technology Division; Werner, James Elmer [Idaho National Lab. (INL), Idaho Falls, ID (United States). Nuclear Science and Technology Division; McKellar, Michael George [Idaho National Lab. (INL), Idaho Falls, ID (United States). Nuclear Science and Technology Division; Hummel, Andrew John [Idaho National Lab. (INL), Idaho Falls, ID (United States). Nuclear Science and Technology Division; Kennedy, John Charles [Idaho National Lab. (INL), Idaho Falls, ID (United States). Nuclear Science and Technology Division; Wright, Richard Neil [Idaho National Lab. (INL), Idaho Falls, ID (United States). Nuclear Science and Technology Division; Biersdorf, John Michael [Idaho National Lab. (INL), Idaho Falls, ID (United States). Nuclear Science and Technology Division

    2017-04-01

    The Phenomena Identification and Ranking Table (PIRT) technique was conducted on the Special Purpose Reactor nuclear plant design. The PIRT is a structured process to identify safety-relevant/safety-significant phenomena and assess the importance and knowledge base by ranking the phenomena. The Special Purpose Reactor is currently in the conceptual design stage. The candidate reactor has a solid monolithic stainless steel core with an array of heat pipes and fuel pellets embedded in the monolith. The heat pipes are used to remove heat from the core using simple, reliable, and well-characterized physics (capillarity, boiling, and condensation). In the initial design, one heat exchanger is used for the working fluid that produces energy, and a second heat exchanger is used to remove decay heat in emergency or shutdown conditions. In addition, a power conversion cycle such as an open-air Brayton system is available as an option for power conversion and process heat. This report summarizes and documents the process and scope of the four PIRT reviews, noting the major activities and conclusions. The identified phenomena, analyses, rationales, and associated ratings are presented along with a summary of the findings from the four individual PIRTs, namely (1) Reactor Accident and Normal Operations, (2) Heat Pipes, (3) Materials, and (4) Power Conversion. The PIRT reports for these four major system areas evaluated are attached as appendixes to this report and provide considerably more detail about each assessment as well as a more complete listing of the phenomena that were evaluated.

  14. Non-nuclear radiological emergencies. Special plan for radiological risk of the Valencian Community

    International Nuclear Information System (INIS)

    Rodríguez Rodrigo, I.; Piles Alepuz, I.; Peiró Juan, J.; Calvet Rodríguez, D.

    2015-01-01

    After the publication of the Radiological Hazard Basic Directive, Generalitat (the regional government in Valencian Community) initiated the edition of the pertinent Special Plan, with the objective to assemble the response of all the Security and Emergency Agencies, including the Armed Forces, in a radiological emergency affecting the territory of the Valencian Community, under a single hierarchy command. Being approved and homologated the Radiological Hazard Special Plan, Generalitat has undertaken the implementation process planned to finish in June 2015. Following the same process as other Plans, implementation is organized in a first informative stage, followed of a formative and training stage, and finishing with an activation exercise of the Plan. At the end of the process, is expected that every Agency will know their functions, the structure and organization in which the intervention takes place, the resources needed, and adapt their protocols to the Plan requirements. From the beginning, it has been essential working together with the Nuclear Safety Council, as is established in the agreement signed in order to collaborate in Planning, Preparedness and Response in Radiological Emergencies. [es

  15. Environmental-impact appraisal related to special nuclear materials. License No. SNM-696; Docket No. 70-734

    International Nuclear Information System (INIS)

    1983-06-01

    This Environmental Impact Appraisal is issued by the US Nuclear Regulatory Commission in response to an application by GA Technologies, Inc., (GA) for renewal of Special Nuclear Material (SNM) License No. SNM-696 covering plant operations at San Diego, California. The proposed action provides for continuing research, development, and production activities involving SNM, uranium enriched in the U-235 and U-233 isotopes, and plutonium

  16. Study of the stability of the stationary wave of nuclear fission

    International Nuclear Information System (INIS)

    Khotyanintsev, V.N.; Aksenov, A.V.; Khotyanintseva, E.N.; Pavlovich, V.N.

    2014-01-01

    Stability of the stationary wave of nuclear burning in fast reactor with uranium-plutonium fuel chain is investigated. The reactor model including 1-D diffusion equation in one-group approximation for neutron flux density and kinetic equations for nuclear densities describes slow evolution of nuclear densities followed by neutron flux. New analytical approach was proposed, which is based on the approximation of small wave velocity of the stationary wave. We obtain so-called wave velocity characteristic of the reactor which is the dependence of wave velocity to the effective absorber concentration. We show that due to instability of long-living 241 Pu a turning point and lower branch of stationary solutions appear. Numerical solution of the time dependent problem proves that the solutions of the lower branch are unstable. Thus, the turning point of the velocity characteristic corresponds to the lower margin of possible wave velocities of nuclear fission waves of the steady shape. At the same time the solutions of the upper branch are stable with respect to slow evolution of nuclear densities

  17. Special nuclear materials cutoff exercise: Issues and lessons learned. Volume 1: Summary of exercise

    International Nuclear Information System (INIS)

    Libby, R.A.; Davis, C.; Segal, J.E.; Stanbro, W.D.

    1995-08-01

    In a September 1993 address to the United Nations General Assembly, President Clinton announced a new nonproliferation and export control policy that established a framework for US efforts to prevent the proliferation of weapons of mass destruction. The new policy proposed that the US undertake a comprehensive approach to the growing accumulation of fissile material. One of the key elements was for the US to support a special nuclear materials (SNM) multilateral convention prohibiting the production of highly enriched uranium (HEU) or plutonium for nuclear explosives purposes or outside of international safeguards. This policy is often referred to as the President's Cutoff Initiative or the Fissile Material Cutoff Treaty (FMCT). Because both the US Department of Energy (DOE) and foreign reprocessing facilities similar to PUREX will likely to be inspected under a FMCT, the DOE Office of Arms Control and Nonproliferation, Negotiations and Analysis Division (DOE/NN-41) tasked Pacific Northwest Laboratory (PNL) to perform an information gathering exercise, the PUREX Exercise, using the Plutonium-Uranium Extraction (PUREX) Plant located on the Hanford Site in Washington State. PUREX is a former production reactor fuel reprocessing plant currently undergoing a transition to a ''decontamination and decommissioning (D ampersand D) ready'' mode. The PUREX Exercise was conducted March 29--30, 1994, to examine aspects of the imposition of several possible cutoff regimes and to study verification of non-production of SNM for nuclear weapons purposes or outside of safeguards. A follow-up activity to further examine various additional verification regimes was held at Los Alamos National Laboratory (LANL) on May 10, 1994

  18. Special national report of the Slovak Republic compiled under the convention on nuclear safety. April 2012

    International Nuclear Information System (INIS)

    2012-04-01

    A Special safety report of the Slovak Republic in 2012 is presented. An account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (0) Introduction; (0.1) Purpose of the report; (0.2) Brief description of the site characteristics and units; (1) Executive summary; (2) External events; (2.1) Seismic; (2.2) Flooding; (2.3) Extreme weather conditions; (3) Design issues; (3.1) Loss of electrical power; (3.2) Loss of the decay heat removal capability/ultimate heat sink; (3.3) Loss of the primary ultimate heat sink, combined with station black out (see stress tests specifications); (4) Severe accident management; (4.1) Organization and arrangements of the licensee to manage accidents; (4.2) Accident management measures in place at the various stages of a scenario of loss of the core cooling function; (4.3) Maintaining the containment integrity after occurrence of significant fuel damage (up to core meltdown) in the reactor core; (4.4) Accident management measures to restrict the radioactive releases; (5) National organizations (regulator, technical support organizations, operator, government); (5.1) Legislative and regulatory framework; (6) Emergency preparedness and response and post--accident management (off-site); (6.1) Implementation of legislation in the field of emergency preparedness; (7) International cooperation; (7.1) Conventions and communications; (7.2) Cooperation with the international organizations; (7.3) Providing feedback including occurrences at nuclear installations of other nuclear power plants abroad.

  19. Study of the stability of organic ligands usable for the spent nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Draye, Micheline

    1994-01-01

    The first part of this research thesis on the stability of organic ligands in radioactive environment, reports the study of the stability of the dicyclohexano-18-crown-6 (DCH18C6) in radioactive environment by using several analytical techniques (nuclear magnetic resonance or NMR, X-ray diffraction, Fourier transform infrared spectroscopy or FTIR, gas chromatography or GC, and coupled gas chromatography/mass spectroscopy). The seven main radiolysis products of DCH18C6 are identified and then synthesised to be tested in radioactive environment. These products are soluble in nitric medium, and partially precipitate plutonium, but cannot in any case disturb the reprocessing process based on a continuous extraction system. Chemical yields are computed and DCH18C6 appears to be a serious candidate for the reprocessing of spent nuclear fuels. The second part reports the study of the stability of the poly(4-vinylpyridine) or P4VP in radioactive environment. It appears that gamma radiations produce radicals in the P4VP which recombine in function of the irradiation dose. However, this material is very stable in acid environment and radioactive environment [fr

  20. Stability analysis of the high temperature thermal pebble bed nuclear reactor concept

    International Nuclear Information System (INIS)

    Vondy, D.R.

    1981-02-01

    A study was made of the stability of the high temperature gas-cooled pebble bed core against xenon-driven oscillation. This generic study indicated that a core as large as 3000 MW(t) could be stable. Several aspects present a challenge to analysis including the void space above the pebble bed, the effects of possible control rod configurations, and the temperature feedback contribution. Special methods of analysis were developed in this effort. Of considerable utility was the scheme of including an azimuthal buckling loss term in the neturon balance equations admitting direct solution of the first azimuthal harmonic for a core having azimuthal symmetry. This technique allows the linear stability analysis to be done solving two-dimensional (RZ) problems instead of three-dimensional problems. A scheme for removing the fundamental source contribution was also implemented to allow direct iteration toward the dominant harmonic solution, treating up to three dimensions with diffusion theory

  1. 2008 annual nuclear technology conference: opting out of the use of nuclear power. German special approach leads into a dead end of energy policy. Conference report

    International Nuclear Information System (INIS)

    Anon.

    2008-01-01

    The President of the Deutsches Atomforum, Dr. Walter Hohlefelder, emphasized in his opening address at the 2008 Annual Nuclear Technology Conference in Hamburg that the German special approach to nuclear power utilization led straight into a dead end of energy policy. ''The outcome is foreseeable: The ambitious German goals of carbon dioxide reduction are missed, the competitiveness of the country is jeopardized, dependency on foreign energy imports rises,'' Dr. Hohlefelder stated. In view of the growing challenges in energy policy Germany had no alternative but to reassess nuclear power. The only outcome of this reappraisal could be extension of the life of nuclear power plants currently in operation. This was necessary also in order to avoid an impending gap in German electricity supply, Dr. Hohlefelder added. He invited all stakeholders to join in an open, unbiased dialog. Dr. Hohlefelder openly criticized the continued ban on research into the development of new reactors. ''A policy of this kind, a policy which bans thinking, is unacceptable in a technology-oriented, industrialized nation such as Germany.'' Nuclear power technology as a high-tech area was a unique achievement which had contributed to the prosperity of the country. The Annual Nuclear Technology Conference, which was held for the 39th time this year, is one of the biggest specialized conferences in the nuclear field with an attendance, this year, of approximately 1300 participants from more than twenty nations. (orig.)

  2. Jobs for partners - significant stabilization factor for personnel of East Slovakia nuclear power plant

    International Nuclear Information System (INIS)

    Uvirova, E.

    1987-01-01

    The problem is discussed of employment of the wives of operating personnel of the nuclear power plant to be built in East Slovakia. It is expected that almost a half of the number of the wives have completed secondary education with final examination. A list is presented of openings best suitable for women. It is estimated that jobs for 1,580 women will have to be provided of which number 253 will be specialized jobs in health care and education. An increased number of vacancies are expected to be available, especially in the Kosice and Presov towns. (J.B.). 4 tabs., 4 refs

  3. Stability analysis of BWR nuclear-coupled thermal-hyraulics using a simple model

    Energy Technology Data Exchange (ETDEWEB)

    Karve, A.A.; Rizwan-uddin; Dorning, J.J. [Univ. of Virginia, Charlottesville, VA (United States)

    1995-09-01

    A simple mathematical model is developed to describe the dynamics of the nuclear-coupled thermal-hydraulics in a boiling water reactor (BWR) core. The model, which incorporates the essential features of neutron kinetics, and single-phase and two-phase thermal-hydraulics, leads to simple dynamical system comprised of a set of nonlinear ordinary differential equations (ODEs). The stability boundary is determined and plotted in the inlet-subcooling-number (enthalpy)/external-reactivity operating parameter plane. The eigenvalues of the Jacobian matrix of the dynamical system also are calculated at various steady-states (fixed points); the results are consistent with those of the direct stability analysis and indicate that a Hopf bifurcation occurs as the stability boundary in the operating parameter plane is crossed. Numerical simulations of the time-dependent, nonlinear ODEs are carried out for selected points in the operating parameter plane to obtain the actual damped and growing oscillations in the neutron number density, the channel inlet flow velocity, and the other phase variables. These indicate that the Hopf bifurcation is subcritical, hence, density wave oscillations with growing amplitude could result from a finite perturbation of the system even where the steady-state is stable. The power-flow map, frequently used by reactor operators during start-up and shut-down operation of a BWR, is mapped to the inlet-subcooling-number/neutron-density (operating-parameter/phase-variable) plane, and then related to the stability boundaries for different fixed inlet velocities corresponding to selected points on the flow-control line. The stability boundaries for different fixed inlet subcooling numbers corresponding to those selected points, are plotted in the neutron-density/inlet-velocity phase variable plane and then the points on the flow-control line are related to their respective stability boundaries in this plane.

  4. Study of the relationships between nuclear decontamination foams stability and their physicochemical properties

    International Nuclear Information System (INIS)

    Dame, C.

    2006-03-01

    The LPAD (French Atomic Energy Commission) develops innovative processes in the frame of the future dismantling of nuclear facilities. Formulations were developed using high viscosified foams stabilized by biodegradable nonionic surfactants: alkyl poly-glucosides and viscosifiers (xanthan gum), which allow us to increase the foam lifetime and thus contact time of chemical reactants with the facility walls. We have considered the relationships between physicochemical properties and foam stability through the exploration of the foam at three different scales: from the molecular range (micelles, surface tension and visco-elasticity), to the film and Plateau border range (XR reflectivity, surface shear viscosity) and to macroscopic range, meaning the whole foam (foaminess, liquid fraction and wall film thickness evolution). Finally, exploratory study is presented concerning simultaneous foam three scales characterisation by small angle neutron scattering. (author)

  5. Effects of nuclear electromagnetic pulse (EMP) on synchronous stability of the electric power system

    International Nuclear Information System (INIS)

    Manweiler, R.W.

    1975-11-01

    The effects of a nuclear electromagnetic pulse (EMP) on the synchronous stability of the electric power transmission and distribution systems are evaluated. The various modes of coupling of EMP to the power system are briefly discussed, with particular emphasis on those perturbations affecting the synchronous stability of the transmission system. A brief review of the fundamental concepts of the stability problem is given, with a discussion of the general characteristics of transient analysis. A model is developed to represent single sets as well as repetitive sets of multiple faults on the distribution systems, as might be produced by EMP. The results of many numerical stability calculations are presented to illustrate the transmission system's response from different types of perturbations. The important parameters of both multiple and repetitive faults are studied, including the dependence of the response on the size of the perturbed area, the fault density, and the effective impedance between the fault location and the transmission system. Both major load reduction and the effect of the opening of tie lines at the time of perturbation are also studied. We conclude that there is a high probability that EMP can induce perturbations on the distribution networks causing a large portion of the transmission network in the perturbed area to lose synchronism. The result would be an immediate and massive power failure

  6. 10 CFR 74.11 - Reports of loss or theft or attempted theft or unauthorized production of special nuclear material.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Reports of loss or theft or attempted theft or... Requirements § 74.11 Reports of loss or theft or attempted theft or unauthorized production of special nuclear... plutonium shall notify the NRC Operations Center within 1 hour of discovery of any loss or theft or other...

  7. Planning criteria for open pit mines under special consideration of slope stability and controlled blasting

    Energy Technology Data Exchange (ETDEWEB)

    Weise, H

    1986-04-01

    The criteria which influence the economics of a future surface mining operation are discussed; these include the size of the mine and the depth of the deposit. The methods of working are outlined - single bench, multiple bench - and choices of haulage equipment (trucks vs. conveyors) are discussed. For a mine using conveyors, the slope of the open pit will affect the operating cost. Pumps will be required to dewater the strata; it will be necessary to take steps to ensure slope stability. Bucket wheel excavators will be impeded by the presence of consolidated material, which may be best removed by shatter blasting. An example is given of the use of shatter blasting at the Neyveli lignite mine in Tamil Nadu, India. 5 references.

  8. Nuclear Gamma-Ray Spectroscopy at the Limit of Particle Stability

    International Nuclear Information System (INIS)

    Dr. Norbert Pietralla

    2006-01-01

    The research project ''Nuclear Gamma-Ray Spectroscopy at the Limit of Particle Stability'' with sponsor ID ''DE-FG02-04ER41334'' started late-summer 2004 and aims at the investigation of highly excited low-spin states of selected key-nuclei in the vicinity of the particle separation threshold by means of high-resolution gamma-ray spectroscopy in electromagnetic excitation reactions. This work addresses nuclear structures with excitation energies close to the binding energy or highly excited off-yrast states in accordance with the NSAC milestones. In 2005 the program was extended towards additional use of virtual photons and theoretical description of the low-lying collective excitations in the well deformed nuclei

  9. A numerical technique for enhanced efficiency and stability for the solution of the nuclear reactor equation

    International Nuclear Information System (INIS)

    Khotylev, V.A.; Hoogenboom, J.E.

    1996-01-01

    The paper presents new techniques for the solution of the nuclear reactor equation in diffusion approximation, that has enhanced efficiency and stability. The code system based on the new technique solves a number of steady-state and/or transient problems with coupled thermal hydraulics in one-, two-, or three dimensional geometry with reduced CPU time as compared to similar code systems of previous generations if well-posed neutronics problems are considered. Automated detection of ill-posed problem and selection of the appropriate numerical method makes the new code system capable of yielding a correct solution for wider range of problems without user intervention. (author)

  10. A numerical technique for enhanced efficiency and stability for the solution of the nuclear reactor equation

    Energy Technology Data Exchange (ETDEWEB)

    Khotylev, V.A.; Hoogenboom, J.E. [Delft Univ. of Technology, Interfaculty Reactor Inst., Delft (Netherlands)

    1996-07-01

    The paper presents new techniques for the solution of the nuclear reactor equation in diffusion approximation, that has enhanced efficiency and stability. The code system based on the new technique solves a number of steady-state and/or transient problems with coupled thermal hydraulics in one-, two-, or three dimensional geometry with reduced CPU time as compared to similar code systems of previous generations if well-posed neutronics problems are considered. Automated detection of ill-posed problem and selection of the appropriate numerical method makes the new code system capable of yielding a correct solution for wider range of problems without user intervention. (author)

  11. Dimensional stability of some Fe-Ni-Cr alloys used in nuclear power generation

    International Nuclear Information System (INIS)

    Marucco, A.; Nath, B.

    1983-01-01

    The dimensional stability of four materials used in the nuclear power industry, viz Nimonic PE16, 20Cr-25Ni steel, Alloy 600 and Inconel 690, have been studied using X-ray diffractometry, electrical resistivity and thin foil microscopic techniques. Appreciable reductions in lattice parameters of these alloys occur on exposure to temperatures of 823 deg K and below. An order-disorder transformation has been found to be responsible for the observed behaviour. The transformation kinetics, associated microstructural changes and the implications for the usage of these materials are discussed. (author)

  12. Static stability characteristics of the boilers at Oldbury nuclear power station

    International Nuclear Information System (INIS)

    Paynter, R.J.; Rea, J.

    1986-01-01

    The cause of an intermittent load loss at Oldbury Nuclear Power Station is shown to be the high sensitivity of boiler performance to the imposed spatial distribution of boiler gas inlet temperature. This high sensitivity is demonstrated to be a function of the inherent static stability characteristics of the boilers. The installation of orifice plates with a high flow resistance into the feed pipework to the half boilers has greatly reduced the boiler sensitivity and eliminated the intermittent load loss so that, on average, higher electrical generation is obtained from the station. (author)

  13. Development of bubble chambers with enhanced stability and sensitivity to low-energy nuclear recoils

    International Nuclear Information System (INIS)

    Bolte, W.J.; Collar, J.I.; Crisler, M.; Hall, J.; Holmgren, D.; Nakazawa, D.; Odom, B.; O'Sullivan, K.; Plunkett, R.; Ramberg, E.; Raskin, A.; Sonnenschein, A.; Vieira, J.D.

    2007-01-01

    The viability of using Bubble Chambers as dark matter particle detectors is considered. Techniques leading to the enhanced chamber stability needed for this new application are described in detail. Prototype trials show that sensitivity to the low-energy nuclear recoils induced by Weakly Interacting Massive Particles (WIMP) is possible in conditions of extreme insensitivity to minimum ionizing backgrounds. An understanding of detector response is demonstrated using existing theoretical models. We briefly comment on the prospects for detection of supersymmetric dark matter with large CF 3 I chambers

  14. A study on aseismic performance estimation of a nuclear facility from a viewpoint of structural stability

    International Nuclear Information System (INIS)

    En, Koshiro; Imazuka, Yoshikatsu; Okutani, Tetsuya; Akita, Shodo; Kawasato, Takeshi

    2004-01-01

    In estimating aseismic performance of a nuclear facility, structural stability is quantified in terms of ''contact ratio'' of a base considering dynamic soil-structure interaction. However, the maximum response in the time-domain non-linear analysis may strongly depend on the phase characteristics of input motions. The stochastic properties of the overturning moment and ''contact ratio'' are investigated through Monte Carlo simulation using 100 artificial seismic waves synthesized for the multi-damping design response spectra. The fragility curve is also proposed based on random vibration theory and its dependence on both geometric proportion of the structure and the amplitude of input motions is illustrated. (author)

  15. PROGRESS WITH K BASINS SLUDGE RETRIEVAL STABILIZATION & PACKAGING AT THE HANFORD NUCLEAR SITE

    Energy Technology Data Exchange (ETDEWEB)

    KNOLLMEYER, P.M.; PHILLIPS, C; TOWNSON, P.S.

    2006-01-30

    This paper shows how Fluor Hanford and BNG America have combined nuclear plant skills from the U.S. and the U.K. to devise methods to retrieve and treat the sludge that has accumulated in K Basins at the Hanford Site over many years. Retrieving the sludge is the final stage in removing fuel and sludge from the basins to allow them to be decontaminated and decommissioned, so as to remove the threat of contamination of the Columbia River. A description is given of sludge retrieval using vacuum lances and specially developed nozzles and pumps into Consolidation Containers within the basins. The special attention that had to be paid to the heat generation and potential criticality issues with the irradiated uranium-containing sludge is described. The processes developed to re-mobilize the sludge from the Consolidation Containers and pump it through flexible and transportable hose-in-hose piping to the treatment facility are explained with particular note made of dealing with the abrasive nature of the sludge. The treatment facility, housed in an existing Hanford building, is described, and the uranium-corrosion and grout packaging processes explained. The uranium corrosion process is a robust, tempered process very suitable for dealing with a range of differing sludge compositions. Optimization and simplification of the original sludge corrosion process design is described and the use of transportable and reusable equipment is indicated. The processes and techniques described in the paper are shown to have wide applicability to nuclear cleanup.

  16. Terminating Safeguards on Excess Special Nuclear Material: Defense TRU Waste Clean-up and Nonproliferation - 12426

    Energy Technology Data Exchange (ETDEWEB)

    Hayes, Timothy [Los Alamos National Laboratory, Carlsbad Operations Group (United States); Nelson, Roger [Department Of Energy, Carlsbad Operations Office (United States)

    2012-07-01

    The Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) manages defense nuclear material that has been determined to be excess to programmatic needs and declared waste. When these wastes contain plutonium, they almost always meet the definition of defense transuranic (TRU) waste and are thus eligible for disposal at the Waste Isolation Pilot Plant (WIPP). The DOE operates the WIPP in a manner that physical protections for attractiveness level D or higher special nuclear material (SNM) are not the normal operating condition. Therefore, there is currently a requirement to terminate safeguards before disposal of these wastes at the WIPP. Presented are the processes used to terminate safeguards, lessons learned during the termination process, and how these approaches might be useful for future defense TRU waste needing safeguards termination prior to shipment and disposal at the WIPP. Also described is a new criticality control container, which will increase the amount of fissile material that can be loaded per container, and how it will save significant taxpayer dollars. Retrieval, compliant packaging and shipment of retrievably stored legacy TRU waste has dominated disposal operations at WIPP since it began operations 12 years ago. But because most of this legacy waste has successfully been emplaced in WIPP, the TRU waste clean-up focus is turning to newly-generated TRU materials. A major component will be transuranic SNM, currently managed in safeguards-protected vaults around the weapons complex. As DOE and NNSA continue to consolidate and shrink the weapons complex footprint, it is expected that significant quantities of transuranic SNM will be declared surplus to the nation's needs. Safeguards termination of SNM varies due to the wide range of attractiveness level of the potential material that may be directly discarded as waste. To enhance the efficiency of shipping waste with high TRU fissile content to WIPP, DOE designed an

  17. Dual Neutral Particle Beam Interrogation of Intermodal Shipping Containers for Special Nuclear Material

    Science.gov (United States)

    Keith, Rodney Lyman

    Intermodal shipping containers entering the United States provide an avenue to smuggle unsecured or stolen special nuclear material (SNM). The only direct method fielded to indicate the presence of SNM is by passive photon/neutron radiation detection. Active interrogation using neutral particle beams to induce fission in SNM is a method under consideration. One by-product of fission is the creation of fragments that undergo radioactive decay over a time period on the order of tens of seconds after the initial event. The "delayed" gamma-rays emitted from these fragments over this period are considered a hallmark for the presence of SNM. A fundamental model is developed using homogenized cargos with a SNM target embedded at the center and computationally interrogated using simultaneous neutron and photon beams. Findings from analysis of the delayed gamma emissions from these experiments are intended to mitigate the effects of poor quality information about the composition and disposition of suspect cargo before examination in an active interrogation portal.

  18. Investigation of Active Interrogation Techniques to Detect Special Nuclear Material in Maritime Environments

    International Nuclear Information System (INIS)

    Miller, Thomas Martin; Patton, Bruce W.

    2010-01-01

    The detection and interdiction of special nuclear material (SNM) is still a high-priority focus area for many organizations around the world. One method that is commonly considered a leading candidate in the detection of SNM is active interrogation (AI). AI is different from its close relative, passive interrogation, in that an active source is used to enhance or create a detectable signal (usually fission) from SNM, particularly in shielded scenarios or scenarios where the SNM has a low activity. The use of AI thus makes the detection of SNM easier or, in some scenarios, even enables previously impossible detection. In this work the signal from prompt neutrons and photons as well as delayed neutrons and photons will be combined, as is typically done in AI. In previous work AI has been evaluated experimentally and computationally. However, for the purposes of this work, past scenarios are considered lightly shielded and tightly coupled spatially. At most, the previous work interrogated the contents of one standard cargo container (2.44 x 2.60 x 6.10 m) and the source and detector were both within a few meters of the object being interrogated. A few examples of this type of previous work can be found in references 1 and 2. Obviously, more heavily shielded AI scenarios will require larger source intensities, larger detector surface areas (larger detectors or more detectors), greater detector efficiencies, longer count times, or some combination of these.

  19. Technique for detecting a small magnitude loss of special nuclear material

    International Nuclear Information System (INIS)

    Pike, D.H.; Chernick, M.R.; Downing, D.J.

    The detection of losses of special nuclear materials has been the subject of much research in recent years. The standard industry practice using ID/LEID will detect large magnitude losses. Time series techniques such as the Kalman Filter or CUSUM methods will detect small magnitude losses if they occur regularly over a sustained period of time. To date no technique has been proposed which adequately addresses the problem of detecting a small magnitude loss occurring in a single period. This paper proposes a method for detecting a small magnitude loss. The approach makes use of the influence function of Hempel. The influence function measures the effect of a single inventory difference on a group of statistics. An inventory difference for a period in which a loss occurs can be expected to produce an abnormality in the calculated statistics. This abnormality is measurable by the influence function. It is shown that a one period loss smaller in magnitude than the LEID can be detected using this approach

  20. Technical and economical prerequisites of special district-heating nuclear power plant development

    International Nuclear Information System (INIS)

    Baturov, B.B.; Boldyrev, V.M.; Losev, V.L.; Sigal, M.V.

    1983-01-01

    Results are presented of technical and economical analysis of advisability of constructing combined Nuclear Power and Heating Plants (NPHP) assuring the possibility of their location near the areas of heat power consumption in case of observing a given degree of radiation safety for population and personnel. Specific features determining the choice of turbine-driven units for such plants are analyzed. Conditions of competiveness of a specialized NPHP with alternative power units, NPHP based on the WWER-1000 reactor and district heating plants (NDHP), are determined. Analysis of design specifications of NPHP with two VK-500 reactor units and structures of capital investments in such a plant reveal that an increase in the total capital investments in the NPHP would not exceed 2% with account of the difference in costs for grid heaters and a corresponding change in dimensions of operation rooms as well as changes in costs of heat removal system (within one site) at the TK turbine replacement by the T turbine

  1. On screening for Special Nuclear Materials (SNMs) with X-ray diffraction

    International Nuclear Information System (INIS)

    Harding, G.

    2010-01-01

    A novel detection technique employing X-ray diffraction (XRD) to screen for Special Nuclear Materials (SNMs), in particular for uranium, has been recently proposed. It is based on the interesting fact that uranium (and incidentally, plutonium) has a non-cubic lattice structure, in contrast to all other non-SNM, high-density elements of the Periodic Table. The principle of this screening technique is briefly elucidated by comparing the XRD lines of uranium with those of lead, a material of high atomic number (Z) commonly found in container traffic. Several physical conditions that must be satisfied to enable XRD for SNM screening are considered. To achieve adequate penetration, both of suspicious high-Z materials and their containers, photon energies of 1 MeV and above must be employed. Implications from partial coherence theory for the XRD measurement geometry at such photon energies are presented. The question of multiple scatter degradation of the coherent scatter signal is addressed. Technological considerations relevant to performing XRD at 1 MeV, particularly regarding the radiation source and detector, are discussed. A novel secondary aperture scheme permitting high energy XRD is presented. It is concluded that the importance of the application and the prospect of its feasibility are sufficient to warrant experimental verification.

  2. Evaluating safeguards effectiveness against protracted theft of special nuclear material by insiders

    International Nuclear Information System (INIS)

    Al-Ayat, R.; Sicherman, A.

    1991-01-01

    The new draft DOE Material Control and Accountability Order 5633.3 requires that facilities handling special nuclear material (SNM) evaluate their effectiveness against provided theft of SNMProtracted theft means repeated thefts of small quantities of material to accumulate a goal quanfity. To evaluate the safeguards effectiveness against pro thefts, one must addresses several issues: (1) defining relevant time frames for various threat scenarios and delayed detection safeguards: (2) identifying which safeguards come into play more than once because of repeated adversary actions or because of periodic occurrence during the theft time frame (e.g., daily administrative check on presence of material): (3) considering whether the second and subsequent applications of safeguards are different in effectiveness from the first; (4)synthesizing how physical security, material control, and material accountability safeguards combine to provide protection against protracted theft scenarios. In this paper we discuss these issues and describe how we are augmenting the Analytic System and Software for Evaluating Safeguards and Security (ASSESS) to provide the user with a tool for evaluating effectiveness against protracted theft. Currently, the Insider module of ASSESS focuses on evaluating the ''timely'' detection of abrupt theft attempts by various types of single nonviolent insiders. In this paper we describe the approach we're implementing to augment ASSESS to handle various cases of protracted theft attempts

  3. Validation of SIMULATE-3K for stability analysis of Laguna Verde nuclear plant

    Energy Technology Data Exchange (ETDEWEB)

    Castillo, Rogelio, E-mail: rogelio.castillo@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Alonso, Gustavo, E-mail: gustavo.alonso@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Instituto Politecnico Nacional, Unidad Profesional Adolfo Lopez Mateos, Ed. 9, Lindavista, D.F. 07300 (Mexico); Ramírez, J. Ramón, E-mail: ramon.ramirez@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico)

    2013-12-15

    Highlights: • Neutronic/thermal hydraulic event in Laguna Verde is modeled. • A good agreement is obtained between SIMULATE-3K results and data plant for frequency and DR. • Other noise analysis techniques are used for the same purpose with good agreement. • Validation of SIMULATE-3K for stability analysis of Laguna Verde is confirmed - Abstract: Boiling Water Reactors are two phase flow systems which are susceptible to different types of flow instabilities. Among these are the coupled neutronic/thermal-hydraulic instabilities, these may compromise established fuel safety limits. These instabilities are characterized by periodic core-power and hydraulic oscillations. SIMULATE-3K code has been tested for stability analysis for several benchmarks, however to qualify the SIMULATE-3K code for a particular power plant a specific reactor plant analysis must be done. In this paper, the plant model of Laguna Verde Nuclear Power Plant is built and SIMULATE-3K is tested against the 1995 coupled neutronic/thermal-hydraulic instability event of Laguna Verde. Results obtained show the adequacy of this code to specific Laguna Verde power plant stability analysis.

  4. Improving the calculated core stability by the core nuclear design optimization

    International Nuclear Information System (INIS)

    Partanen, P.

    1995-01-01

    Three different equilibrium core loadings for TVO II reactor have been generated in order to improve the core stability properties at uprated power level. The reactor thermal power is assumed to be uprated from 2160 MW th to 2500 MW th , which moves the operating point after a rapid pump rundown where the core stability has been calculated from 1340 MW th and 3200 kg/s to 1675 MW th and 4000 kg/s. The core has been refuelled with ABB Atom Svea-100 -fuel, which has 3,64% w/o U-235 average enrichment in the highly enriched zone. PHOENIX lattice code has been used to provide the homogenized nuclear constants. POLCA4 static core simulator has been used for core loadings and cycle simulations and RAMONA-3B program for simulating the dynamic response to the disturbance for which the stability behaviour has been evaluated. The core decay ratio has been successfully reduced from 0,83 to 0,55 mainly by reducing the power peaking factors. (orig.) (7 figs., 1 tab.)

  5. Special problems in nuclear instrumentation. Final report for period ending July 31, 1978

    International Nuclear Information System (INIS)

    Spokas, J.J.

    1979-01-01

    The development of special conducting plastics to meet the special needs of radiation dosimetry is reported. The most critical application of the special plastics is in the construction of ionization chambers which provide the best means of accurately measuring absorbed dose and exposure, low-noise signal cables, and electrometers for the ionization chambers are described

  6. Nuclear power newsletter Vol. 3, no. 3, special issue, September 2006

    International Nuclear Information System (INIS)

    2006-09-01

    The topics presented in this newsletter are: IAEA's Contribution to Peaceful Use of Nuclear Power by Mr. Sinha; IAEA's Contribution to Peaceful Use of Nuclear Power by Mr. Tipping; Message from the Director of the Division of Nuclear Power; Nuclear power plant operating performance and life cycle management; Improving organizational performance; Coordination of INPRO; Technology development for advanced reactors; Support for non-electric applications of nuclear power; Planned meetings in 2006 and 2007; Division of Nuclear Power Web site link. The first two topics have been indexed separately

  7. Mobile Pit verification system design based on passive special nuclear material verification in weapons storage facilities

    Energy Technology Data Exchange (ETDEWEB)

    Paul, J. N.; Chin, M. R.; Sjoden, G. E. [Nuclear and Radiological Engineering Program, George W. Woodruff School of Mechanical Engineering, Georgia Institute of Technology, 770 State St, Atlanta, GA 30332-0745 (United States)

    2013-07-01

    A mobile 'drive by' passive radiation detection system to be applied in special nuclear materials (SNM) storage facilities for validation and compliance purposes has been designed through the use of computational modeling and new radiation detection methods. This project was the result of work over a 1 year period to create optimal design specifications to include creation of 3D models using both Monte Carlo and deterministic codes to characterize the gamma and neutron leakage out each surface of SNM-bearing canisters. Results were compared and agreement was demonstrated between both models. Container leakages were then used to determine the expected reaction rates using transport theory in the detectors when placed at varying distances from the can. A 'typical' background signature was incorporated to determine the minimum signatures versus the probability of detection to evaluate moving source protocols with collimation. This established the criteria for verification of source presence and time gating at a given vehicle speed. New methods for the passive detection of SNM were employed and shown to give reliable identification of age and material for highly enriched uranium (HEU) and weapons grade plutonium (WGPu). The finalized 'Mobile Pit Verification System' (MPVS) design demonstrated that a 'drive-by' detection system, collimated and operating at nominally 2 mph, is capable of rapidly verifying each and every weapon pit stored in regularly spaced, shelved storage containers, using completely passive gamma and neutron signatures for HEU and WGPu. This system is ready for real evaluation to demonstrate passive total material accountability in storage facilities. (authors)

  8. Department of Energy (DOE) system for the transportation of strategic quantities of special nuclear material (SQ SNM)

    International Nuclear Information System (INIS)

    Dickason, D.P.

    1978-01-01

    Since 1947 DOE and its predecessor agencies, AEC and ERDA, have moved nuclear materials by a variety of commercial and government transportation modes. In the late 1960's world-wide terrorism and other dissident activities prompted the then-AEC to review its procedures for safeguarding SNM. These reviews resulted in immediate and long-range programs for improvement of overall safeguards. Domestic transportation of completed nuclear weapons and SNM used in the weapons program was selected for special consideration. In the early 1970's AEC started the development of a Safe Secure Trailer (SST) to transport nuclear weapons and nuclear components and the development and installation of a high frequency (HF) communications system to assure continuous radio contact between selected highway and rail shipments and Headquarters, Albuquerque Operations (ALO). Late 1974 AEC directed ALO to develop a transportation system to extend weapons-level protection to all AEC SQ SNM shipments and to consolidate, manage, and operate this system. As of September 1976 all SQ SNM was being transported in the Safe Secure DOE (then ERDA) transportation safeguards system, composed of the following principal elements: (1) Transport equipment consisting of Safe Secure Trailers and specially modified towing tractors; Safe Secure Railcars and specially modified escort coaches; and specially designed highway escort vehicles. (2) An automated high-frequency digital radio system that enables continuous communications between the transporting equipment and central control. (3) A courier force that operates all transport equipment (except aircraft and rail power units) and mobile communications equipment; provides armed protection for shipments; and assures proper safety en route. (4) A central Headquarters staff that plans, executes, and controls shipments and directs, manages, and operates the system

  9. Performance evaluation of a commercially available heat flow calorimeter and applicability assessment for safeguarding special nuclear materials

    International Nuclear Information System (INIS)

    Bracken, D.S.; Biddle, R.; Rudy, C.

    1998-01-01

    The performance characteristics of a commercially available heat-flow calorimeter will be presented. The heat-flow sensors within the calorimeter are based on thermopile technology with a vendor-quoted sensitivity of 150 microV/mW. The calorimeter is a full-twin design to compensate for ambient temperature fluctuations. The efficacy of temperature fluctuation compensations will also be detailed. Finally, an assessment of design applicability to special nuclear materials control and accountability and safeguarding will be presented

  10. Mechanical stability of bentonite buffer system for high level nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Lempinen, A. [Helsinki Univ. of Technology, Espoo (Finland). Lab. of Theoretical and Applied Mechanics

    1998-05-01

    According to present plans, high level nuclear waste in Finland is going to be disposed of in bedrock at a depth of several hundred metres. The spent fuel containers will be placed in boreholes drilled in the floors of deposition tunnels with engineered clay buffer, which is made of bentonite blocks. The tunnels will be filled with a mixture of bentonite and crushed rock. For stability calculations a thermomechanical model for compressed bentonite is needed. In the study a thermomechanically consistent model for reversible processes for swelling clays is presented. Preliminary calculations were performed and they show that uncertainty in material parameter values causes significantly different results. Therefore, measurements that are consistent with the model are needed 12 refs.

  11. Mechanical stability of bentonite buffer system for high level nuclear waste

    International Nuclear Information System (INIS)

    Lempinen, A.

    1998-05-01

    According to present plans, high level nuclear waste in Finland is going to be disposed of in bedrock at a depth of several hundred metres. The spent fuel containers will be placed in boreholes drilled in the floors of deposition tunnels with engineered clay buffer, which is made of bentonite blocks. The tunnels will be filled with a mixture of bentonite and crushed rock. For stability calculations a thermomechanical model for compressed bentonite is needed. In the study a thermomechanically consistent model for reversible processes for swelling clays is presented. Preliminary calculations were performed and they show that uncertainty in material parameter values causes significantly different results. Therefore, measurements that are consistent with the model are needed

  12. Stabilization

    Directory of Open Access Journals (Sweden)

    Muhammad H. Al-Malack

    2016-07-01

    Full Text Available Fuel oil flyash (FFA produced in power and water desalination plants firing crude oils in the Kingdom of Saudi Arabia is being disposed in landfills, which increases the burden on the environment, therefore, FFA utilization must be encouraged. In the current research, the effect of adding FFA on the engineering properties of two indigenous soils, namely sand and marl, was investigated. FFA was added at concentrations of 5%, 10% and 15% to both soils with and without the addition of Portland cement. Mixtures of the stabilized soils were thoroughly evaluated using compaction, California Bearing Ratio (CBR, unconfined compressive strength (USC and durability tests. Results of these tests indicated that stabilized sand mixtures could not attain the ACI strength requirements. However, marl was found to satisfy the ACI strength requirement when only 5% of FFA was added together with 5% of cement. When the FFA was increased to 10% and 15%, the mixture’s strength was found to decrease to values below the ACI requirements. Results of the Toxicity Characteristics Leaching Procedure (TCLP, which was performed on samples that passed the ACI requirements, indicated that FFA must be cautiously used in soil stabilization.

  13. The function of specialized organization in work safety engineering for nuclear installations

    International Nuclear Information System (INIS)

    Salvatore, J.E.L.

    1989-01-01

    The attributions of Brazilian CNEN in the licensing procedures of any nuclear installation are discussed. It is shown that the work safety engineering and industrial safety constitute important functions for nuclear safety. (M.C.K.) [pt

  14. The nuclear protein Artemis promotes AMPK activation by stabilizing the LKB1–AMPK complex

    International Nuclear Information System (INIS)

    Nakagawa, Koji; Uehata, Yasuko; Natsuizaka, Mitsuteru; Kohara, Toshihisa; Darmanin, Stephanie; Asaka, Masahiro; Takeda, Hiroshi; Kobayashi, Masanobu

    2012-01-01

    Highlights: ► The nuclear protein Artemis physically interacts with AMPKα2. ► Artemis co-localizes with AMPKα2 in the nucleus. ► Artemis promotes phosphorylation and activation of AMPK. ► The interaction between AMPKα2 and LKB1 is stabilized by Artemis. -- Abstract: AMP-activated protein kinase (AMPK) is a hetero-trimeric Ser/Thr kinase composed of a catalytic α subunit and regulatory β and γ subunits; it functions as an energy sensor that controls cellular energy homeostasis. In response to an increased cellular AMP/ATP ratio, AMPK is activated by phosphorylation at Thr172 in the α-subunit by upstream AMPK kinases (AMPKKs), including tumor suppressor liver kinase B1 (LKB1). To elucidate more precise molecular mechanisms of AMPK activation, we performed yeast two-hybrid screening and isolated the complementary DNA (cDNA) encoding the nuclear protein Artemis/DNA cross-link repair 1C (DCLRE1C) as an AMPKα2-binding protein. Artemis was found to co-immunoprecipitate with AMPKα2, and the co-localization of Artemis with AMPKα2 in the nucleus was confirmed by immunofluorescence staining in U2OS cells. Moreover, over-expression of Artemis enhanced the phosphorylation of AMPKα2 and the AMPK substrate acetyl-CoA carboxylase (ACC). Conversely, RNAi-mediated knockdown of Artemis reduced AMPK and ACC phosphorylation. In addition, Artemis markedly increased the physical association between AMPKα2 and LKB1. Taken together, these results suggest that Artemis functions as a positive regulator of AMPK signaling by stabilizing the LKB1–AMPK complex.

  15. The nuclear protein Artemis promotes AMPK activation by stabilizing the LKB1-AMPK complex

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Koji, E-mail: k_nakagawa@pharm.hokudai.ac.jp [Department of Pathophysiology and Therapeutics, Division of Pharmascience, Faculty of Pharmaceutical Sciences, Hokkaido University, N12 W6, Kita-ku, Sapporo, Hokkaido 060-0812 (Japan); Uehata, Yasuko; Natsuizaka, Mitsuteru; Kohara, Toshihisa; Darmanin, Stephanie [Department of Gastroenterology and Hematology, Graduate School of Medicine, Hokkaido University, N15 W7, Kita-ku, Sapporo, Hokkaido 060-8638 (Japan); Asaka, Masahiro [Department of Gastroenterology and Hematology, Graduate School of Medicine, Hokkaido University, N15 W7, Kita-ku, Sapporo, Hokkaido 060-8638 (Japan); Department of Cancer Preventive Medicine, Graduate School of Medicine, Hokkaido University, N15 W7, Kita-ku, Sapporo, Hokkaido 060-8638 (Japan); Takeda, Hiroshi [Department of Pathophysiology and Therapeutics, Division of Pharmascience, Faculty of Pharmaceutical Sciences, Hokkaido University, N12 W6, Kita-ku, Sapporo, Hokkaido 060-0812 (Japan); Department of Gastroenterology and Hematology, Graduate School of Medicine, Hokkaido University, N15 W7, Kita-ku, Sapporo, Hokkaido 060-8638 (Japan); Kobayashi, Masanobu [Department of Cancer Preventive Medicine, Graduate School of Medicine, Hokkaido University, N15 W7, Kita-ku, Sapporo, Hokkaido 060-8638 (Japan); School of Nursing and Social Services, Health Sciences University of Hokkaido, Ishikari-Toubetsu, Hokkaido 061-0293 (Japan)

    2012-11-02

    Highlights: Black-Right-Pointing-Pointer The nuclear protein Artemis physically interacts with AMPK{alpha}2. Black-Right-Pointing-Pointer Artemis co-localizes with AMPK{alpha}2 in the nucleus. Black-Right-Pointing-Pointer Artemis promotes phosphorylation and activation of AMPK. Black-Right-Pointing-Pointer The interaction between AMPK{alpha}2 and LKB1 is stabilized by Artemis. -- Abstract: AMP-activated protein kinase (AMPK) is a hetero-trimeric Ser/Thr kinase composed of a catalytic {alpha} subunit and regulatory {beta} and {gamma} subunits; it functions as an energy sensor that controls cellular energy homeostasis. In response to an increased cellular AMP/ATP ratio, AMPK is activated by phosphorylation at Thr172 in the {alpha}-subunit by upstream AMPK kinases (AMPKKs), including tumor suppressor liver kinase B1 (LKB1). To elucidate more precise molecular mechanisms of AMPK activation, we performed yeast two-hybrid screening and isolated the complementary DNA (cDNA) encoding the nuclear protein Artemis/DNA cross-link repair 1C (DCLRE1C) as an AMPK{alpha}2-binding protein. Artemis was found to co-immunoprecipitate with AMPK{alpha}2, and the co-localization of Artemis with AMPK{alpha}2 in the nucleus was confirmed by immunofluorescence staining in U2OS cells. Moreover, over-expression of Artemis enhanced the phosphorylation of AMPK{alpha}2 and the AMPK substrate acetyl-CoA carboxylase (ACC). Conversely, RNAi-mediated knockdown of Artemis reduced AMPK and ACC phosphorylation. In addition, Artemis markedly increased the physical association between AMPK{alpha}2 and LKB1. Taken together, these results suggest that Artemis functions as a positive regulator of AMPK signaling by stabilizing the LKB1-AMPK complex.

  16. Analytical one-dimensional frequency response and stability model for PWR nuclear power plants

    International Nuclear Information System (INIS)

    Hoeld, A.

    1975-01-01

    A dynamic model for PWR nuclear power plants is presented. The plant is assumed to consist of one-dimensional single-channel core, a counterflow once-through steam generator (represented by two nodes according to the nonboiling and boiling region) and the necessary connection coolant lines. The model describes analytically the frequency response behaviour of important parameters of such a plant with respect to perturbations in reactivity, subcooling or mass flow (both at the entrances to the reactor core and/or the secondary steam generator side), the perturbations in steam load or system pressure (on the secondary side of the steam generator). From corresponding 'open' loop considerations it can then be concluded - by applying the Nyquist criterion - upon the degree of the stability behaviour of the underlying system. Based on this theoretical model, a computer code named ADYPMO has been established. From the knowledge of the frequency response behaviour of such a system, the corresponding transient behaviour with respect to a stepwise or any other perturbation signal can also be calculated by applying an appropriate retransformation method, e.g. by using digital code FRETI. To demonstrate this procedure, a transient experimental curve measured during the pre-operational test period at the PWR nuclear power plant KKS Stade was recalculated using the combination ADYPMO-FRETI. Good agreement between theoretical calculations and experimental results give an insight into the validity and efficiency of the underlying theoretical model and the applied retransformation method. (Auth.)

  17. Stabilization, not polymerization, of microtubules inhibits the nuclear translocation of STATs in adipocytes

    International Nuclear Information System (INIS)

    Gleason, Evanna L.; Hogan, Jessica C.; Stephens, Jacqueline M.

    2004-01-01

    Signal transducers and activators of transcriptions (STATs) are a family of latent transcription factors which are activated by a variety of growth factors and cytokines in many cell types. However, the mechanism by which these transcription factors translocate to the nucleus is poorly understood. The goal of this study was to determine the requirement of microfilaments and microtubules for cytokine induced STAT activation in cultured adipocytes. We used seven different actin-specific and microtubule-specific agents that are well-established effectors of these cytoskeletal networks. Our results clearly demonstrate that inhibition of microfilaments or the prevention of microtubule polymerization has no effect on the ability of STATs to be tyrosine phosphorylated or to translocate to the nucleus. However, we observed that paclitaxel, a microtubule stabilizer, resulted in a significant decrease in the nuclear translocation of STATs without affecting the cytosolic tyrosine phosphorylation of these transcription factors. In summary, our results demonstrate that the dynamic instability, but not the polymerization, of microtubules contributes to nuclear translocation of STAT proteins in adipocytes

  18. Demonstration of mechanical connections between integrins, cytoskeletal filaments, and nucleoplasm that stabilize nuclear structure

    Science.gov (United States)

    Maniotis, A. J.; Chen, C. S.; Ingber, D. E.

    1997-01-01

    We report here that living cells and nuclei are hard-wired such that a mechanical tug on cell surface receptors can immediately change the organization of molecular assemblies in the cytoplasm and nucleus. When integrins were pulled by micromanipulating bound microbeads or micropipettes, cytoskeletal filaments reoriented, nuclei distorted, and nucleoli redistributed along the axis of the applied tension field. These effects were specific for integrins, independent of cortical membrane distortion, and were mediated by direct linkages between the cytoskeleton and nucleus. Actin microfilaments mediated force transfer to the nucleus at low strain; however, tearing of the actin gel resulted with greater distortion. In contrast, intermediate filaments effectively mediated force transfer to the nucleus under both conditions. These filament systems also acted as molecular guy wires to mechanically stiffen the nucleus and anchor it in place, whereas microtubules acted to hold open the intermediate filament lattice and to stabilize the nucleus against lateral compression. Molecular connections between integrins, cytoskeletal filaments, and nuclear scaffolds may therefore provide a discrete path for mechanical signal transfer through cells as well as a mechanism for producing integrated changes in cell and nuclear structure in response to changes in extracellular matrix adhesivity or mechanics.

  19. Debt swapping as a tool for economic and social stabilization in Russia's closed nuclear cities

    International Nuclear Information System (INIS)

    JL Fuller; KM Leek

    2000-01-01

    The magnitude of Russian foreign debt, both official bilateral and commercial, compounded by collapse of the Russian economic system, is an obstacle in preventing the Russian Federation from effectively increasing the domestic priority of drawing down its nuclear weapons complex and providing a healthy, competitive environment to its nuclear cities. Debt-for-nature swaps, introduced in the early 1980s, provide debtor nations with a means of converting a portion of foreign debt into local currency, often at steep discounts, to use for purposes such as environmental protection that serve both a domestic and international need. This paper presents the debt-for-nature concept as a model for providing an infusion of funds to further U.S. and international nonproliferation objectives to help stabilize Russian closed city economic conditions through direct work on proliferation problems and remediation of the environment. A specific proposal is presented to demonstrate the utility and efficacy of the dept swap concept through initial collaboration with the city administration of Ozersk. The purpose of the proposal is to facilitate making Ozersk a safe, healthy competitive city, providing useful employment for its scientists and population and converting its superior infrastructure into productive activities

  20. Natively Unfolded FG Repeats Stabilize the Structure of the Nuclear Pore Complex.

    Science.gov (United States)

    Onischenko, Evgeny; Tang, Jeffrey H; Andersen, Kasper R; Knockenhauer, Kevin E; Vallotton, Pascal; Derrer, Carina P; Kralt, Annemarie; Mugler, Christopher F; Chan, Leon Y; Schwartz, Thomas U; Weis, Karsten

    2017-11-02

    Nuclear pore complexes (NPCs) are ∼100 MDa transport channels assembled from multiple copies of ∼30 nucleoporins (Nups). One-third of these Nups contain phenylalanine-glycine (FG)-rich repeats, forming a diffusion barrier, which is selectively permeable for nuclear transport receptors that interact with these repeats. Here, we identify an additional function of FG repeats in the structure and biogenesis of the yeast NPC. We demonstrate that GLFG-containing FG repeats directly bind to multiple scaffold Nups in vitro and act as NPC-targeting determinants in vivo. Furthermore, we show that the GLFG repeats of Nup116 function in a redundant manner with Nup188, a nonessential scaffold Nup, to stabilize critical interactions within the NPC scaffold needed for late steps of NPC assembly. Our results reveal a previously unanticipated structural role for natively unfolded GLFG repeats as Velcro to link NPC subcomplexes and thus add a new layer of connections to current models of the NPC architecture. Copyright © 2017 Elsevier Inc. All rights reserved.

  1. Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multimodal transportation network

    Energy Technology Data Exchange (ETDEWEB)

    Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

    2010-01-01

    Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, and focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

  2. Modeling most likely pathways for smuggling radioactive and special nuclear materials on a worldwide multi-modal transportation network

    Energy Technology Data Exchange (ETDEWEB)

    Saeger, Kevin J [Los Alamos National Laboratory; Cuellar, Leticia [Los Alamos National Laboratory

    2010-10-28

    Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or special nuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, all focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

  3. Locating sensors for detecting source-to-target patterns of special nuclear material smuggling: a spatial information theoretic approach.

    Science.gov (United States)

    Przybyla, Jay; Taylor, Jeffrey; Zhou, Xuesong

    2010-01-01

    In this paper, a spatial information-theoretic model is proposed to locate sensors for detecting source-to-target patterns of special nuclear material (SNM) smuggling. In order to ship the nuclear materials from a source location with SNM production to a target city, the smugglers must employ global and domestic logistics systems. This paper focuses on locating a limited set of fixed and mobile radiation sensors in a transportation network, with the intent to maximize the expected information gain and minimize the estimation error for the subsequent nuclear material detection stage. A Kalman filtering-based framework is adapted to assist the decision-maker in quantifying the network-wide information gain and SNM flow estimation accuracy.

  4. Standard guide for application of radiation monitors to the control and physical security of special nuclear material

    International Nuclear Information System (INIS)

    Anon.

    1989-01-01

    This guide briefly describes the state-of-the-art of radiation monitors for detecting special nuclear material (SNM) in order to establish the context in which to write performance standards for the monitors. This guide extracts information from technical documentation to provide information for selecting, calibrating, testing, and operating such radiation monitors when they are used for the control and protection of SNM. This guide offers an unobtrusive means of searching pedestrians, packages, and motor vehicles for concealed SNM as one part of a nuclear material control or security plan for nuclear materials. The radiation monitors can provide an efficient, sensitive, and reliable means of detecting the theft of small quantities of SNM while maintaining a low likelihood of nuisance alarms

  5. Standard guide for application of radiation monitors to the control and physical security of special nuclear material

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1999-01-01

    1.1 This guide briefly describes the state-of-the-art of radiation monitors for detecting special nuclear material (SNM) (see 3.1.11) in order to establish the context in which to write performance standards for the monitors. This guide extracts information from technical documentation to provide information for selecting, calibrating, testing, and operating such radiation monitors when they are used for the control and protection of SNM. This guide offers an unobtrusive means of searching pedestrians, packages, and motor vehicles for concealed SNM as one part of a nuclear material control or security plan for nuclear materials. The radiation monitors can provide an efficient, sensitive, and reliable means of detecting the theft of small quantities of SNM while maintaining a low likelihood of nuisance alarms. 1.2 Dependable operation of SNM radiation monitors rests on selecting appropriate monitors for the task, operating them in a hospitable environment, and conducting an effective program to test, calibrat...

  6. Locating Sensors for Detecting Source-to-Target Patterns of Special Nuclear Material Smuggling: A Spatial Information Theoretic Approach

    Directory of Open Access Journals (Sweden)

    Xuesong Zhou

    2010-08-01

    Full Text Available In this paper, a spatial information-theoretic model is proposed to locate sensors for detecting source-to-target patterns of special nuclear material (SNM smuggling. In order to ship the nuclear materials from a source location with SNM production to a target city, the smugglers must employ global and domestic logistics systems. This paper focuses on locating a limited set of fixed and mobile radiation sensors in a transportation network, with the intent to maximize the expected information gain and minimize the estimation error for the subsequent nuclear material detection stage. A Kalman filtering-based framework is adapted to assist the decision-maker in quantifying the network-wide information gain and SNM flow estimation accuracy.

  7. A Stochastic Imaging Technique for Spatio-Spectral Characterization of Special Nuclear Material

    Science.gov (United States)

    Hamel, Michael C.

    Radiation imaging is advantageous for detecting, locating and characterizing special nuclear material (SNM) in complex environments. A dual-particle imager (DPI) has been designed that is capable of detecting gamma-ray and neutron signatures from shielded SNM. The system combines liquid organic and NaI(Tl) scintillators to form a combined Compton and neutron scatter camera. Effective image reconstruction of detected particles is a crucial component for maximizing the performance of the system; however, a key deficiency exists in the widely used list-mode maximum-likelihood estimation-maximization (MLEM) image reconstruction technique. The steady-state solution produced by this iterative method will have poor quality compared to solutions produced with fewer iterations. A stopping condition is required to achieve a better solution but these conditions fail to achieve maximum image quality. Stochastic origin ensembles (SOE) imaging is a good candidate to address this problem as it uses Markov chain Monte Carlo to reach a stochastic steady-state solution that has image quality comparable to the best MLEM solution. The application of SOE to the DPI is presented in this work. SOE was originally applied in medical imaging applications with no mechanism to isolate spectral information based on location. This capability is critical for non-proliferation applications as complex radiation environments with multiple sources are often encountered. This dissertation extends the SOE algorithm to produce spatially dependent spectra and presents experimental result showing that the technique was effective for isolating a 4.1-kg mass of weapons grade plutonium (WGPu) when other neutron and gamma-ray sources were present. This work also demonstrates the DPI as an effective tool for localizing and characterizing highly enriched uranium (HEU). A series of experiments were performed with the DPI using a deuterium-deuterium (DD) and deuterium-tritium (DT) neutron generator, as well as

  8. Stabilization of the outputs of pulse amplifiers utilizing non-linear feedback networks. Application to nuclear spectrometer amplifiers

    International Nuclear Information System (INIS)

    Henein, K.L.

    1978-02-01

    In nuclear spectroscopy, baseline instability and random fluctuations at the output of the amplifier create imperfectly solved problems mainly at high counting rates. After a critical examination of current systems, solutions are proposed which surpass existing ones. It is shown that restorers and stabilizers of baselines have their own preferential application. Considering natural limits of performance the proposed solutions give entirely satisfactory results [fr

  9. Necessity of Internal Monitoring for Nuclear Medicine Staff in a Large Specialized Chinese Hospital.

    Science.gov (United States)

    Wang, Hong-Bo; Zhang, Qing-Zhao; Zhang, Zhen; Hou, Chang-Song; Li, Wen-Liang; Yang, Hui; Sun, Quan-Fu

    2016-04-12

    This work intends to quantify the risk of internal contaminations in the nuclear medicine staff of one hospital in Henan province, China. For this purpose, the criteria proposed by the International Atomic Energy Agency (IAEA) to determine whether it is necessary to conduct internal individual monitoring was applied to all of the 18 nuclear medicine staff members who handled radionuclides. The activity of different radionuclides used during a whole calendar year and the protection measures adopted were collected for each staff member, and the decision as to whether nuclear medicine staff in the hospital should be subjected to internal monitoring was made on the basis of the criteria proposed by IAEA. It is concluded that for all 18 members of the nuclear medicine staff in the hospital, internal monitoring is required. Internal exposure received by nuclear medicine staff should not be ignored, and it is necessary to implement internal monitoring for nuclear medicine staff routinely.

  10. Transport of chemically bonded nuclear energy in a closed cycle with special consideration to energy disconnection

    International Nuclear Information System (INIS)

    Ossami, S.

    1976-01-01

    The article describes the utilisation of nuclear energy in the form of 'nuclear long-distance energy'. Heat produced by nuclear fission is bonded to a reversible chemical reaction (cracking gas) which release the heat again at the place of comsumption by catalytic transformation. The article deals in particular with the process of methane cracking/methanisation, the disconnection of the energy (heat) by the methanisation process and the decisive role of the methanisation catalyzers. (orig.) [de

  11. Legislation for the countermeasures on special issues of nuclear safety regulations

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Hak Man; Oh, Ho Chul [Chongju Univ., Cheongju (Korea, Republic of)

    2003-02-15

    Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea.

  12. The concept of nuclear-weapon-free zones, with special reference to East Asia

    International Nuclear Information System (INIS)

    Prawitz, J.

    1997-01-01

    The concept of nuclear-weapon-free zone, as it has developed from political deliberation since mid-1950s, today covers a spectrum of arrangements, geographically ranging from whole continent like Latin America to a corridor in central Europe, and functionally serving the purposes of preventing the spread of nuclear weapons and avoiding nuclear war. Among the nuclear-weapon-free zones proposed but not established, one is now being negotiated and two are subject to investigations published in official reports. These are the proposed zones in ASEAN area, The Middle East and Nordic Europe

  13. Legislation for the countermeasures on special issues of nuclear safety regulations

    International Nuclear Information System (INIS)

    Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Hak Man; Oh, Ho Chul

    2003-02-01

    Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea

  14. CNN's evaluation of the radiological monitoring special programs at the sites of nuclear installations

    International Nuclear Information System (INIS)

    Lareyne, O.; Marugan Tovar, I.; Martinez Moreno, M.; Sanz Alduan, M. T.

    2011-01-01

    In 2008, occurred in the Spanish plants various events related to the existence on the sites of the Spanish nuclear facilities or areas dotted with radioactive contamination outside the buildings, events that were reported to the Nuclear Safety Council (CSN) in accordance with the provisions of the regulation, as a result of the analysis of those events, the CSN issued in July 2008, a complementary technique INSTRUCTIONAL requiring the implementation of environmental monitoring programs in outdoor areas within sites nuclear tacilities. First, the CSN nuclear facilities referred to the programs and methodologies intended to perform such monitoring, and, in late 2009, reports of program results.

  15. Analysis of the emergency plan of Angra dos Reis Nuclear Power Plants: a critical view related to accessibility and mobility of people with special needs

    International Nuclear Information System (INIS)

    Correa, Luanda C.A.; Correa, Samanda C.A.; Santos, Geissa; Souza, Edmilson M.

    2014-01-01

    This work intends to make a critical analysis of the emergency plan of the Angra dos Reis Nuclear Power Plants related to appropriate transportation, accommodation and infrastructure for people with special needs

  16. Atmospheric stability modelling for nuclear emergency response systems using fuzzy set theory

    International Nuclear Information System (INIS)

    Walle, B. van de; Ruan, D.; Govaerts, P.

    1993-01-01

    A new approach to Pasquill stability classification is developed using fuzzy set theory, taking into account the natural continuity of the atmospheric stability and providing means to analyse the obtained stability classes. (2 figs.)

  17. Detection of special nuclear material from delayed neutron emission induced by a dual-particle monoenergetic source

    Energy Technology Data Exchange (ETDEWEB)

    Mayer, M. [Department of Mechanical and Nuclear Engineering, The Pennsylvania State University, University Park, Pennsylvania 16802 (United States); Nattress, J.; Jovanovic, I., E-mail: ijov@umich.edu [Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor, Michigan 48109 (United States)

    2016-06-27

    Detection of unique signatures of special nuclear materials is critical for their interdiction in a variety of nuclear security and nonproliferation scenarios. We report on the observation of delayed neutrons from fission of uranium induced in dual-particle active interrogation based on the {sup 11}B(d,n γ){sup 12}C nuclear reaction. Majority of the fissions are attributed to fast fission induced by the incident quasi-monoenergetic neutrons. A Li-doped glass–polymer composite scintillation neutron detector, which displays excellent neutron/γ discrimination at low energies, was used in the measurements, along with a recoil-based liquid scintillation detector. Time-dependent buildup and decay of delayed neutron emission from {sup 238}U were measured between the interrogating beam pulses and after the interrogating beam was turned off, respectively. Characteristic buildup and decay time profiles were compared to the common parametrization into six delayed neutron groups, finding a good agreement between the measurement and nuclear data. This method is promising for detecting fissile and fissionable materials in cargo scanning applications and can be readily integrated with transmission radiography using low-energy nuclear reaction sources.

  18. On-site transportation and handling of uranium-233 special nuclear material: Preliminary hazards and accident analysis. Final

    International Nuclear Information System (INIS)

    Solack, T.; West, D.; Ullman, D.; Coppock, G.; Cox, C.

    1995-01-01

    U-233 Special Nuclear Material (SNM) currently stored at the T-Building Storage Areas A and B must be transported to the SW/R Tritium Complex for repackaging. This SNM is in the form of oxide powder contained in glass jars which in turn are contained in heat sealed double polyethylene bags. These doubled-bagged glass jars have been primarily stored in structural steel casks and birdcages for approximately 20 years. The three casks, eight birdcages, and one pail/pressure vessel will be loaded onto a transport truck and moved over an eight day period. The Preliminary Hazards and Accident Analysis for the on-site transportation and handling of Uranium-233 Special Nuclear Material, documented herein, was performed in accordance with the format and content guidance of DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, dated July 1994, specifically Chapter Three, Hazard and Accident Analysis. The Preliminary Hazards Analysis involved detailed walkdowns of all areas of the U-233 SNM movement route, including the T-Building Storage Area A and B, T-Building truck tunnel, and the roadway route. Extensive discussions were held with operations personnel from the Nuclear Material Control Group, Nuclear Materials Accountability Group, EG and G Mound Security and the Material Handling Systems Transportation Group. Existing documentation related to the on-site transportation of hazardous materials, T-Building and SW/R Tritium Complex SARs, and emergency preparedness/response documentation were also reviewed and analyzed to identify and develop the complete spectrum of energy source hazards

  19. Introduction to This Special Issue of Georgia Social Science Journal on the Nuclear Arms Race.

    Science.gov (United States)

    Totten, Sam

    1985-01-01

    Of the many serious problems now facing the world, the most important is threat of nuclear destruction. Social studies educators should provide ample classroom time for discussing and examining the facts concerning nuclear warfare, and they must make sure that various points of view are presented. (RM)

  20. 77 FR 22362 - Exemption Requests for Special Nuclear Material License SNM-362, Department of Commerce...

    Science.gov (United States)

    2012-04-13

    ... Nuclear Material License SNM-362, Department of Commerce, Gaithersburg, MD AGENCY: Nuclear Regulatory... Commerce, National Institutes of Standards and Technology (NIST) in Gaithersburg, Maryland. NIST requested... within the Department of Commerce. The SNM license was renewed in 1979, 1985, 1991, and 1997. The current...

  1. The Unsuspected Roles of Chemistry in Nuclear Power Plants: Special Chemical Technologies for Enhanced Safety and Increased Performance

    International Nuclear Information System (INIS)

    Sempere Belda, Luis

    2008-01-01

    The plant's chemists main responsibility is the establishment and monitoring of an adequate water chemistry to minimize corrosion and in PWRs, to control the neutron flux. But this is by no means the only way in which chemical applications contribute to the performance and safety of a NPP during its entire life: The use of special coatings and treatment protects the plant's components from aggressive environmental conditions. The chemical scale removal in steam generators improves the power output of aging plants, helping even to achieve permissions for NPP life extension. The use of special adhesives can replace welding in complicated or high-dose areas, even underwater. And chemical decontamination is used to remove activity from the components of the primary circuit prior to maintenance or replacement works in order to decrease the radiation exposure of the plant's personnel, employing revolutionary methods of waste minimization to limit the amount of generated radioactive waste to a minimum. The AREVA Group, in its pursue of excellence in all stages of the nuclear cycle, has devoted years of research and development to be able to provide the most advanced technological solutions in this field. The awareness of the existing possibilities will help present and future nuclear professionals, chemists and non-chemists alike, to benefit from the years of experience and continuous development in chemical technologies at the service of the nuclear industry. (authors)

  2. Educational Research Centre of the Joint Institute for Nuclear Research and students training on the 'Medical Physics' speciality

    International Nuclear Information System (INIS)

    Ivanova, S.P.; )

    2005-01-01

    The Educational Research Centre (ERC) of the Joint Institute for Nuclear Research is the place of joint activity of the JINR, Moscow State University (MSU) and Moscow Engineering Physical Institute (MEFI) on students training by a broadened circle of specialities with introduction of new educational forms. Active application of medical accelerator beams of the JINR Laboratory of Nuclear Beams becomes a reason for implementation of a new training chair in the MEFI on the JINR base - the Physical methods in applied studies in the medicine chair. For the 'medical physics' trend development in 2003 the workshop on discussion both curricula and teaching methodic by the speciality was held. One the Educational Research Centre main activities is both organization and conducting an international scientific schools and training courses. The International student School 'Nuclear-Physical Methods and Accelerators is the most popular and traditional. The principal aim of these schools and courses is familiarization of students and postgraduates with last achievement and and contemporary problems of applied medical physics. The school audience is a students and postgraduates of ERC, MSU, MEFI, and an institutes of Poland, Hungary, Slovakia, France, Czech and Bulgaria

  3. The Analysis of the System of special water purification of Beloyarskaya Nuclear Power Plant unit BN-800

    Science.gov (United States)

    Valtseva, A. I.; Bibik, I. S.

    2017-11-01

    This article discusses how the latest system of special water purification KPF-30, designed specifically for the fourth power unit of Beloyarskaya nuclear power plant, which has a number of advantages over other water purification systems as chemical-physical and technical-economic, environmental, and other industrial indicators. The scheme covered in this article systems of special water purification involves the use of a hydrocyclone at the preliminary stage of water treatment, as a worthy alternative to ion-exchange filters, which can significantly reduce the volume of toxic waste. The world community implements the project of closing the nuclear fuel cycle, there is a need to improve the reliability of the equipment for safe processes and development of critical and supercritical parameters in the nuclear industry. Essentially, on operated NPP units, the only factor that can cost-effectively optimize to improve the reliability of equipment is the water chemistry. System KPF30 meets the principles and criteria of ecological safety, demonstrating the justification for reagent less method of water treatment on the main stages, in which no formation of toxic wastes, leading to irreversible consequences of environmental pollution and helps to conserve water.

  4. The Unsuspected Roles of Chemistry in Nuclear Power Plants: Special Chemical Technologies for Enhanced Safety and Increased Performance

    Energy Technology Data Exchange (ETDEWEB)

    Sempere Belda, Luis [AREVA NP GmbH, An AREVA and SIEMENS Company, P.O. Box 1109, Erlangen (Germany)

    2008-07-01

    The plant's chemists main responsibility is the establishment and monitoring of an adequate water chemistry to minimize corrosion and in PWRs, to control the neutron flux. But this is by no means the only way in which chemical applications contribute to the performance and safety of a NPP during its entire life: The use of special coatings and treatment protects the plant's components from aggressive environmental conditions. The chemical scale removal in steam generators improves the power output of aging plants, helping even to achieve permissions for NPP life extension. The use of special adhesives can replace welding in complicated or high-dose areas, even underwater. And chemical decontamination is used to remove activity from the components of the primary circuit prior to maintenance or replacement works in order to decrease the radiation exposure of the plant's personnel, employing revolutionary methods of waste minimization to limit the amount of generated radioactive waste to a minimum. The AREVA Group, in its pursue of excellence in all stages of the nuclear cycle, has devoted years of research and development to be able to provide the most advanced technological solutions in this field. The awareness of the existing possibilities will help present and future nuclear professionals, chemists and non-chemists alike, to benefit from the years of experience and continuous development in chemical technologies at the service of the nuclear industry. (authors)

  5. Development of NUFREQ-N, an analytical model for the stability analysis of nuclear coupled density-wave oscillations in boiling water nuclear reactors

    International Nuclear Information System (INIS)

    Park, G.C.

    1983-01-01

    A state-of-the-art one-dimensional thermal-hydraulic model has been developed to be used for the linear analysis of nuclear-coupled density-wave oscillations in a boiling water nuclear reactor (BWR). The model accounts for phasic slip, distributed spacers, subcooled boiling, space/time-dependent power distributions and distributed heated wall dynamics. In addition to a parallel channel stability analysis, a detailed model was derived for the BWR loop analysis of both the natural and forced circulation modes of operation. In its final form, this model constitutes a multi-input, multi-output (MIMO) linear system, which features a general nodal neutron kinetics model. Kinetics parameters for use in the kinetics model have been obtained by utilizing self-consistent nodal data and power distributions. The stability characteristics of a typical BWR/4 has been investigated with the Nyquist criterion. The computer implementation of this mode, NUFREQ-N, was used for the parametric study of a typical BWR/4 and comparison were made with existing in-core and out-of-core data. Also, NUFREQ-N was used to analyze the expected stability characteristics of a typical BWR/4. The parametric results revealed important factors influencing BWR stability margin. It was found that NUFREQ-N generally agreed well with out-of-core data. This was especially true for the predicted power-to-flow transfer function, which is the most important transfer function in thermal-hydraulic stability analysis

  6. Emerging trends in forensic science with special emphasis on nuclear and radiochemistry

    International Nuclear Information System (INIS)

    Krishnamurthy, Rukmani

    2011-01-01

    Forensic science uses the basic principles of all physical and natural science and have evolved many domain of its owns, like Anthropometry, fingerprint, Foot print, ballistics, documentation, Forensic Biology and Serology, Forensic Chemistry, Nuclear forensic science, Forensic Physic, Toxicology, Odontology, Forensic DNA, Cyber Forensic, Forensic Psychology, Forensic engineering etc., which provides a fool prove scientific aid to criminal justice administration. Nuclear forensic science is a fairly young discipline and only a small number of laboratories are active practitioners. However, the number of incidents of illicit trafficking reported and furthermore, the threat of nuclear terrorism calls for preparedness and for effective tools providing hints on the origin of the material and thus on the perpetrator. The determination of characteristic parameters is subject to ongoing research and development work in a number of nuclear measurement laboratories. Parameters like isotopic composition, chemical impurities, age of the material, macroscopic parameters and microstructure provide clues on the origin and on the intended use of the material. Today, nuclear forensics has reached a high degree of maturity and it is highly relevant in the areas of non-proliferation and of nuclear security. Continued development activities and strengthened international cooperation will be of key importance for the perfection of the discipline of nuclear forensics

  7. A special device used for measuring waste gas flow rate in the vent channel of Qinshan Nuclear Power Plant

    International Nuclear Information System (INIS)

    Zhang Yingjun; Zong Guifang; Shi Huaming; Yang Huimin; Jiang Yuana.

    1988-01-01

    A special Venturi-Pitot complex device is discribed which is used for measuring waste gas flow rate in the vent channel of Qinshan nuclear power plant. The device is located at the center of the channel. It can produce enlarged differential pressure signal under the condition of low gas velocity. And the flow resistance of this device is negligible. Experiments to determine the ratio of the velocity at the center of the channel to the average velocity were performed on a 1:12 test model. The special device was calibrated in a closed wind tunnel and its discharge coefficient was obtained. The uncertainty is ±3.5% and the nonlinearity is ±1.3%. The enlargement ratio and the discharge coefficient of the device are also deduced analytically on the basis of hydrodynamics theory

  8. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

  9. Finding of no significant impact. Consolidation and interim storage of special nuclear material at Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    1995-06-01

    The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II special nuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage

  10. Stabilization of neptunium valence states in nitric media for spent nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Feldhaus, P.

    1996-12-01

    A possibility of standarizing the extraction-behavior of Neptunium during the reprocessing of spent nuclear fuel corresponding to PUREX-Process was investigated. The aim of the work was a qualitative dirigation of the Transuraniumelement (TRUE) into the raffinat of the first extraction cycle by a complete redoxconversion of the Neptunium valence states to unextractable Np(V). In the beginning the theoretical and experimental research focussed on the redoxchemistry of the actinide during the fuel dissolution and the feed preparation. Thereby the nitrous acid, which is produced by a radiological, photochemical and reductive degradation of the nitric acid, revealed an ambivalent influence on the Neptunium valences. By a short-term increase in HNO 2 -concentration the Np(V)-fraction could be obviously risen. The use of some stabilizing reagents inhibited a later reoxidation to Np(VI) also catalyzed by nitrous acid. The urea used for this purpose also led to a further increase in the obtained conversion rates due to a Np(VI)-reduction. The analysis of the valence distribution was performed by an extraction method. This had been compared to chromatographic separation in some preliminary investigations and had turned out to be comparably reliable and easily manageable. (orig.) [de

  11. Influence of nuclear burning of the stability of degenerate and nondegenerate accretion disks

    International Nuclear Information System (INIS)

    Taam, R.E.; Fryxell, B.A.

    1985-01-01

    The structure and stability of accretion disks composed of hydrogen-rich matter rotating about a central neutron star have been investigated for known sources of viscosity. Two general classes of solutions have been found. For one class the energy generated in the disk is provided by hydrogen burning, whereas for the other class the gravitational binding energy released by viscous dissipation dominates. The former solutions are thermally unstable (stable) whenever hydrogen burns via the normal CNO cycle ( pp chain) in a partially or fully degenerate region of the disk. Solutions characterized by nuclear burning via the β-limited CNO cycle or by viscous dissipation only are always stable. On the basis of a local analysis it is shown that modulations of the mass flow in the disk are possible for a range of mass inflow rates into the disk. In such circumstances the disk can undergo a phase transition from a cold, low-viscosity state to a hot, high-viscosity state as a result of the thermonuclear flash instability. Phase transitions from the hot state to the cold state also occur whenever the mass input rate into the disk is less than the equilibrium mass flow rate corresponding to the hot state. It is also shown that for sufficiently high mass flow rates all the hydrogen-rich matter can be processed to helium in the inner regions of the disk before it can be accreted by a neutron star

  12. Impact of nuclear organization and chromatin structure on DNA repair and genome stability

    International Nuclear Information System (INIS)

    Batte, Amandine

    2016-01-01

    The non-random organization of the eukaryotic cell nucleus and the folding of genome in chromatin more or less condensed can influence many functions related to DNA metabolism, including genome stability. Double-strand breaks (DSBs) are the most deleterious DNA damages for the cells. To preserve genome integrity, eukaryotic cells thus developed DSB repair mechanisms conserved from yeast to human, among which homologous recombination (HR) that uses an intact homologous sequence to repair a broken chromosome. HR can be separated in two sub-pathways: Gene Conversion (GC) transfers genetic information from one molecule to its homologous and Break Induced Replication (BIR) establishes a replication fork than can proceed until the chromosome end. My doctorate work was focused on the contribution of the chromatin context and 3D genome organization on DSB repair. In S. cerevisiae, nuclear organization and heterochromatin spreading at sub-telomeres can be modified through the overexpression of the Sir3 or sir3A2Q mutant proteins. We demonstrated that reducing the physical distance between homologous sequences increased GC rates, reinforcing the notion that homology search is a limiting step for recombination. We also showed that hetero-chromatinization of DSB site fine-tunes DSB resection, limiting the loss of the DSB ends required to perform homology search and complete HR. Finally, we noticed that the presence of heterochromatin at the donor locus decreased both GC and BIR efficiencies, probably by affecting strand invasion. This work highlights new regulatory pathways of DNA repair. (author) [fr

  13. Rare and special indications for nuclear medicine evaluation of infective disease; Seltene und spezielle Indikationen fuer eine nuklearmedizinische Entzuendungsdiagnostik

    Energy Technology Data Exchange (ETDEWEB)

    Tesche, S.; Siefker, U.; Hamann, A.; Sahlmann, C.O.; Meller, J. [Goettingen Univ. (Germany). Abt. Nuklearmedizin; Meller, B. [Luebeck Univ. (Germany). Abt. Nuklearmedizin

    2007-06-15

    This article gives an evidence-based overview about several special indications for scintigraphy in imaging infection and inflammation. In diagnosing and evaluating the extent of inflammatory bowel disease, the scintigraphy with {sup 99m}Tc-HMPAO labelled leucocytes remains the standard evaluation in Nuclear Medicine. Appendicitis can be proven or excluded with a high grade of certainty both by {sup 99m}Tc-labelled monoclonal antigranulocytic antibodies and FAb'-fragments and by in-vitro labelled leucocytes. In endocarditis a late SPECT (20-24 h p. i.) with a {sup 99m}Tc-labeled anti-CD66 monoclonal antibody is a useful adjunct to echocardiographic techniques. In infected vascular prostheses, {sup 99m}Tc-HMPAO-labelled autologous leucocytes remain the standard of Nuclear Medicine although [{sup 18}F]FDG-PET or [{sup 18}F]FDG-PET / CT may exhibit a higher diagnostic accuracy. (orig.)

  14. American National Standard ANSI/ANS-8.15-1983: Nuclear criticality control of special actinide elements

    International Nuclear Information System (INIS)

    Brewer, R.W.; Pruvost, N.L.; Rombough, C.T.

    1996-01-01

    The American National Standard, 'Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors' ANSI/ANS-8.1- 1983 provides guidance for the nuclides [sup 233]U, [sup 235]U, and [sup 239]Pu These three nuclides are of primary interest in out-of-reactor criticality safety since they are the most commonly encountered in the vast majority of operations. However, some operations can involve nuclides other than 'U, 'U, and 'Pu in sufficient quantities that their effect on criticality safety could be of concern. The American National Standard, 'Nuclear Criticality Control of Special Actinide Elements' ANSI/ANS-8.'15-1983 (Ref 2), provides guidance for fifteen such nuclides

  15. Risks associated with low level ionizing radiation (with special reference to nuclear power workers)

    International Nuclear Information System (INIS)

    1989-01-01

    This document describes a project to use epidemiological studies of workers in the nuclear industry to estimate the cancer risk associated with low-dose chronic exposure to ionizing radiation. The project aims both to improve the basis for radiation risk assessment and to test the validity of currently used models for the extrapolation of radiation risk. This report focusses on the former aim, and summarizes discussions at two meetings held in June 1988. One of these was a small working group consisting mainly of epidemiologists who had carried out studies of nuclear workers; the other included nominees of the nuclear industries of eleven countries as well as epidemiologists and radiation physicists and biologists. As a result of the meetings, efforts are underway to pool existing data and a feasibility study is addressing the possibility of an international collaborative study of unstudied groups of nuclear workers

  16. 76 FR 34273 - Environmental Assessment and Finding of No Significant Impact for Special Nuclear Material...

    Science.gov (United States)

    2011-06-13

    ... Nuclear Material, TVA applied for an SNM license by application dated November 12, 2009 (ML100120487). The..., including site geography, demographics, meteorology, hydrology, and geology. The proposed activity is...

  17. Order of 10 october 1977 on the special safety measures applicable to certain large nuclear installations

    International Nuclear Information System (INIS)

    1978-01-01

    This Order by the Minister of Industry, Commerce and Crafts and the Minister of Labour was made in implementation of Section 40 of Decree No. 75-306 of 28 April 1975 on the protection of workers against the hazards of ionizing radiation in large nuclear installations. It lays down the safety measures applicable to nuclear reactors and ancillary facilities, particle accelerators, irradiated fuel reprocessing plants and facilities for the storage of radioactive waste. (NEA) [fr

  18. Reliability evaluation of power supply and distribution for special heat removal systems in nuclear power stations

    International Nuclear Information System (INIS)

    Jazbec, D.

    1982-01-01

    An example of the power supply and distribution of a Special Emergency Heat Removal System (SEHR) shows how an engineering organization may, with the aid of the analytical method of min-cut sets optimize the system reliability. Herein are given the necessary simple calculation methods. (Auth.)

  19. Physical protection of special nuclear material in the commercial fuel cycle. Volume I. Executive summary

    International Nuclear Information System (INIS)

    1976-04-01

    This is the summary of the work and recommendations resulting from Sandia's participation in the Special Safeguards Study, which covered three areas: protection of SNM at fixed facilities, protection of SNM while in transit, and relocation and recovery of lost SNM. The results are published in full in five other volumes. 6 tables, 4 fig

  20. Nuclear microscopy in biomedical analysis with special emphasis on clinical metal biology

    Science.gov (United States)

    Lindh, Ulf; Frisk, Peter; Nyström, Joakim; Danersund, Antero; Hudecek, Romuald; Lindvall, Anders; Thunell, Stig

    1997-07-01

    Nuclear microscopy based upon developments in high energy ion beam techniques is by now an accepted technique in many fields of research. The advancements into the biomedical field have, however, been slower than expected. A major factor explaining this tendency is the availability of nuclear microscopy. This paper reviews briefly the biomedical work using nuclear microscopy that has been carried out since the 4 th International Conference on Nuclear Microprobe Technology and Applications held in Shanghai. Nuclear microscopy of isolated individual blood cells from patients adversely affected by metal exposure from dental amalgam has been performed both before and after removal of the metallic fillings. The elemental profile of blood cells was more or less normalised after treatment. Some of these results will be presented to illustrate a medical application. Results from bulk analysis by ICP-MS of erythrocytes and plasma before and after treatment will also be presented to illustrate the difference in information content between these two approaches as well as the need for complementary information in solving biomedical problems. As part of a larger study of acute porphyria, nuclear microscopy of blood cells was included among the 78 laboratory tests. The approach in this study was unbiased in the sense that no hypothesis was formulated as to which laboratory parameters would be the most explanatory for health or disease. Multivariate discriminant analysis was applied to the large amounts of data acquired. This approach led to the hypothesis that oxidative stress increased the synthesis of manganese-dependent superoxide dismutase in the mitochondria of polymorphonuclear leukocytes, explaining the increase of manganese in these cells. Antioxidant therapy was therefore applied to a couple of patients with porphyria, however, without clinical success.

  1. Environmental impact analysis of the Nuclear Merchant Ship Program-addendum. Special study

    International Nuclear Information System (INIS)

    1977-06-01

    This study represents a qualitative extension of an earlier Environmental Impact Analysis of the Nuclear Merchant Ship Program (MarAd, 1975) using an Ultra Large Crude Carrier (ULCC) as the reference ship, to other types of ships including a containership, dry-bulk cargo vessel, and an icebreaking oil tanker. This qualitative analysis shows that, for ships operating into coastal ports (containerships and possibly dry-bulk carriers), both ecological and radiological impacts would be somewhat greater than for the reference ULCC docking at an offshore terminal. These impacts can be kept within the guidelines established for land based nuclear power plants by implementation of appropriate operating procedures

  2. Semi-annual report on strategic special nuclear material inventory differences

    International Nuclear Information System (INIS)

    1981-01-01

    This report provides and explains the differences between the amounts of nuclear materials charged to DOE facilities and the amounts that could be physically inventoried. This report covers data for the period from October 1, 1979, through March 31, 1980, and includes accounting corrections for data from earlier periods. It is the seventh such semiannual report. These data and explanations, together with the absences of physical indications of any theft attempt, support a finding that during this period no theft or diversion of strategic spcial nuclear material has occurred

  3. Some interesting aspects of water, with special reference to nuclear desalination

    International Nuclear Information System (INIS)

    Inam-ur-Rahman

    2002-01-01

    A brief review is given of the formation, importance, resources and some unique characteristics of water. A reference has been made about the available water racecourse of Pakistan and urgent need of acquiring additional water resources in the county. Importance of water for energy production and energy for acquiring additional water resources is mentioned. Attractive features and feasibility of nuclear desalination, using dual purpose nuclear power plants are discussed. Criteria for selection of suitable reactor type and desalination process are discussed for desired water to power ratios. The world wide growth of desalination capacity, using various desalination processes are listed. (author)

  4. High resolution positron Q-value measurements and nuclear structure studies far from the stability line. Progress report

    International Nuclear Information System (INIS)

    Avignone, F.T. III.

    1982-01-01

    Research progress in briefly described, and details are presented in the attached preprints and reprints: (1) precision mass differences in light rubidium and krypton isotopes utilizing beta endpoint measurements; (2) precision mass measurements utilizing beta endpoints; (3) Monte Carlo calculations predicting the response of intrinsic GE detectors to electrons and positrons; and (4) reactor antineutrino spectra and nuclear spectroscopy of isotopes far from beta stability

  5. Role of temperature in the radiation stability of yttria stabilized zirconia under swift heavy ion irradiation: A study from the perspective of nuclear reactor applications

    Science.gov (United States)

    Kalita, Parswajit; Ghosh, Santanu; Sattonnay, Gaël; Singh, Udai B.; Grover, Vinita; Shukla, Rakesh; Amirthapandian, S.; Meena, Ramcharan; Tyagi, A. K.; Avasthi, Devesh K.

    2017-07-01

    The search for materials that can withstand the harsh radiation environments of the nuclear industry has become an urgent challenge in the face of ever-increasing demands for nuclear energy. To this end, polycrystalline yttria stabilized zirconia (YSZ) pellets were irradiated with 80 MeV Ag6+ ions to investigate their radiation tolerance against fission fragments. To better simulate a nuclear reactor environment, the irradiations were carried out at the typical nuclear reactor temperature (850 °C). For comparison, irradiations were also performed at room temperature. Grazing incidence X-ray diffraction and Raman spectroscopy measurements reveal degradation in crystallinity for the room temperature irradiated samples. No bulk structural amorphization was however observed, whereas defect clusters were formed as indicated by transmission electron microscopy and supported by thermal spike simulation results. A significant reduction of the irradiation induced defects/damage, i.e., improvement in the radiation tolerance, was seen under irradiation at 850 °C. This is attributed to the fact that the rapid thermal quenching of the localized hot molten zones (arising from spike in the lattice temperature upon irradiation) is confined to 850 °C (i.e., attributed to the resistance inflicted on the rapid thermal quenching of the localized hot molten zones by the high temperature of the environment) thereby resulting in the reduction of the defects/damage produced. Our results present strong evidence for the applicability of YSZ as an inert matrix fuel in nuclear reactors, where competitive effects of radiation damage and dynamic thermal healing mechanisms may lead to a strong reduction in the damage production and thus sustain its physical integrity.

  6. Thermal stability of the French nuclear waste glass - long term behavior modeling

    International Nuclear Information System (INIS)

    Orlhac, X.

    2000-01-01

    The thermal stability of the French nuclear waste glass was investigated experimentally and by modeling to predict its long-term evolution at low temperature. The crystallization mechanisms were analyzed by studying devitrification in the supercooled liquid. Three main crystalline phases were characterized (CaMoO 4 , CeCO 2 , ZnCr 2 O 4 ). Their crystallisation was TO 4.24 wt%, due to the low concentration of the constituent elements. The nucleation and growth curves showed that platinoid elements catalysed nucleation but did not affect growth, which was governed by volume diffusion. The criteria of classic nucleation theory were applied to determine the thermodynamic and diffusional activation energies. Viscosity measurements illustrate the analogy between the activation energy of viscous flow and diffusion, indicating control of crystallization by viscous flow phenomena. The combined action of nucleation and growth was assessed by TTT plots, revealing a crystallization equilibrium line that enables the crystallized fractions to be predicted over the long term. The authors show that hetero-genetics catalyze the transformation without modifying the maximum crystallized fraction. A kinetic model was developed to describe devitrification in the glass based on the nucleation and growth curves alone. The authors show that the low-temperature growth exhibits scale behavior (between time and temperature) similar to thermo-rheological simplicity. The analogy between the resulting activation energy and that of the viscosity was used to model growth on the basis of viscosity. After validation with a simplified (BaO 2 SiO 2 ) glass, the model was applied to the containment glass. The result indicated that the glass remained completely vitreous after a cooling scenario with the one measured at the glass core. Under isothermal conditions, several million years would be required to reach the maximum theoretical crystallization fraction. (author)

  7. Special points of health physics in connection with the operation of a nuclear power plant

    International Nuclear Information System (INIS)

    Samuel, T.

    1981-01-01

    The paper covers the origin of the radioactivity in nuclear power plants, the type of sources (open or sealed) encountered, and their methods of measurement. It covers the problem of personnel dosimetry, including contamination and incorporation, and the administrative methods used to avoid these. It outlines a general work philosophy, as developed in an actual power plant. (orig./RW)

  8. A survey of infrared technology for special nuclear materials control and accounting

    International Nuclear Information System (INIS)

    Stanbro, W.D.; Leonard, R.S.; Steverson, C.A.; Angerman, M.I.

    1992-03-01

    This report reviews some aspects of current infrared measurement technology and suggests two applications in which it may be used in nuclear safeguards. These applications include both materials control and materials accounting. In each case, the measurements rely on passive detection of infrared radiation generated from the heat produced by the radioactive decay of plutonium. Both imaging and non-imaging techniques are discussed

  9. Population information on major technological risks and specially on nuclear risk

    International Nuclear Information System (INIS)

    De Choudens, H.

    1992-01-01

    Following Chernobyl accident which has revealed in France a strong need for information on technological risks among population and a lack in its organization, the Mayor of Grenoble City who was also at this time, Environment Minister in French Government had initiated in lsere Region an important operation of consideration of action, which has to been undertaken to correct theses lacks. Among ten actions retained one of them was the creation of an Association for Information of the public for Prevention of major risks. This Association has first initiated a consultation on the perception by the population of the different major risks (Industrial and Naturals) in view of the results of this consultation, Medical Professions were the first concerned and a publication 'Medicine and Nuclear risk' has been elaborated and distributed to all doctors of the Region. A Memento on Nuclear risk as then been written and largely distributed in the region, especially in the medias. A booklet on nuclear risk and behavior in case of nuclear accident has then been realized and distributed to all people around Electronuclear Reactors of the Region and to children in the schools. In complement, public meetings have been organized in these sectors to inform, and discuss with the population. (author)

  10. Britain’s Nuclear Deterrent Force and the U.S.-U.K. Special Relationship

    Science.gov (United States)

    2014-06-01

    Role,” Science 214, no. 4518 (1981): 324, http://www.jstor.org/stable/1686877. 80 Ferenc Morton Szasz , The Day the Sun Rose Twice: The Story of the...Richard N. Defense of the Realm: British Strategy in the Nuclear Epoch. New York: Columbia University Press, 1968. Szasz , Ferenc Morton. The Day

  11. Czechoslovakia's electrical energy industry with special regard on the development of nuclear power plants

    International Nuclear Information System (INIS)

    Paulina, A.

    1979-01-01

    In electric energy production and consumption, Czechoslovakia holds a remarkable place. Its development after the second world war can be divided into four characteristic periods. The author summarizes the features of the past development and points out the tasks of the future in which the extension of nuclear power plant building plays an important role. (author)

  12. Impact of phase stability on the corrosion behavior of the austenitic candidate materials for NNWSI [Nevada Nuclear Waste Storage Investigations

    International Nuclear Information System (INIS)

    Bullen, D.B.; Gdowski, G.E.; McCright, R.D.

    1987-10-01

    The Nuclear Waste Management Program at Lawrence Livermore National Laboratory is responsible for the development of the waste package design to meet the Nuclear Regulatory Commission licensing requirements for the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. The metallic container component of the waste package is required to assist in providing substantially complete containment of the waste for a period of up to 1000 years. Long term phase stability of the austenitic candidate materials (304L and 316L stainless steels and alloy 825) over this time period at moderate temperatures (100-250 0 C) can impact the mechanical and corrosion behavior of the metal barrier. A review of the technical literature with respect to phase stability of 304L, 316L and 825 is presented. The impact of martensitic transformations, carbide precipitation and intermediate (σ, chi, and eta) phase formation on the mechanical properties and corrosion behavior of these alloys at repository relevant conditions is discussed. The effect of sensitization on intergranular stress corrosion cracking (IGSCC) of each alloy is also addressed. A summary of the impact of phase stability on the degradation of each alloy in the proposed repository environment is included. 32 refs., 6 figs

  13. Crisis Stability and Nuclear Exchange Risks on the Subcontinent: Major Trends and the Iran Factor

    Science.gov (United States)

    2013-11-01

    justification to go nuclear. They have an international ob- ligation. They have signed [the Nuclear Nonproliferation Treaty] and they should respect that.”69...plutonium reactor to increase Pakistan’s inventory of nuclear weapons, the 32 Strategic Perspectives, No. 14 imposition of a veto on negotiations for a...explanation of Iran’s nuclear program is found in the observation of Mark Fitzpatrick, International Institute for Strategic Studies Nonproliferation and

  14. Analysis of the stability of underground high-level nuclear waste repository in discontinuous rock mass using 3DEC

    International Nuclear Information System (INIS)

    Kwon, Sang Ki; Park, Jeong Hwa; Choi, Jong Won; Kang, Chul Hyung

    2001-03-01

    For the safe design of a high-level nuclear waste repository in deep location, it is necessary to confirm the stability of the underground excavations under the high overburden pressure and also to investigate the influence of discontinuities such as fault, fracture zone, and joints. In this study, computer simulations using 3DEC, which is a Distince Element (DEM) code, were carried out for determining important parameters on the stability of the disposal tunnel and deposition holes excavated in 500 m deep granite body. The development of plastic zone and stress and strain distributions were analyzed with various modelling conditions with variation on the parameters including joint numbers, tunnel size, joint properties, rock properties, and stress ratio. Furthermore, the influence of fracture zone, which is located around the underground excavations, on the stability of the excavation was investigated. In this study, the variation of stress and strain distribution due to the variation of fracture zone location, dip, and width was analyzed

  15. Development and manufacturing of special fission chambers for in-core measurement requirements in nuclear reactors

    International Nuclear Information System (INIS)

    Geslot, B.; Berhouet, F.; Oriol, L.; Breaud, S.; Jammes, C.; Filliatre, P.; Villard, J. F.

    2009-01-01

    The Dosimetry Command control and Instrumentation Laboratory (LDCI) at CEA/Cadarache is specialized in the development, design and manufacturing of miniature fission chambers (from 8 mm down to 1.5 mm in diameter). The LDCI fission chambers workshop specificity is its capacity to manufacture and distribute special fission chambers with fissile deposits other than U 235 (typically Pu 242 , Np 237 , U 238 , Th 232 ). We are also able to define the characteristics of the detector for any in-core measurement requirements: sensor geometry, fissile deposit material and mass, filling gas composition and pressure, operating mode (pulse, current or Campbelling) with associated cable and electronics. The fission chamber design relies on numerical simulation and modeling tools developed by the LDCI. One of our present activities in fission chamber applications is to develop a fast neutron flux instrumentation using Campbelling mode dedicated to measurements in material testing reactors. (authors)

  16. Development and manufacturing of special fission chambers for in-core measurement requirements in nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Geslot, B.; Berhouet, F.; Oriol, L.; Breaud, S.; Jammes, C.; Filliatre, P.; Villard, J. F. [CEA, DEN, Dosimetry Command Control and Instrumentation Laboratory, F-13109 Saint-Paul-lez-Durance (France)

    2009-07-01

    The Dosimetry Command control and Instrumentation Laboratory (LDCI) at CEA/Cadarache is specialized in the development, design and manufacturing of miniature fission chambers (from 8 mm down to 1.5 mm in diameter). The LDCI fission chambers workshop specificity is its capacity to manufacture and distribute special fission chambers with fissile deposits other than U{sup 235} (typically Pu{sup 242}, Np{sup 237}, U{sup 238}, Th{sup 232}). We are also able to define the characteristics of the detector for any in-core measurement requirements: sensor geometry, fissile deposit material and mass, filling gas composition and pressure, operating mode (pulse, current or Campbelling) with associated cable and electronics. The fission chamber design relies on numerical simulation and modeling tools developed by the LDCI. One of our present activities in fission chamber applications is to develop a fast neutron flux instrumentation using Campbelling mode dedicated to measurements in material testing reactors. (authors)

  17. Radiotherapy and Nuclear Medicine Project for an Integral Oncology Center at the Oaxaca High Specialization Regional Hospital

    International Nuclear Information System (INIS)

    De Jesus, M.; Trujillo-Zamudio, F. E.

    2010-01-01

    A building project of Radiotherapy and Nuclear Medicine services (diagnostic and therapy), within an Integral Oncology Center (IOC), requires interdisciplinary participation of architects, biomedical engineers, radiation oncologists and medical physicists. This report focus on the medical physicist role in designing, building and commissioning stages, for the final clinical use of an IOC at the Oaxaca High Specialization Regional Hospital (HRAEO). As a first step, during design stage, the medical physicist participates in discussions about radiation safety and regulatory requirements for the National Regulatory Agency (called CNSNS in Mexico). Medical physicists propose solutions to clinical needs and take decisions about installing medical equipment, in order to fulfill technical and medical requirements. As a second step, during the construction stage, medical physicists keep an eye on building materials and structural specifications. Meanwhile, regulatory documentation must be sent to CNSNS. This documentation compiles information about medical equipment, radioactivity facility, radiation workers and nuclear material data, in order to obtain the license for the linear accelerator, brachytherapy and nuclear medicine facilities. As a final step, after equipment installation, the commissioning stage takes place. As the conclusion, we show that medical physicists are essentials in order to fulfill with Mexican regulatory requirements in medical facilities.

  18. A modified index for monitoring of radiation protection programmes with special reference to Nuclear Medicine Institute

    International Nuclear Information System (INIS)

    Gupta, M.M.; Nagaratnam, A.

    1988-01-01

    In India, the Institute of Nuclear Medicine and Allied Sciences was established with the main objective of developing radioisotopic methodologies for diagnosis, therapy, biomedical research and training. The steady progress in India's atomic energy program gave impetus to rapid growth in the application of nuclear medicine techniques at the Institute and now it is one of the largest users of unsealed radiation sources in the country. Right from the beginning adequate attention has been devoted to the radiation safety of the staff and personnel management techniques have been successfully employed to assess performance of the radiation protection staff. A significant positive correlation (p 0.02) between performance and job satisfaction of radiation protection personnel of the Institute has been demonstrated. Efforts are also directed to evolve a parameter that may throw light on the effectiveness of radiation protection staff and subsequently that may be helpful to monitor the radiation protection program of other establishments

  19. Summary Report of a Specialized Workshop on Nuclear Structure and Decay Data (NSDD) Evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Nichols, Alan L. [Univ. of Surrey, Guildford (United Kingdom); Dimitrious, P. [IAEA Nuclear Data Section, Vienna (Austria); Kondev, F. G. [Argonne National Lab. (ANL), Argonne, IL (United States); Ricard-McCutchan, E. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2015-04-27

    A three-day specialised workshop on Nuclear Structure and Decay Data Evaluations was organised and held at the headquarters of the International Atomic Energy Agency in Vienna, Austria, from 27 to 29 April 2015. This workshop covered a wide range of important topics and issues addressed when evaluating and maintaining the Evaluated Nuclear Structure Data File (ENSDF). The primary aim was to improve evaluators’ abilities to identify and understand the most appropriate evaluation processes to adopt in the formulation of individual ENSDF data sets. Participants assessed and reviewed existing policies, procedures and codes, and round-table discussions included the debate and resolution of specific difficulties experienced by ENSDF evaluators (i.e., all workshop participants). The contents of this report constitute a record of this workshop, based on the presentations and subsequent discussions.

  20. Summary Report of a Specialized Workshop on Nuclear Structure and Decay Data (NSDD) Evaluations

    International Nuclear Information System (INIS)

    Nichols, Alan L.; Dimitrious, P.; Kondev, F. G.; Ricard-McCutchan, E.

    2015-01-01

    A three-day specialised workshop on Nuclear Structure and Decay Data Evaluations was organised and held at the headquarters of the International Atomic Energy Agency in Vienna, Austria, from 27 to 29 April 2015. This workshop covered a wide range of important topics and issues addressed when evaluating and maintaining the Evaluated Nuclear Structure Data File (ENSDF). The primary aim was to improve evaluators' abilities to identify and understand the most appropriate evaluation processes to adopt in the formulation of individual ENSDF data sets. Participants assessed and reviewed existing policies, procedures and codes, and round-table discussions included the debate and resolution of specific difficulties experienced by ENSDF evaluators (i.e., all workshop participants). The contents of this report constitute a record of this workshop, based on the presentations and subsequent discussions.

  1. Report by a special panel of the American Nuclear Society: Protection and management of plutonium

    International Nuclear Information System (INIS)

    Bengelsdorf, H.

    1996-01-01

    The American Nuclear Society (ANS) established an independent and prestigious panel several months ago to take the matter up where the US National Academy of Science (NAS) left off. The challenge was to look at the broader issue of what to do with civil plutonium, as well as excess weapons material. In terms of approach, the report focused on several short- and long-term issues. The short-term focus was on the disposition of excess weapons plutonium, while the longer-range issue concerned the disposition of the plutonium being produced in the civil nuclear fuel cycle. For the short term, the ANS panel strongly endorsed the concept that all plutonium scheduled for release from the US and Russian weapons stocks should be converted to a form that is intensively radioactive in order to protect the plutonium from theft of seizure (the spent fuel standard). However, since the conversion will at best take several years to complete, the panel has concluded that immediate emphasis should be placed on the assurance that all unconverted materials are protected as securely as when they were part of the active weapon stockpiles. More importantly, the panel also recommended prompt implementation of the so-called reactor option for disposing of surplus US and Russian weapons plutonium. The longer-term issues covered by the panel were those posed by the growing stocks of both separated plutonium and spent fuel generated in the world's civil nuclear power programs. These issues included what fuel cycle policies should be prudently pursued in light of proliferation risks and likely future energy needs, what steps should be taken in regard to the increase in the demand for nuclear power in the future, and how civil plutonium in its various forms should be protected and managed to minimize proliferation. Overall, the panel concluded that plutonium is an energy resource that should be used and not a waste material to be disposed of

  2. Separation and study of nuclides far from beta stability and search for new regimes of nuclear stability

    International Nuclear Information System (INIS)

    Skarestad, M.

    1977-01-01

    In radiochemical separations progress has been made in developing both discontinuous and continuous separation techniques. Outstanding examples of fast, discontinuous separations have been reported from the University of Mainz where chemical separations are performed on a subsecond time scale. However, when experiments have to be performed repeatedly, a continuous separation process delivering a steady source of short-lived species is more appropriate. Such separations are accomplished in the on-line operating solvent extraction system SISAK. The combination of this separation technique with a Gas Jet Recoil Transport (GJRT) system makes it possible to adapt the separation system to different irradiation facilities. The performance of SISAK has been illustrated through the study of short-lived rare-earth isotopes, using conventional gamma-ray spectroscopy. Following some initial test experiments at a 14 MeV neutron generator in Gothenburg the SISAK system was installed at a Philips PW 5320 neutron generator situated in the Dept. of Nuclear Chemistry, Univ. of Oslo in 1972. In the following two years the main effort was devoted to the development of the experimental separation technique although some physics results were obtained in this period. In 1974 the SISAK system was combined with a GJRT arrangement and installed at the Mainz TRIGA reactor. (JIW)

  3. Nuclear Waste Separation and Transmutation Research with Special Focus on Russian Transmutation Projects Sponsored by ISTC

    International Nuclear Information System (INIS)

    Conde, Henri; Blomgren, Jan; Olsson, Nils

    2003-03-01

    High-level nuclear reactor waste is made up of relatively few long-lived radioactive species, among them plutonium, that contribute to difficulties with its storage and disposal. Separation of these species from larger waste volumes mainly constituting of uranium (about 95 %) coupled with nuclear incineration to fission products of plutonium and the so called minor actinides (Neptunium, Americium, and Curium) and transmutation of some of the long lived fission products to short lived or stable isotopes represents a viable nuclear waste management strategy to drastically reduce the time and space requirements for a bed-rock repository of the remaining waste. A remarkable increase in the international research and development on partitioning and transmutation has occurred during the recent years. The road-map report published in April 2001 by The European Technical Working Group on ADS for the development of a European demonstration facility for nuclear waste transmutation has high-lighted the ongoing European research and pointed out the need for further research. The road-map has given the different research activities a position in the ultimate goal of producing an ADS demonstrator and is guiding research planning on the national as well as on the EU level. The Advanced Accelerator Application (3A) program in the US, with the long term goals to enhance long term public safety, provide benefits for the repository, reduce proliferation risks and improve prospects for nuclear power has focused the research on nuclear waste transmutation. The reports on the 3A program indicates a change of the US former abandonment position towards reprocessing and fast reactors due to a strong incentive to eliminate the reactor plutonium and to lower the amount of high level reactor waste for the Yucca Mountain repository. The SKB's proposed research and development program for the next 3 years (FUD01) was presented by SKB in September 2001. It is proposed that the research program

  4. Nuclear safety. Summary of the intermediate report of the special joint parliamentary committee on nuclear safety, present and future outlook of the nuclear industry

    International Nuclear Information System (INIS)

    Birraux, Claude; Bataille, Christian; Sido, Bruno

    2011-09-01

    Following the Fukushima events, the Parliamentary Office for Scientific and Technological Assessment (OPECST) was officially asked at the end of March 2011 - jointly by the National Assembly Bureau and by the Senate Committee on the economy, sustainable development, territorial and regional planning - to carry out a study on nuclear safety, and the present and future outlook of the nuclear industry. To carry out this study, seven members of the National Assembly economic affairs and sustainable development committees were also involved, as well as eight members of the Senate Committee on the economy, sustainable development, territorial and regional planning. The first part of this study, devoted to nuclear safety, was completed on 30 June 2011 by the publication of an intermediate report. This report assembles and summarises the information collected during six public hearings and seven trips to nuclear sites. France is one of the nuclear countries where the management of safety is both the most demanding and the most transparent. In this respect, the independence of the Safety Authority is the best guarantee of strictness in the safety field and the existence of pluralistic bodies, such as the Local Information Committees, is the best guarantee of the transparency of safety. But no country can pride itself on being totally safe from a natural disaster of an unexpected scale. The French nuclear industry must therefore ratchet up one more notch its investment in safety and strengthen the means of university research. It must imagine events of even greater intensity, cascading accidents, with interactions between neighbouring industrial sites. Investment must be made by placing safety requirements above any economic consideration and in strict compliance with the specifications of public authorities supervising safety. (authors)

  5. The transport of radioactive materials, paying special attention to nuclear fuels

    International Nuclear Information System (INIS)

    Blechschmidt, M.

    1977-06-01

    The transport of radioactive materials, particularly within the nuclear fuel cycle, is of increasing importance, and is more than ever a matter of public debate. This report provides information concerning the necessary physical, technical and administrative precautions which must be taken to ensure protection of the environment. The international standard of requirements for the packing of the materials is emphasized, as in many cases, transports cross national borders. The relatively comprehensive list of references can be used for the study of details. (orig.) [de

  6. Status of commercial nuclear high-level waste disposal. Special report

    International Nuclear Information System (INIS)

    Dau, G.J.; Williams, R.F.

    1976-09-01

    The results of this review, presented in the form of a functional description of high level waste management system, shows that technology is available to dispose of nuclear waste safely by several different processes. The most attractive alternative in terms of available technology and shortness of time to demonstrate it at commercial scale is a system that converts the waste to a solid by immobilizing the radioactive elements in a glass matrix. Brief comments are also given on international efforts in high level waste management and advanced disposal concepts

  7. ONE YEAR'S EXPERIENCE IN REGULATING BYPRODUCT, SOURCE, AND SPECIAL NUCLEAR MATERIAL IN THE COMMONWEALTH OF KENTUCKY

    Energy Technology Data Exchange (ETDEWEB)

    Weaver, C L

    1963-06-15

    On March 26, 1962, Kentucky assumed regulatory control for the licensing of subcritical nuclear materials within its boundaries. The administration of the state radiological health program is described, and the manpower, fiscal, and equipment requirements are outlined. The licensing activity of the state is also described. Results are reported of preliminary studies of state-owned land for low-level radioactive waste disposal. The procedures for inspection of licensees are described. Proposed changes in the Radiological Health regulations of Kentucky in order to bring about compatibility with AEC's code of Federal Regulations are outlined. (D.L.C.)

  8. Savannah River Site's H-Canyon Facility: Impacts of Foreign Obligations on Special Nuclear Material Disposition

    International Nuclear Information System (INIS)

    Magoulas, Virginia

    2013-01-01

    The US has a non-proliferation policy to receive foreign and domestic research reactor returns of spent fuel materials of US origin. These spent fuel materials are returned to the Department of Energy (DOE) and placed in storage in the L-area spent fuel basin at the Savannah River Site (SRS). The foreign research reactor returns fall subject to the 123 agreements for peaceful cooperation. These ''123 agreements'' are named after section 123 of the Atomic Energy Act of 1954 and govern the conditions of nuclear cooperation with foreign partners. The SRS management of these foreign obligations while planning material disposition paths can be a challenge.

  9. Development of database for spent fuel and special waste from the Spanish nuclear power plants

    International Nuclear Information System (INIS)

    Gonzalez Gandal, R.; Rodriguez Gomez, M. A.; Serrano, G.; Lopez Alvarez, G.

    2013-01-01

    GNF Engineering is developing together with ENRESA and with the UNESA participation, the spent fuel and high activity radioactive waste data base of Spanish nuclear power plants. In the article is detailed how this strategic project essential to carry out the CTS (centralized temporary storage) future management and other project which could be emerged is being dealing with, This data base will serve as mechanics of relationship between ENRESA and Spanish NPPS, covering the expected necessary information to deal with mentioned future management of spent fuel and high activity radioactive waste. (Author)

  10. Perspective for special Gurdon issue for differentiation: can cell fusion inform nuclear reprogramming?

    Science.gov (United States)

    Burns, David; Blau, Helen M

    2014-07-01

    Nuclear reprogramming was first shown to be possible by Sir John Gurdon over a half century ago. The process has been revolutionized by the production of induced pluripotent cells by overexpression of the four transcription factors discovered by Shinya Yamanaka, which now enables mammalian applications. Yet, reprogramming by a few transcription factors remains incomplete and inefficient, whether to pluripotent or differentiated cells. We propose that a better understanding of mechanistic insights based on developmental principles gained from heterokaryon studies may inform the process of directing cell fate, fundamentally and clinically. Copyright © 2014 International Society of Differentiation. Published by Elsevier B.V. All rights reserved.

  11. Standard format and content of a licensee physical protection plan for strategic special nuclear material in transit - April 1980

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    A predetermined plan to respond to safeguards contingency events is required to be prepared, based on personnel and other physical protection resources described in the Physical Protection Plan for strategic special nuclear material (SSNM) in transit. Specific requirements for the contingency plan are provided in Appendix C. Licensee Safeguards Contingency Plans, to 10 CFR Part 73. Regulatory Guide 5.56, Standard Format and Content of Safeguards Contingency Plans for Transportation, provides guidance for the preparation of transportation contingency plans. Licensee is reminded that all three submissions - the Physical Protection Plan, the Physical Protection Arrangements for Specific Shipments, and the Safeguards Contingency Plan - together describe the system for physical protection of each particular shipment. They should be developed and maintained to be completely consistent with each other for each shipment

  12. Fiscal Drag as an Automatic Stability Tool, in the Case of New Regulation with Price Criteria in Automotive Sectors Special Consumption Tax (SCT

    Directory of Open Access Journals (Sweden)

    Abdurrahman TARAKTAŞ

    2017-12-01

    Full Text Available Fiscal drag is a result of real or nominal expanding economy and progressive taxation. In general, individuals are forced to enter the upper tax bracket depending on their increased income or expenditure. More tax burden can result in less consumption. Fiscal drag, lack of spending or excessive taxation can cause the economy to slow down. Traditional view suggests that fiscal drag may serve as a natural automatic stabilizer to cool the economy. However, this view ignores the supply side and in particular the potential effects of the high tax burden on economy. This study examines the extent to which the expected automatic stabilization function can be performed and the possible side effects on economic balances and income distribution of fiscal drag in our country in the case of new regulation with price criteria in automotive sectors Special Consumption Tax (SCT.

  13. The Study on the analysis of the revised regulation on the special nuclear materials

    International Nuclear Information System (INIS)

    Ahn, Seung Ho; Koh, Byung Marn; Kim, Ki Hyun

    2015-01-01

    In accordance with successful implementation of the IS in the ROK, the IAEA request the enhanced partnership between the ROK and the IAEA to increase the role of the SSAC(State System of Accounting for and Control of nuclear material) in the ROK. For this reason, the ROK and the IAEA signed the EC(Enhanced Cooperation) arrangement to expand the cooperation area beyond existing LWR enhanced cooperation. The IAEA set up it the one of the EC's objectives to increase the practical use and enhancement of the SSAC. In 2013, the NSSC(Nuclear Safety and Security Committee) formed task force team which included the TSO(Technical Support Organization) staffs and operators to establish scope, object and role of the SSAC for improving it. The improvement of the state safeguards system envisioned in the amendment to the notification is intended to ensure the integrity of the state safeguards with the agreement reached with the IAEA to enhance cooperation, enable facility operators to ensure compliance with their obligatory requirements without assuming unnecessarily duplicate administrative workload, and eliminate unreasonableness of the state accounting and control inspection

  14. The Study on the analysis of the revised regulation on the special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, Seung Ho; Koh, Byung Marn; Kim, Ki Hyun [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

    2015-05-15

    In accordance with successful implementation of the IS in the ROK, the IAEA request the enhanced partnership between the ROK and the IAEA to increase the role of the SSAC(State System of Accounting for and Control of nuclear material) in the ROK. For this reason, the ROK and the IAEA signed the EC(Enhanced Cooperation) arrangement to expand the cooperation area beyond existing LWR enhanced cooperation. The IAEA set up it the one of the EC's objectives to increase the practical use and enhancement of the SSAC. In 2013, the NSSC(Nuclear Safety and Security Committee) formed task force team which included the TSO(Technical Support Organization) staffs and operators to establish scope, object and role of the SSAC for improving it. The improvement of the state safeguards system envisioned in the amendment to the notification is intended to ensure the integrity of the state safeguards with the agreement reached with the IAEA to enhance cooperation, enable facility operators to ensure compliance with their obligatory requirements without assuming unnecessarily duplicate administrative workload, and eliminate unreasonableness of the state accounting and control inspection.

  15. Nuclear data libraries for gamma analysis programs, including special purpose libraries

    International Nuclear Information System (INIS)

    Westmeier, W.; Reus, U.; Siemon, K.; Westmeier, H.

    2002-01-01

    A complete set of gamma ray and other data relating to the decay of all known nuclides has been compiled from the literature and electronic sources. The data were critically reviewed, evaluated and the consistency was checked. The total catalogue is comprised of data-sets for 3841 nuclides and isomers with 106,355 gamma ray and 19,347 X ray entries. A subset of 1,627 nuclides with 32,456 gamma ray entries is extracted into a database, which provides the basis for the generation of nuclide libraries for the application in spectrometry programmes. The WINDOWS based program NUC M AN was developed which serves for the updating and editing of the database as well as the generation of task-specific user libraries for special purposes. The literature cut-off date for this catalogue is January 1, 1998. (author)

  16. Special radiation protection aspects of radiotherapy and nuclear medicine in a medium-sized Swiss hospital

    International Nuclear Information System (INIS)

    Benes, I.; Heinzel, F.; Mueller-Duysing, W.

    1985-01-01

    The evolution of radiation protection in Switzerland caused the Triemli City Hospital to implement building modifications throughout its 13 years of existence which have not been completed todate. However, modest methods allowed to find practicable solutions which largely comply with today's radiation protection regulation. Radiation protection provisions have been rendered more stringent thus resulting in more jobs. At least one additional staff member is required in order to discharge all supervisory functions required like incorporation controls, controls of cleaning and technical staff for their working correctly, contamination controls of floors and working areas, exit controls of special working clothes, etc. The best solution for the hospital would be to have one health physics man specifically commissioned with and employed for radiation protection. (orig./HSCH) [de

  17. Analysis of linear stability in nuclear systems associated to two-phase fluid flow and in thermodynamic balance

    International Nuclear Information System (INIS)

    Galvao, O.B.; Amorim, E.S. do; D'Oliveira, A.B.

    1981-03-01

    Under special conditions a water-cooled reactor or other multiphase process can be subject to instabilities as the so called density-wave oscillations phenomenon. The purpose of this investigation is to derive the stability limits of a boiling channel for the dynamic response to an inlet velocity perturbation. The solution scheme allowed a coupling for the single and two-phase regions together with a model for the dynamic thermal response of the heated surface. The frequency response of a rational transfer function is obtained and a Nyquist plot is used for stability analysis. The model is, although simplified, quite capable of predicting the threshold for self-excited system or the trends given by more exact solution. (Author) [pt

  18. Project Plan For Remove Special Nuclear Material (SNM) from Plutonium Finishing Plant (PFP) Project

    International Nuclear Information System (INIS)

    BARTLETT, W.D.

    1999-01-01

    This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove SNM Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617. This project plan is the top-level definitive project management document for the PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baseline to manage the execution of the Remove SNM Materials project. Any deviation to the document must be authorized through the appropriate change control process. The Remove SNM Materials project provides the necessary support and controls required for DOE-HQ, DOE-RL, BWHC, and other DOE Complex Contractors the path forward to negotiate shipped/receiver agreements, schedule shipments, and transfer material out of PFP to enable final deactivation

  19. Nondestructive Inspection System for Special Nuclear Material Using Inertial Electrostatic Confinement Fusion Neutrons and Laser Compton Scattering Gamma-Rays

    Science.gov (United States)

    Ohgaki, H.; Daito, I.; Zen, H.; Kii, T.; Masuda, K.; Misawa, T.; Hajima, R.; Hayakawa, T.; Shizuma, T.; Kando, M.; Fujimoto, S.

    2017-07-01

    A Neutron/Gamma-ray combined inspection system for hidden special nuclear materials (SNMs) in cargo containers has been developed under a program of Japan Science and Technology Agency in Japan. This inspection system consists of an active neutron-detection system for fast screening and a laser Compton backscattering gamma-ray source in coupling with nuclear resonance fluorescence (NRF) method for precise inspection. The inertial electrostatic confinement fusion device has been adopted as a neutron source and two neutron-detection methods, delayed neutron noise analysis method and high-energy neutron-detection method, have been developed to realize the fast screening system. The prototype system has been constructed and tested in the Reactor Research Institute, Kyoto University. For the generation of the laser Compton backscattering gamma-ray beam, a race track microtron accelerator has been used to reduce the size of the system. For the NRF measurement, an array of LaBr3(Ce) scintillation detectors has been adopted to realize a low-cost detection system. The prototype of the gamma-ray system has been demonstrated in the Kansai Photon Science Institute, National Institutes for Quantum and Radiological Science and Technology. By using numerical simulations based on the data taken from these prototype systems and the inspection-flow, the system designed by this program can detect 1 kg of highly enriched 235U (HEU) hidden in an empty 20-ft container within several minutes.

  20. Study of the prompt gamma ray signal from fissions in special nuclear materials induced using an associated particle neutron generator

    International Nuclear Information System (INIS)

    Koltick, D. S.; Kane, S. Z.

    2009-01-01

    More than 42 million cargo containers entered the United States in 2005. To search for a few kilograms of special nuclear material (SNM) within this vast stream of cargo, an inspection system based on neutron-induced fission followed by the coincident detection of multiple prompt fission gamma rays is investigated using MCNP-Polimi code. The system utilizes two deuterium-tritium (DT) associated particle neutron generators, each capable of 10 9 neutrons/s at 14.1 MeV, with sub-nanosecond timing resolution ZnO:Ga alpha detectors internal to the generator. Because prompt fission signals are approximately 100 times stronger than the delayed signals, the neutron flux is greatly reduced compared to 10 11-12 neutrons/s required for systems based on delayed signals such as the 'nuclear car wash' [4]. In addition the system utilizes 30 cm deep liquid krypton (LKr) noble gas detectors having 94% detection efficiency for 1 MeV gamma rays, high solid angle coverage (∼ 50% of the total solid angle), and sub-nanosecond timing resolution (∼ 600 ps). An algorithm for distinguishing U-235 from U-238 is presented. (authors)

  1. Attachment Stability in Children Aged 6 to 9 Years in Extended and Nuclear Families

    Science.gov (United States)

    Seven, Serdal; Ogelman, Hulya Gulay

    2012-01-01

    Research Findings: The main aim of this study was to identify whether the attachment security of children living in nuclear and extended families is stable from ages 6 to 9 years in a sample of Turkish children. In total, 54 children participated in the study, of whom 27 lived in nuclear families and the other 27 lived in extended families in Mus…

  2. Steel, specially for the fabrication of welded structure working under pressure in nuclear installations

    International Nuclear Information System (INIS)

    Dolbenko, E.T.; Astafiev, A.A.; Kark, G.S.

    1981-01-01

    The present invention is in the field of metallurgy. Steels have found an increasing number of applications in mechanical constructions, and notably in the construction of materials for the production of energy and for the fabrication of welded structures operating under pressure at temperatures as high as 450 0 C. A possible application is the pressurized vessels of nuclear facilities. The steels of interest contain carbon, silicon, manganese, nickel, molybdenum, vanadium, aluminium, nitrogen, phosphorus and iron, but are characterized by the fact that they also contain arsenic, tin and calcium. The sum of the weighted percentages of nickel and manganese and the weighted percentage of phosphorous are related as follows: (Ni + Mn) . P [fr

  3. Discussion on two special stainless steels used in nuclear fuel processing plants

    International Nuclear Information System (INIS)

    Desestret, A.; Ferriol, J.; Vallier, G.

    1977-01-01

    Nuclear fuel treatment may entail difficult corrosion problems for the metallurgist. A first case occurs when the nitric solution is concentrated (60 to 70% of HNO 3 ) at temperatures of 130 0 C. This is solved by use of a steel having a very high chromium content (25%), a high nickel content (20%), and a very low carbon content, which is now readily produced on an industrial scale. A second case happens when nitric solutions are made highly agressive, even when diluted at medium temperatures, by highly oxidising ions such as chromate or ceric ions. The stainless steel is then placed in transpassive conditions and subject to very rapid intergranular attack, even when free from precipitated chromium carbides. A steel of the Cr 17 / Ni 14 / Si 4 / C [fr

  4. High-fidelity MCNP modeling of a D-T neutron generator for active interrogation of special nuclear material

    International Nuclear Information System (INIS)

    Katalenich, Jeff; Flaska, Marek; Pozzi, Sara A.; Hartman, Michael R.

    2011-01-01

    Fast and robust methods for interrogation of special nuclear material (SNM) are of interest to many agencies and institutions in the United States. It is well known that passive interrogation methods are typically sufficient for plutonium identification because of a relatively high neutron production rate from 240 Pu . On the other hand, identification of shielded uranium requires active methods using neutron or photon sources . Deuterium-deuterium (2.45 MeV) and deuterium-tritium (14.1 MeV) neutron-generator sources have been previously tested and proven to be relatively reliable instruments for active interrogation of nuclear materials . In addition, the newest generators of this type are small enough for applications requiring portable interrogation systems. Active interrogation techniques using high-energy neutrons are being investigated as a method to detect hidden SNM in shielded containers . Due to the thickness of some containers, penetrating radiation such as high-energy neutrons can provide a potential means of probing shielded SNM. In an effort to develop the capability to assess the signal seen from various forms of shielded nuclear materials, University of Michigan Neutron Science Laboratory's D-T neutron generator and its shielding were accurately modeled in MCNP. The generator, while operating at nominal power, produces approximately 1x10 10 neutrons/s, a source intensity which requires a large amount of shielding to minimize the dose rates around the generator. For this reason, the existing shielding completely encompasses the generator and does not include beam ports. Therefore, several MCNP simulations were performed to estimate the yield of uncollided 14.1-MeV neutrons from the generator for active interrogation experiments. Beam port diameters of 5, 10, 15, 20, and 25 cm were modeled to assess the resulting neutron fluxes. The neutron flux outside the beam ports was estimated to be approximately 2x10 4 n/cm 2 s.

  5. Application of tearing modulus stability concepts to nuclear piping. Final report

    International Nuclear Information System (INIS)

    Cotter, K.H.; Chang, H.Y.; Zahoor, A.

    1982-02-01

    The recently developed tearing modulus stability concept was successfully applied to several boiling water reactor (BWR) and pressurized water reactor (PWR) piping systems. Circumferentially oriented through-the-thickness cracks were postulated at numerous locations in each system. For each location, the simplified tearing stability methods developed in USNRC Report NUREG/CR-0838 were used to determine crack stability. The J-T diagram was used to present the results of the computations. The piping systems considered included Type 304 stainless steel as well as A106 carbon steel materials. These systems were analyzed using the piping analysis computer code MINK

  6. Application of tearing modulus stability concepts to nuclear piping. Final report. [PWR; BWR

    Energy Technology Data Exchange (ETDEWEB)

    Cotter, K.H.; Chang, H.Y.; Zahoor, A.

    1982-02-01

    The recently developed tearing modulus stability concept was successfully applied to several boiling water reactor (BWR) and pressurized water reactor (PWR) piping systems. Circumferentially oriented through-the-thickness cracks were postulated at numerous locations in each system. For each location, the simplified tearing stability methods developed in USNRC Report NUREG/CR-0838 were used to determine crack stability. The J-T diagram was used to present the results of the computations. The piping systems considered included Type 304 stainless steel as well as A106 carbon steel materials. These systems were analyzed using the piping analysis computer code MINK.

  7. Development of a re-brazeable containment system for special nuclear material storage and transport

    International Nuclear Information System (INIS)

    Pierce, J.D.; Stephens, J.J.; Walker, C.A.; Hosking, F.M.; Curlee, R.M.

    1995-01-01

    This report describes a novel means of closing and sealing small type B radioactive material transport packages for surface or air transport as governed by 10CFR71 or NUREG-0360 has been developed at Sandia National Laboratories (SNL). This method is a controlled brazing process that may be used to attach and seal a closure lid to a containment vessel and then remove it at a later time. The process may be performed multiple times without the need for special preparations of the braze joint. A number of advantages for utilization of this technique have been determined. A brazed seal has integrity at high temperatures for better protection in accident or abnormal environments. A properly designed joint has essentially the same strength as the parent metal. A closure that is brazed, therefore, will no longer be the anticipated point of failure for a broad range of accident environments. This technique will allow the containment vessel design to be optimized with a lighter, more uniform wall thickness throughout. Finally, with a well defined process for sealing, mechanical inspection, leak testing, and then reopening at a later time, automation of the process is relatively straightforward and the overall system should be as easy to use as one that utilizes elastomeric seals for containment

  8. Nuclear shape coexistence and the study of nuclei far from stability

    International Nuclear Information System (INIS)

    Wood, J.L.

    1987-01-01

    The systematic features of shape coexistence are briefly outlined. The most useful spectroscopic fingerprints for identifying shape coexistence far from stability are presented. Directions for future work are discussed

  9. Evaluation of the geologic relations and seismotectonic stability of the Yucca Mountain area, Nevada Nuclear Waste Site Investigation (NNWSI)

    International Nuclear Information System (INIS)

    1988-10-01

    This report provides a summary of progress for the project ''Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI)'' for the eighteen month period of January 1, 1987 to June 10, 1988. This final report was preceded by the final report for the initial six month period, July 1, 1986 to December 31, 1986 (submitted on January 25, 1987, and revised in June 1987.) Quaternary Tectonics, Geochemical, Mineral Deposits, Vulcanic Geology, Seismology, Tectonics, Neotectonics, Remote Sensing, Geotechnical Assessments, Geotechnical Rock Mass Assessments, Basinal Studies, and Strong Ground Motion

  10. Evaluation of the geologic relations and seismotectonic stability of the Yucca Mountain Area Nevada Nuclear Waste Site Investigation (NNWSI)

    International Nuclear Information System (INIS)

    1995-01-01

    This report provides a summary of progress for the project open-quotes Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI).close quotes A similar report was previously provided for the period of 1 October 1993 to 30 September 1994. The report initially covers the activities of the General Task and is followed by sections that describe the progress of the other ongoing Tasks which are listed below. Task 1: Quaternary Tectonics Task 3: Mineral Deposits, Volcanic Geology Task 4: Seismology Task 5: Tectonics Task 8: Basinal Studies

  11. A note on the assay of special nuclear materials in solution by x-ray fluorescence

    International Nuclear Information System (INIS)

    Canada, T.R.; Hsue, S.T.

    1982-01-01

    Presents a formulation that allows empirical results of the ''internal standard'' approach to be understood in a quantifiable manner, and suggests an alternative measurement procedure that removes many of the technique's undesirable features while maintaining those that add to instrumental accuracy. Assumes that the reader is familiar with x-ray fluorescence (XRF) technology. Promises a more detailed presentation, including proof-of-principle experimental results, in the future. Points out that practical applications of this approach may be achieved with both K- and L-x-ray fluorescence. Concludes that the formulation and alternative measurement procedure suggested indicates that the ''internal standard'' approach may be improved by making measurements at one or more additional x-ray energies of the element to be assayed. Effects of solution acidity variations and the relative concentrations of plutonium and uranium may be avoided. Because of the inherent stability of ratio techniques, little or no modification to this formulation is anticipated for cylindrical near-field geometries

  12. Decree of the Czechoslovak Atomic Energy Commission No. 191/1989 on procedures, terms and conditions for examining special professional qualification and competence of selected nuclear facility personnel

    International Nuclear Information System (INIS)

    1995-01-01

    The procedures, terms and conditions for examining special professional competence of selected nuclear facility personnel are specified, including conditions for professional training and for issuing licenses qualifying the personnel for their work. Nuclear safety-related jobs at nuclear facilities are listed. Professional licenses with a two-year term of validity are granted by the Czechoslovak Atomic Energy Agency (CSAEC) to candidates who have passed examination before the State Examination Commission. Personnel training may only be performed by bodies authorized for that by the CSAEC. The Decree entered into force on 1 January 1990. (J.B.)

  13. Standard practice for sampling special nuclear materials in multi-container lots

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    1987-01-01

    1.1 This practice provides an aid in designing a sampling and analysis plan for the purpose of minimizing random error in the measurement of the amount of nuclear material in a lot consisting of several containers. The problem addressed is the selection of the number of containers to be sampled, the number of samples to be taken from each sampled container, and the number of aliquot analyses to be performed on each sample. 1.2 This practice provides examples for application as well as the necessary development for understanding the statistics involved. The uniqueness of most situations does not allow presentation of step-by-step procedures for designing sampling plans. It is recommended that a statistician experienced in materials sampling be consulted when developing such plans. 1.3 The values stated in SI units are to be regarded as the standard. 1.4 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standar...

  14. Nondestructive assay of special nuclear material for uranium fuel-fabrication facilities

    International Nuclear Information System (INIS)

    Smith, H.A. Jr.; Schillebeeckx, P.

    1997-01-01

    A high-quality materials accounting system and effective international inspections in uranium fuel-fabrication facilities depend heavily upon accurate nondestructive assay measurements of the facility's nuclear materials. While item accounting can monitor a large portion of the facility inventory (fuel rods, assemblies, storage items), the contents of all such items and mass values for all bulk materials must be based on quantitative measurements. Weight measurements, combined with destructive analysis of process samples, can provide highly accurate quantitative information on well-characterized and uniform product materials. However, to cover the full range of process materials and to provide timely accountancy data on hard-to-measure items and rapid verification of previous measurements, radiation-based nondestructive assay (NDA) techniques play an important role. NDA for uranium fuel fabrication facilities relies on passive gamma spectroscopy for enrichment and U isotope mass values of medium-to-low-density samples and holdup deposits; it relies on active neutron techniques for U-235 mass values of high-density and heterogeneous samples. This paper will describe the basic radiation-based nondestructive assay techniques used to perform these measurements. The authors will also discuss the NDA measurement applications for international inspections of European fuel-fabrication facilities

  15. Increasing the operational safety of nuclear facilities by using special insulation parts in the containment zone

    International Nuclear Information System (INIS)

    Drumm, F.

    2005-01-01

    LOCA (Loss of coolant accident) resistant heat-shrinkable polymeric products are widely used for the connection of LV cables for class 1E systems inside the containment area of nuclear power plants. The paper/presentation describes the verification of a reformulated compound for these products, where certain components of the compound formulation had to be substituted. A qualification programme with this so-called reformulated compound was undertaken to proof the equivalency of the products to the products made out of the original compound. The basic elements of this requalification project were material qualification tests including accelerated aging tests according to the arrhenius method and type tests in accordance to IEEE 383, including flammability tests. The test results showed that the products made out of the reformulated compound were similar in fit, form and function to the original products. Additional tests have also proven higher application ranges for the heat-shrinkable tubings and the successful evaluation of a design for a medium voltage joint design for LOCA resistant application. (author)

  16. Osteoclast cell-surface specializations and nuclear kinetics during egg-laying in Japanese quail

    International Nuclear Information System (INIS)

    Miller, S.C.

    1981-01-01

    Medullary bone deposits serve as a reservoir of labile calcium for egg-shell calcification in birds. Quantitative transmission-electron-microscope methods and light-microscope autoradiographic cell-population-kinetic analyses were used to determine changes in cell-surface specializations and population dynamics of medullary bone osteoclasts during egg-laying in Japanese quail. Prior to egg-shell formation, from 0 to about 8 hours after the previous oviposition, very few osteoclast profiles had ruffled borders. The appearance of ruffled borders coincided with the beginning of egg-shell calcification, about 9-10 hours after the previous oviposition. During egg-shell calcification, about 10-21 hours after the previous oviposition, most osteoclast profiles had ruffled borders. Ruffled borders disappeared at the completion of egg-shell calcification and commencement of egg-shell pigmentation. Thus, functional activities of medullary bone osteoclasts appear to be closely synchronized with egg-shell calcification during egg-laying. From 1 to 48 hours after a single injection of 3H-thymidine (3H-TdR), very few labeled osteoclast nuclei were seen during egg-laying. Following multiple injections of 3H-TdR, the percentage of labeled nuclei reached a peak at about 170 hours after the first injection. At this peak-labeling time, relatively few of the osteoclast profiles that had labeled nuclei had two or more; although the average number of nuclei per osteoclast profile was about 3.6. These kinetic data suggest that the medullary bone osteoclast population has a prolonged rate of turnover compared to rapid changes in cell activities associated with each 24-hour egg-laying cycle; and collectively they would suggest that rapid changes in osteoclast functions occur independently of changes in cell-population dynamics

  17. The Text of Tile Master Agreement between the Agency and the United States of America Governing Sales of Source, By- Product and Special Nuclear Materials for research Purposes

    International Nuclear Information System (INIS)

    1974-01-01

    The text of the Master Agreement Governing Sales of Source, Bye Product and Special Nuclear Materials for Research Purposes, which has been concluded between the Agency and the Government of the United States of America, is reproduced herein for the information of all Members,

  18. Radioactive nuclear waste stabilization - Aspects of solid-state molecular engineering and applied geochemistry

    Science.gov (United States)

    Haggerty, S. E.

    1983-01-01

    Stabilization techniques for the storage of radioactive wastes are surveyed, with emphasis on immobilization in a primary barrier of synthetic rock. The composition, half-life, and thermal-emission characteristics of the wastes are shown to require thermally stable immobilization enduring at least 100,000 years. Glass materials are determined to be incapable of withstanding the expected conditions, average temperatures of 100-500 C for the first 100 years. The geological-time stability of crystalline materials, ceramics or synthetic rocks, is examined in detail by comparing their components with similar naturally occurring minerals, especially those containing the same radioactive elements. The high-temperature environment over the first 100 years is seen as stabilizing, since it can recrystallize radiation-induced metamicts. The synthetic-rock stabilization technique is found to be essentially feasible, and improvements are suggested, including the substitution of nepheline with freudenbergite and priderite for alkaline-waste stabilization, the maintenance of low oxygen fugacity, and the dilution of the synthetic-rock pellets into an inert medium.

  19. Nuclear alpha spectrin: Critical roles in DNA interstrand cross-link repair and genomic stability

    OpenAIRE

    Lambert, Muriel W

    2016-01-01

    Non-erythroid alpha spectrin (?IISp) is a structural protein which we have shown is present in the nucleus of human cells. It interacts with a number of nuclear proteins such as actin, lamin, emerin, chromatin remodeling factors, and DNA repair proteins. ?IISp?s interaction with DNA repair proteins has been extensively studied. We have demonstrated that nuclear ?IISp is critical in DNA interstrand cross-link (ICL) repair in S phase, in both genomic (non-telomeric) and telomeric DNA, and in ma...

  20. Stabilization of high-level waste from a chloride volatility nuclear fuel reprocessing system

    International Nuclear Information System (INIS)

    Smith, L.A.; Thornton, T.A.

    1979-01-01

    Methods for stabilizing high-level waste from a chloride volatility thorium-based fuel coprocessing system have been studied. The waste, which is present as chloride salts, is combined with SiO 2 or Al 2 O 3 and pyrohydrolyzed to remove the chloride ions. The resulting solid is then combined with a flux and glassified. 3 figures, 4 tables

  1. Specially Treated Aramid Fiber Stabilized Gel-Emulsions: Preparation of Porous Polymeric Monoliths and Highly Efficient Removing of Airborne HCHO.

    Science.gov (United States)

    Liu, Jianfei; Chen, Xiangli; Wang, Pei; Fu, Xuwei; Liu, Kaiqiang; Fang, Yu

    2017-08-01

    Porous polymeric monoliths with densities as low as ≈0.060 g cm -3 are prepared in a gel-emulsion template way, of which the stabilizer employed is a newly discovered acidified aramid fiber that is so efficient that 0.05% (w/v, accounts for continuous phase) is enough to gel the system. The porous monoliths as obtained can be dried at ambient conditions, avoiding energy-consuming processes. Importantly, the monoliths show selective adsorption to HCHO, and the corresponding adsorption capacity (M6) is ≈2700 mg g -1 , the best result that is reported until now. More importantly, the monoliths can be reused after drying. © 2017 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  2. NSCL and FRIB at Michigan State University: Nuclear science at the limits of stability

    Science.gov (United States)

    Gade, A.; Sherrill, B. M.

    2016-05-01

    The National Superconducting Cyclotron Laboratory (NSCL) at Michigan State University (MSU) is a scientific user facility that offers beams of rare isotopes at a wide range of energies. This article describes the facility, its capabilities, and some of the experimental devices used to conduct research with rare isotopes. The versatile nuclear science program carried out by researchers at NSCL continues to address the broad challenges of the field, employing sensitive experimental techniques that have been developed and optimized for measurements with rare isotopes produced by in-flight separation. Selected examples showcase the broad program, capabilities, and the relevance for forefront science questions in nuclear physics, addressing, for example, the limits of nuclear existence; the nature of the nuclear force; the origin of the elements in the cosmos; the processes that fuel explosive scenarios in the Universe; and tests for physics beyond the standard model of particle physics. NSCL will cease operations in approximately 2021. The future program will be carried out at the Facility for Rare Isotope Beams, FRIB, presently under construction on the MSU campus adjacent to NSCL. FRIB will provide fast, stopped, and reaccelerated beams of rare isotopes at intensities exceeding NSCL’s capabilities by three orders of magnitude. An outlook will be provided on the enormous opportunities that will arise upon completion of FRIB in the early 2020s.

  3. Gas laser spectrometer for nuclear investigation at nucleonic stability limit. (project)

    International Nuclear Information System (INIS)

    Myshinskij, G.V.

    1989-01-01

    It is proposed to obtain the atomic beam of the proton-rich and neutron-rich nuclides with half-lives of up to 1 ms, by using the gas-jet technique. Subsequently their properties are investigated using the methods of laser resonance ionization and nuclear spectroscopy. 8 refs.; 4 figs

  4. Radiation stability of some sealing materials used in nuclear power plants

    International Nuclear Information System (INIS)

    Lukac, P.; Foeldesova, M.; Dillinger, P.

    1987-01-01

    The radiation stability was investigated of sealing strips by Wonisch, Silhoffer and Dehtochema. Samples of the strips were irradiated with various single doses at a dose rate 5.27 kGy.h -1 . Changes in mechanical properties were studied by measuring tensile strength, ductility, compressibility and resistance against aqueous decontamination solutions. The results of the measurement were compared with values for non-irradiated materials and were expressed in percentage. The experiments showed that the materials were stable within the given region of absorbed radiation doses. The highest stability for a dose of 0.25 MGy was shown by the sealing strip Asfaretan by Dehtochema which in many properties compares well with foreign-made materials and in some respects is even better. Its compressibility is, however, worse. The experimental results have shown that polymerization processes (cross-linking) prevail at doses of up to 0.33 MGy and that material degradation prevails above this level. (author)

  5. Nuclear Energy Research Initiative. Development of a Stabilized Light Water Reactor Fuel Matrix for Extended Burnup

    International Nuclear Information System (INIS)

    BD Hanson; J Abrefah; SC Marschman; SG Prussin

    2000-01-01

    The main objective of this project is to develop an advanced fuel matrix capable of achieving extended burnup while improving safety margins and reliability for present operations. In the course of this project, the authors improve understanding of the mechanism for high burnup structure (HBS) formation and attempt to design a fuel to minimize its formation. The use of soluble dopants in the UO 2 matrix to stabilize the matrix and minimize fuel-side corrosion of the cladding is the main focus

  6. Real-time stability monitoring method for boiling water reactor nuclear power plants

    International Nuclear Information System (INIS)

    Fukunishi, K.; Suzuki, S.

    1987-01-01

    A method for real-time stability monitoring is developed for supervising the steady-state operation of a boiling water reactor core. The decay ratio of the reactor power fluctuation is determined by measuring only the output neutron noise. The concept of an inverse system is introduced to identify the dynamic characteristics of the reactor core. The adoption of an adaptive digital filter is useful in real-time identification. A feasibility test that used measured output noise as an indication of reactor power suggests that this method is useful in a real-time stability monitoring system. Using this method, the tedious and difficult work for modeling reactor core dynamics can be reduced. The method employs a simple algorithm that eliminates the need for stochastic computation, thus making the method suitable for real-time computation with a simple microprocessor. In addition, there is no need to disturb the reactor core during operation. Real-time stability monitoring using the proposed algorithm may allow operation under less stable margins

  7. SUMOylation regulates nuclear localization and stability of TRAIP/RNF206

    International Nuclear Information System (INIS)

    Park, I. Seul; Han, Ye gi; Chung, Hee Jin; Jung, Yong Woo; Kim, Yonghwan; Kim, Hongtae

    2016-01-01

    TRAIP/RNF206 plays diverse roles in cell cycle progression, DNA damage response, and DNA repair pathways. Physiological importance of TRAIP is highlighted by the identification of pathogenic mutations of TRAIP gene in patients diagnosed with primordial dwarfism. Although the diverse functions of TRAIP in the nucleus have been well characterized, molecular mechanism of TRAIP retention in the nucleus has not been determined. Here, we discovered that TRAIP is post-translationally modified by the small ubiquitin-like protein (SUMO). In addition, we identified five SUMOylation sites in TRAIP, and successfully generated SUMOylation deficient mutant of TRAIP. In an attempt to define the functional roles of TRAIP SUMOylation, we discovered that SUMOylation deficient TRAIP is not retained in the nucleus. In addition, protein stability of SUMOylation deficient TRAIP is lower than wild type TRAIP, demonstrating that SUMOylation is critical for both proper subcellular localization and protein stability of TRAIP. Taken together, these findings improve the understanding clinical implication of TRAIP in various diseases including primordial dwarfism and cancers. - Highlights: • TRAIP is post-translationally modified by SUMO. • SUMOylation affects subcellular localization of TRAIP. • SUMOylation regulates protein stability of TRAIP.

  8. SUMOylation regulates nuclear localization and stability of TRAIP/RNF206

    Energy Technology Data Exchange (ETDEWEB)

    Park, I. Seul; Han, Ye gi; Chung, Hee Jin [Department of Biological Sciences, Sungkyunkwan University (SKKU), Suwon 440-746 (Korea, Republic of); Jung, Yong Woo [College of Pharmacy, Korea University, Sejong City 339-700 (Korea, Republic of); Kim, Yonghwan, E-mail: yhkim@sookmyung.ac.kr [Department of Biological Sciences, Sookmyung Women' s University, Seoul 04310 (Korea, Republic of); Kim, Hongtae, E-mail: khtcat@skku.edu [Department of Biological Sciences, Sungkyunkwan University (SKKU), Suwon 440-746 (Korea, Republic of)

    2016-02-19

    TRAIP/RNF206 plays diverse roles in cell cycle progression, DNA damage response, and DNA repair pathways. Physiological importance of TRAIP is highlighted by the identification of pathogenic mutations of TRAIP gene in patients diagnosed with primordial dwarfism. Although the diverse functions of TRAIP in the nucleus have been well characterized, molecular mechanism of TRAIP retention in the nucleus has not been determined. Here, we discovered that TRAIP is post-translationally modified by the small ubiquitin-like protein (SUMO). In addition, we identified five SUMOylation sites in TRAIP, and successfully generated SUMOylation deficient mutant of TRAIP. In an attempt to define the functional roles of TRAIP SUMOylation, we discovered that SUMOylation deficient TRAIP is not retained in the nucleus. In addition, protein stability of SUMOylation deficient TRAIP is lower than wild type TRAIP, demonstrating that SUMOylation is critical for both proper subcellular localization and protein stability of TRAIP. Taken together, these findings improve the understanding clinical implication of TRAIP in various diseases including primordial dwarfism and cancers. - Highlights: • TRAIP is post-translationally modified by SUMO. • SUMOylation affects subcellular localization of TRAIP. • SUMOylation regulates protein stability of TRAIP.

  9. Factors affecting individual foraging specialization and temporal diet stability across the range of a large "generalist" apex predator.

    Science.gov (United States)

    Rosenblatt, Adam E; Nifong, James C; Heithaus, Michael R; Mazzotti, Frank J; Cherkiss, Michael S; Jeffery, Brian M; Elsey, Ruth M; Decker, Rachel A; Silliman, Brian R; Guillette, Louis J; Lowers, Russell H; Larson, Justin C

    2015-05-01

    Individual niche specialization (INS) is increasingly recognized as an important component of ecological and evolutionary dynamics. However, most studies that have investigated INS have focused on the effects of niche width and inter- and intraspecific competition on INS in small-bodied species for short time periods, with less attention paid to INS in large-bodied reptilian predators and the effects of available prey types on INS. We investigated the prevalence, causes, and consequences of INS in foraging behaviors across different populations of American alligators (Alligator mississippiensis), the dominant aquatic apex predator across the southeast US, using stomach contents and stable isotopes. Gut contents revealed that, over the short term, although alligator populations occupied wide ranges of the INS spectrum, general patterns were apparent. Alligator populations inhabiting lakes exhibited lower INS than coastal populations, likely driven by variation in habitat type and available prey types. Stable isotopes revealed that over longer time spans alligators exhibited remarkably consistent use of variable mixtures of carbon pools (e.g., marine and freshwater food webs). We conclude that INS in large-bodied reptilian predator populations is likely affected by variation in available prey types and habitat heterogeneity, and that INS should be incorporated into management strategies to efficiently meet intended goals. Also, ecological models, which typically do not consider behavioral variability, should include INS to increase model realism and applicability.

  10. Factors affecting individual foraging specialization and temporal diet stability across the range of a large “generalist” apex predator

    Science.gov (United States)

    Rosenblatt, Adam E.; Nifong, James C.; Heithaus, Michael R.; Mazzotti, Frank J.; Cherkiss, Michael S.; Jeffery, Brian M.; Elsey, Ruth M.; Decker, Rachel A.; Silliman, Brian R.; Guillette, Louis J.; Lowers, Russell H.; Larson, Justin C.

    2015-01-01

    Individual niche specialization (INS) is increasingly recognized as an important component of ecological and evolutionary dynamics. However, most studies that have investigated INS have focused on the effects of niche width and inter- and intraspecific competition on INS in small-bodied species for short time periods, with less attention paid to INS in large-bodied reptilian predators and the effects of available prey types on INS. We investigated the prevalence, causes, and consequences of INS in foraging behaviors across different populations of American alligators (Alligator mississippiensis), the dominant aquatic apex predator across the southeast US, using stomach contents and stable isotopes. Gut contents revealed that, over the short term, although alligator populations occupied wide ranges of the INS spectrum, general patterns were apparent. Alligator populations inhabiting lakes exhibited lower INS than coastal populations, likely driven by variation in habitat type and available prey types. Stable isotopes revealed that over longer time spans alligators exhibited remarkably consistent use of variable mixtures of carbon pools (e.g., marine and freshwater food webs). We conclude that INS in large-bodied reptilian predator populations is likely affected by variation in available prey types and habitat heterogeneity, and that INS should be incorporated into management strategies to efficiently meet intended goals. Also, ecological models, which typically do not consider behavioral variability, should include INS to increase model realism and applicability.

  11. Living with the Devil: Stability in the 21st Century World With or Without Nuclear Weapons

    Science.gov (United States)

    2012-03-01

    author’s opinion - if we are not progressing, we must be falling behind . While an arms race is not desired, a strong and unwavering approach towards...than your congresses: on the day that two army corps can mutually annihilate each other in a second, all civilised nations will surely recoil with...we must thus consider this a driving force behind nuclear proliferation. Therefore, as diplomatic, political and social consequences continue to

  12. Heavy ion collisions with A = 1057: Aspects of nuclear stability and the nuclear equation of state in coalescing neutron-star binary systems

    International Nuclear Information System (INIS)

    Mathews, G.J.; Wilson, J.R.; Evans, C.R.; Detweiler, S.L.

    1987-12-01

    The dynamics of the final stages of the coalescence of two neturon stars (such as the binary pulsar PSR 1913+16) is an unsolved problem in astrophysics. Such systems are probably efficient generators of gravitational radiation, and may be significant contributors to heavy-element nucleosynthesis. The input physics for the study of such systems is similar to that required for the strudy of heavy-ion collision hydrodynamics; e.g., a finite temperature nuclear equation of state, properties of nuclei away from stability, etc. We discuss the development of a relativistic hydrodynamics code in three spatial dimensions for the purpose of studying such neutron-star systems. The properties of the mass-radius relation (determined by the nuclear equation of state) may lead to a proposed mechanism by which hot, highly neutronized matter is ejected from the coalescing stars. This material is photodisintegrated into a free (mostly) neutron gas which may subsequently experience rapid-neutron capture (r-process) nucleosynthesis. 15 refs., 4 figs

  13. The dynamics of somatic indicators of basketball players under the influence of the special exercises which are directed to the increase of stability of the vestibular analyzer

    Directory of Open Access Journals (Sweden)

    Yevhen Kharchenko

    2016-06-01

    Full Text Available Purpose: to determine stability of the vestibular analyzer of basketball players of the team of KhSAPC by indicators of somatic displacements after the standard vestibular irritations on the Barany chair, after the introduction of the special exercises in the educational – training process, which are directed on the increase of stability of the vestibular sensor-based system. Material & Methods: the analysis of references, methods of definition of a functional condition of the vestibular analyzer on indicators of somatic displacements before and after the irritation on the Barany chair, methods of mathematical statistics. 12 boys – basketball players of the men's national team of KhSAPC took part in the researches. Results: somatic indicators of a functional condition of the vestibular analyzer of students – basketball players of the team of KhSAPC, and, their changes under the influence of rotary loadings before the pedagogical experiment are given in the article. Conclusions: the analysis of the results which were received after the experiment showed the considerable improvement of indicators, according to the testing of the motive test (4x9 m (s, hand dynamometry of 100% of a maximum and 50% of a maximum of the right and left hands (р0,05.

  14. Inheritance and stability of mevinphos-resistance in Plutella xylostella (L.), with special reference to mutations of acetylcholinesterase 1.

    Science.gov (United States)

    Lin, Chia-Li; Yeh, Shih-Chia; Feng, Hai-Tung; Dai, Shu-Mei

    2017-09-01

    Diamondback moth (Plutella xylostella L.) causes enormous damage on cruciferous vegetables and can rapidly develop resistance to all kinds of insecticides. To effectively manage the insecticide resistance of P. xylostella, an understanding of its inheritance and stability is essential. Here we investigated the phenotypic and genotypic basis of mevinphos resistance by crossing two genetically pure lines of P. xylostella, an SH ggt wild-type strain and an SHM TCN resistant strain carrying 892T/T, 971C/C, and 1156T/G (TCN) mutations of the acetylcholinesterase 1 gene (Pxace1). Similar median lethal concentrations and degrees of dominance in the reciprocal cross progeny, and no plateau on the log concentration-probit line of F1 backcross and self-cross progeny, suggest that the mevinphos-resistance in P. xylostella is inherited as an autosomal and incomplete dominant trait governed by more than one gene. In the absence of mevinphos exposure, the resistance ratio and Pxace1 mutation frequency declined concomitantly in the SHM TCN strain. After 20-generation relaxation, the mevinphos resistance decreased from 52- to 6-fold and the Pxace1 mutation frequency of the TCN haplotype pair decreased from 100% to 0%. A good correlation was found between the resistance ratio and TCN frequency within the range of 12.5- to 25-fold resistance. Since there was no TCN haplotype pair detected below a resistance level of 12.5-fold, we speculate that resistance mechanisms other than target site insensitivity may exist. These observations are important for the prediction and management of mevinphos and related organophosphate resistance in field populations of P. xylostella. Copyright © 2016. Published by Elsevier Inc.

  15. Survey of special events recorded in nuclear power plants of the Federal Republic of Germany in the first quarter of 1991

    International Nuclear Information System (INIS)

    1991-01-01

    50 special events were reported in the old Federal States, 47 of them belonged to the reporting category N (normal notification), three to the reporting category E (immediate notification). According to the international evluation scale (INES = International Nuclear Events Scale) five of those events fell under INES category 1, the rest under category 0. The Greifswald nuclear power plant reported three events of category AE-3 (lowest category) at KGR-5. There was no release of radioactivity involved in these incidents, and there were no effects on man or the environment reported. (HP) [de

  16. Seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel

    Directory of Open Access Journals (Sweden)

    Kaláb Zdeněk

    2017-07-01

    Full Text Available This paper deals with the seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel in the Czech Republic. The basic source of data for historical earthquakes up to 1990 was the seismic website [10]. The most intense earthquake described occurred on September 15, 1590 in the Niederroesterreich region (Austria in the historical period; its reported intensity is Io = 8-9. The source of the contemporary seismic data for the period since 1991 to the end of 2014 was the website [11]. It may be stated based on the databases and literature review that in the period from 1900, no earthquake exceeding magnitude 5.1 originated in the territory of the Czech Republic.

  17. An Investigation of Power Stabilization and Space-Dependent Dynamics of a Nuclear Fluidized-Bed Reactor

    International Nuclear Information System (INIS)

    Pain, Christopher C.; Eaton, Matthew D.; Gomes, Jefferson L.M.A.; Oliveira, Cassiano R.E. de; Umpleby, Adrian P.; Ziver, Kemal; Ackroyd, Ron T.; Miles, Bryan; Goddard, Antony J.H.; Dam, H. van; Hagen, T.H.J.J. van der; Lathouwers, D.

    2003-01-01

    Previous work into the space-dependent kinetics of the conceptual nuclear fluidized bed has highlighted the sensitivity of fission power to particle movements within the bed. The work presented in this paper investigates a method of stabilizing the fission power by making it less sensitive to fuel particle movement. Steady-state neutronic calculations are performed to obtain a suitable design that is stable to radial and axial fuel particle movements in the bed. Detailed spatial/temporal simulations performed using the finite element transient criticality (FETCH) code investigate the dynamics of the new reactor design. A dual requirement of the design is that it has a moderate power output of ∼300 MW(thermal)

  18. Determination of stability of saturated sands of Bredasdorp and Varswater Formations: Koeberg nuclear power station

    International Nuclear Information System (INIS)

    De Witt, M.J.; Barker, O.B.

    1985-01-01

    The planning of the Koeberg nuclear power station was postulated on the basis of possible seismic ground movements of sufficient intensity to cause liquefaction of the sand overlying the bedrock. Where seismic instability may occur, it is normally necessary for the potentially liquefiable soils to be removed and replaced with a stable material. The site investigations were therefore designed to evaluate the soils parameters necessary for the safe excavation of sand. The properties of potential backfill materials were studied and requirements for selective stockpiling of material from the excavation defined

  19. Simulations and imaging algorithm development for a cosmic ray muon tomography system for the detection of special nuclear material in transport containers

    International Nuclear Information System (INIS)

    Jewett, C.; Anghel, V.N.P.; Armitage, J.; Boudjemline, K.; Botte, J.; Bryman, D.; Bueno, J.; Charles, E.; Cousins, T.; Didsbury, R.; Erhardt, L.; Erlandson, A.; Gallant, G.; Jason, A.; Jonkmans, G.; Liu, Z.; McCall, M.; Noel, S.; Oakham, F.G.; Ong, D.; Stocki, T.; Thompson, M.; Waller, D.

    2011-01-01

    The Cosmic Ray Inspection and Passive Tomography (CRIPT) collaboration is developing a cosmic ray muon tomography system to identify Special Nuclear Materials (SNM) in cargo containers. In order to gauge the viability of the technique, and to determine the best detector type, GEANT4 was used to simulate the passage of cosmic ray muons through a cargo container. The scattering density estimation (SDE) algorithm was developed and tested with data from these simulations to determine how well it could reconstruct the interior of a container. The simulation results revealed the ability of cosmic ray muon tomography techniques to image spheres of lead-shielded Special Nuclear Materials (SNM), such as uranium or plutonium, in a cargo container, containing a cargo of granite slabs. (author)

  20. Simulations and imaging algorithm development for a cosmic ray muon tomography system for the detection of special nuclear material in transport containers

    Energy Technology Data Exchange (ETDEWEB)

    Jewett, C.; Anghel, V.N.P. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Armitage, J.; Boudjemline, K.; Botte, J. [Carleton Univ., Dept. of Physics, Ottawa, Ontario (Canada); Bryman, D. [Advanced Applied Physics Solutions, Vancouver, British Columbia (Canada); Univ. of British Columbia, Vancouver, British Columbia (Canada); Bueno, J. [Advanced Applied Physics Solutions, Vancouver, British Columbia (Canada); Charles, E. [Canada Border Services Agency, Ottawa, Ontario (Canada); Cousins, T. [International Safety Research, Ottawa, Ontario (Canada); Didsbury, R. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Erhardt, L. [Defence Research and Development Canada, Ottawa, Ontario (Canada); Erlandson, A. [Carleton Univ., Dept. of Physics, Ottawa, Ontario (Canada); Gallant, G. [Canada Border Services Agency, Ottawa, Ontario (Canada); Jason, A. [Los Alamos National Laboratory, Los Alamos (United States); Jonkmans, G. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Liu, Z. [Advanced Applied Physics Solutions, Vancouver, British Columbia (Canada); Univ. of British Columbia, Vancouver, British Columbia (Canada); McCall, M.; Noel, S. [International Safety Research, Ottawa, Ontario (Canada); Oakham, F.G. [Carleton Univ., Dept. of Physics, Ottawa, Ontario (Canada); TRIUMF, Vancouver, British Columbia, (Canada); Ong, D.; Stocki, T. [Health Canada, Ottawa, Ontario (Canada); Thompson, M. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Waller, D. [Defence Research and Development Canada, Ottawa, Ontario (Canada)

    2011-07-01

    The Cosmic Ray Inspection and Passive Tomography (CRIPT) collaboration is developing a cosmic ray muon tomography system to identify Special Nuclear Materials (SNM) in cargo containers. In order to gauge the viability of the technique, and to determine the best detector type, GEANT4 was used to simulate the passage of cosmic ray muons through a cargo container. The scattering density estimation (SDE) algorithm was developed and tested with data from these simulations to determine how well it could reconstruct the interior of a container. The simulation results revealed the ability of cosmic ray muon tomography techniques to image spheres of lead-shielded Special Nuclear Materials (SNM), such as uranium or plutonium, in a cargo container, containing a cargo of granite slabs. (author)

  1. CSER-98-002: Criticality analysis for the storage of special nuclear material sources and standards in the WRAP Facility

    International Nuclear Information System (INIS)

    Goldberg, H.J.

    1998-01-01

    The Waste Receiving and Processing (WRAP) Facility will store uranium and transuranic (TRU) sources and standards for certification that WRAP meets the requirements of the Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP). In addition, WRAP must meet internal requirements for testing and validation of measuring instruments for nondestructive assay (NDA). In order to be certified for WIPP, WRAP will participate in the NDA Performance Demonstration Program (PDP). This program is a blind test of the NDA capabilities for TRU waste. It is intended to ensure that the NDA capabilities of this facility satisfy the requirements of the quality assurance program plan for the WIPP. The PDP standards have been provided by the Los Alamos National Laboratory (LANL) for this program. These standards will be used in the WRAP facility. To internally check the accuracy and sensitivity of the NDA instruments, a further set of sources and standards will also be used by the facility. Each sealed source or standard will be referred to herein as a unit. Various combinations of these units will be placed in test drums and/or boxes which will be subject to their own limits until unloaded. There will be two sealed test drums with five grams of weapons grade plutonium loaded in them. These drums will be appropriately marked and will be subject to the unit limits rather than the drum limits. This analysis shows that the storage and use of special nuclear material sources and standards within the limited control facility of WRAP (Rooms 101 and 104) is safe from a criticality standpoint. With the form, geometry, and masses involved with this evaluation, a criticality is not possible. The limits given in Section 2 should be imposed on facility operations

  2. Ceramics in nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T D; Mendel, J E [eds.

    1979-05-01

    Seventy-three papers are included, arranged under the following section headings: national programs for the disposal of radioactive wastes, waste from stability and characterization, glass processing, ceramic processing, ceramic and glass processing, leaching of waste materials, properties of nuclear waste forms, and immobilization of special radioactive wastes. Separate abstracts were prepared for all the papers. (DLC)

  3. Interactions of cullin3/KCTD5 complexes with both cytoplasmic and nuclear proteins: Evidence for a role in protein stabilization

    Energy Technology Data Exchange (ETDEWEB)

    Rutz, Natalja; Heilbronn, Regine; Weger, Stefan, E-mail: stefan.weger@charite.de

    2015-08-28

    Based on its specific interaction with cullin3 mediated by an N-terminal BTB/POZ homologous domain, KCTD5 has been proposed to function as substrate adapter for cullin3 based ubiquitin E3 ligases. In the present study we tried to validate this hypothesis through identification and characterization of additional KCTD5 interaction partners. For the replication protein MCM7, the zinc finger protein ZNF711 and FAM193B, a yet poorly characterized cytoplasmic protein, we could demonstrate specific interaction with KCTD5 both in yeast two-hybrid and co-precipitation studies in mammalian cells. Whereas trimeric complexes of cullin3 and KCTD5 with the respective KCTD5 binding partner were formed, KCTD5/cullin3 induced polyubiquitylation and/or proteasome-dependent degradation of these binding partners could not be demonstrated. On the contrary, KCTD5 or Cullin3 overexpression increased ZNF711 protein stability. - Highlights: • KCTD5 nuclear translocation depends upon M phase and protein oligomerization. • Identification of MCM7, ZNF711 and FAM193 as KCTD5 interaction partners. • Formation of trimeric complexes of KCTD5/cullin3 with MCM7, ZNF711 and FAM193B. • KCTD5 is not involved in polyubiquitylation of MCM7 replication factor. • The KCTD5/cullin3 complex stabilizes ZNF711 transcription factor.

  4. Probabilistic considerations on the effects of random soil properties on the stability of ground structures of nuclear power plants

    International Nuclear Information System (INIS)

    Ootori, Yasuki; Ishikawa, Hiroyuki; Takeda, Tomoyoshi

    2004-01-01

    In the JEAG4601-1987 (Japan Electric Association Guide for earthquake resistance design), either the conventional deterministic method or probabilistic method is used for evaluating the stability of ground foundations and surrounding slopes in nuclear power plants. The deterministic method, in which the soil properties of 'mean ± coefficient x standard deviation' is adopted for the calculations, is generally used in the design stage to data. On the other hand, the probabilistic method, in which the soil properties assume to have probabilistic distributions, is stated as a future method. The deterministic method facilitates the evaluation, however, it is necessary to clarify the relationship between the deterministic and probabilistic methods. In order to investigate the relationship, a simple model that can take into account the dynamic effect of structures, and a simplified method for taking the spatial randomness into account are proposed in this study. As a result, it is found that the shear strength of soil is the most important factor for the stability of grounds and slopes, and the probability below the safety factor evaluated with the soil properties of mean - 1.0 x standard deviation' by the deterministic methods of much lower. (author)

  5. Debt swapping as a tool for economic and social stabilization in Russia's closed nuclear cities

    Energy Technology Data Exchange (ETDEWEB)

    JL Fuller; KM Leek

    2000-03-08

    The magnitude of Russian foreign debt, both official bilateral and commercial, compounded by collapse of the Russian economic system, is an obstacle in preventing the Russian Federation from effectively increasing the domestic priority of drawing down its nuclear weapons complex and providing a healthy, competitive environment to its nuclear cities. Debt-for-nature swaps, introduced in the early 1980s, provide debtor nations with a means of converting a portion of foreign debt into local currency, often at steep discounts, to use for purposes such as environmental protection that serve both a domestic and international need. This paper presents the debt-for-nature concept as a model for providing an infusion of funds to further U.S. and international nonproliferation objectives to help stabilize Russian closed city economic conditions through direct work on proliferation problems and remediation of the environment. A specific proposal is presented to demonstrate the utility and efficacy of the dept swap concept through initial collaboration with the city administration of Ozersk. The purpose of the proposal is to facilitate making Ozersk a safe, healthy competitive city, providing useful employment for its scientists and population and converting its superior infrastructure into productive activities.

  6. Role of chromosome stability and telomere length in the production of viable cell lines for somatic cell nuclear transfer

    Directory of Open Access Journals (Sweden)

    Betts Dean H

    2006-08-01

    Full Text Available Abstract Background Somatic cell nuclear transfer (SCNT provides an appealing alternative for the preservation of genetic material in non-domestic and endangered species. An important prerequisite for successful SCNT is the availability of good quality donor cells, as normal embryo development is dependent upon proper reprogramming of the donor genome so that embryonic genes can be appropriately expressed. The characteristics of donor cell lines and their ability to produce embryos by SCNT were evaluated by testing the effects of tissue sample collection (DART biopsy, PUNCH biopsy, post-mortem EAR sample and culture initiation (explant, collagenase digestion techniques. Results Differences in initial sample size based on sample collection technique had an effect on the amount of time necessary for achieving primary confluence and the number of population doublings (PDL produced. Thus, DART and PUNCH biopsies resulted in cultures with decreased lifespans (50 PDL and chromosomally stable (>70% normal cells at 20 PDL cultures produced by post-mortem EAR samples. Chromosome stability was influenced by sample collection technique and was dependent upon the culture's initial telomere length and its rate of shortening over cell passages. Following SCNT, short-lived cultures resulted in significantly lower blastocyst development (≤ 0.9% compared to highly proliferative cultures (11.8%. Chromosome stability and sample collection technique were significant factors in determining blastocyst development outcome. Conclusion These data demonstrate the influence of culture establishment techniques on cell culture characteristics, including the viability, longevity and normality of cells. The identification of a quantifiable marker associated with SCNT embryo developmental potential, chromosome stability, provides a means by which cell culture conditions can be monitored and improved.

  7. Hydrochemical stability of groundwaters surrounding a spent nuclear fuel repository in a 100,000 year perspective

    Energy Technology Data Exchange (ETDEWEB)

    Puigdomeneck, I. (ed.)

    2001-09-01

    This report is focussed on the effects of climate changes on the chemical composition of deep groundwaters. The aim of the work has been to assess the hydrochemical stability at nuclear repository sites in Finland and Sweden. Sites investigated by SKB and POSIVA have been compared. The corresponding features are important in judging how sensitive a site might be to climatic changes. Evidence for climate effects in the past on groundwater compositions has been reviewed, including isotopic and mineralogical data. There is for example evidence that glacial meltwaters are currently present at repository depths in the Fennoscandian Shield. No evidence has been found however that oxidising conditions have ever prevailed at depth, even if glacial meltwaters presumably had a substantial amount of dissolved O{sub 2}. The depth distribution of different calcite types (and other fracture minerals) indicates stability in large-scale groundwater circulation over time. Information on past (and future) groundwater salinities has been sought after in the results of hydrological numerical models for Aespoe in Sweden and Olkiluoto in Finland. It is expected that groundwater salinities will change due to future climatic variations. The main effects will be from shoreline movements, permafrost and continental ice-sheets. In most sites the present reducing redox conditions will remain undisturbed during glacial cycles. The modelling indicated that most of the SKB suitability criteria will be met during the life-span of the repository and the groundwater composition will vary within what is observed in the samples collected today at various depths. The expected changes are therefore not judged to threaten the integrity and functioning of the repository. The major conclusion is that despite long-term hydrodynamic changes hydrochemical stability is expected to dominate at repository depth.

  8. Hydrochemical stability of groundwaters surrounding a spent nuclear fuel repository in a 100,000 year perspective

    International Nuclear Information System (INIS)

    Puigdomeneck, I.

    2001-09-01

    This report is focussed on the effects of climate changes on the chemical composition of deep groundwaters. The aim of the work has been to assess the hydrochemical stability at nuclear repository sites in Finland and Sweden. Sites investigated by SKB and POSIVA have been compared. The corresponding features are important in judging how sensitive a site might be to climatic changes. Evidence for climate effects in the past on groundwater compositions has been reviewed, including isotopic and mineralogical data. There is for example evidence that glacial meltwaters are currently present at repository depths in the Fennoscandian Shield. No evidence has been found however that oxidising conditions have ever prevailed at depth, even if glacial meltwaters presumably had a substantial amount of dissolved O 2 . The depth distribution of different calcite types (and other fracture minerals) indicates stability in large-scale groundwater circulation over time. Information on past (and future) groundwater salinities has been sought after in the results of hydrological numerical models for Aespoe in Sweden and Olkiluoto in Finland. It is expected that groundwater salinities will change due to future climatic variations. The main effects will be from shoreline movements, permafrost and continental ice-sheets. In most sites the present reducing redox conditions will remain undisturbed during glacial cycles. The modelling indicated that most of the SKB suitability criteria will be met during the life-span of the repository and the groundwater composition will vary within what is observed in the samples collected today at various depths. The expected changes are therefore not judged to threaten the integrity and functioning of the repository. The major conclusion is that despite long-term hydrodynamic changes hydrochemical stability is expected to dominate at repository depth

  9. Hydrochemical stability of groundwaters surrounding a spent nuclear fuel repository in a 100,000 year perspective

    Energy Technology Data Exchange (ETDEWEB)

    Puigdomenech, I. (ed.); Gurban, I.; Laaksoharju, M. [and others

    2001-12-01

    This report is focused on the effects of climate changes on the chemical composition of deep groundwaters. The aim of the work has been to assess the hydrochemical stability at nuclear repository sites in Finland and Sweden. Sites investigated by SKB and POSIVA have been compared. The corresponding features are important in judging how sensitive a site might be to climatic changes. Evidence for climate effects in the past on groundwater compositions has been reviewed, including isotopic and mineralogical data. There is for example evidence that glacial meltwaters are currently present at repository depths in the Fennoscandian Shield. No evidence has been found however that oxidising conditions have ever prevailed at depth, even if glacial meltwaters presumably had a substantial amount of dissolved 0{sub 2}. The depth distribution of different calcite types (and other fracture minerals) indicates stability in large-scale groundwater circulation over time. Information on past (and future) groundwater salinities has been sought after in the results of hydrological numerical models for Aespoe in Sweden and Olkiluoto in Finland. It is expected that groundwater salinities will change due to future climatic variations. The main effects will be from shoreline movements, permafrost and continental ice-sheets. In most sites the present reducing redox conditions will remain undisturbed during glacial cycles. The modelling indicated that most of the SKB suitability criteria will be met during the life-span of the repository and the groundwater composition will vary within what is observed in the samples collected today at various depths. The expected changes are therefore not judged to threaten the integrity and functioning of the repository. The major conclusion is that despite long-term hydrodynamic changes hydrochemical stability is expected to dominate at repository depth. (orig.)

  10. Special symposium for the IAEA 50th anniversary: Global challenges for the future of nuclear energy and the IAEA

    International Nuclear Information System (INIS)

    2007-01-01

    The objective of the symposium was to review the 50 years history of the activities of the IAEA and the current status of nuclear power and fuel cycle in the world and discuss the future vision regarding development and safety of nuclear power and fuel cycle and international cooperation. Topics covered were nuclear power and fuel cycle, nuclear safety and security, non proliferation, and national, regional, and IAEA's challenges for the future

  11. Debt swapping as a tool for economic and social stabilization in Russia's closed nuclear cities (briefing paper)

    Energy Technology Data Exchange (ETDEWEB)

    JL Fuller; KM Leek

    2000-03-08

    The next great issue on the Russian landscape will be management of its foreign debt. In the near future the United States will be called upon to lead an international program of debt restructuring to assist Russia in overcoming the burden of its debt trap. With debt service obligations equal to 50{percent} of 1999 revenues, Russia has virtually no chance of sustaining a program of economic recovery without debt relief (Hardt, 1999). With some form of debt restructuring a foregone conclusion, Russia, the United States, and world community have a vital stake in searching for creative ways to transform the inevitability of debt restructuring into something of value and constructive to Russia and the problems it faces. This was the rationale behind debt-for-nature swaps which emerged in the early 1980s in Latin American and Eastern Europe as a means of relieving developing nations of their crippling foreign debt. Debt-for-nature swaps served both domestic and international needs by converting a portion of foreign debt, often at steep discounts, into local currency that was then used to fund programs to preserve the environment. The debt swap mechanism provides the prospect of getting something of real value where nothing is expected. The Pacific Northwest National Laboratory (PNNL) has proposed to use the same model to synergistically capitalize defense threat reduction activities and environmental remediation within Russia's closed nuclear cities. Preventing the emigration of nuclear technology, expertise, and hardware from these cities to subnational groups and countries of proliferation concern is one of the world's foremost pressing problems. It is in the best national security interest of the United states to assist Russia in overcoming the legacy of the Cold War by helping to address the catastrophic environmental and public health effects of nuclear production that negatively impact economic stabilization.

  12. Debt swapping as a tool for economic and social stabilization in Russia's closed nuclear cities (briefing paper)

    International Nuclear Information System (INIS)

    JL Fuller; KM Leek

    2000-01-01

    The next great issue on the Russian landscape will be management of its foreign debt. In the near future the United States will be called upon to lead an international program of debt restructuring to assist Russia in overcoming the burden of its debt trap. With debt service obligations equal to 50% of 1999 revenues, Russia has virtually no chance of sustaining a program of economic recovery without debt relief (Hardt, 1999). With some form of debt restructuring a foregone conclusion, Russia, the United States, and world community have a vital stake in searching for creative ways to transform the inevitability of debt restructuring into something of value and constructive to Russia and the problems it faces. This was the rationale behind debt-for-nature swaps which emerged in the early 1980s in Latin American and Eastern Europe as a means of relieving developing nations of their crippling foreign debt. Debt-for-nature swaps served both domestic and international needs by converting a portion of foreign debt, often at steep discounts, into local currency that was then used to fund programs to preserve the environment. The debt swap mechanism provides the prospect of getting something of real value where nothing is expected. The Pacific Northwest National Laboratory (PNNL) has proposed to use the same model to synergistically capitalize defense threat reduction activities and environmental remediation within Russia's closed nuclear cities. Preventing the emigration of nuclear technology, expertise, and hardware from these cities to subnational groups and countries of proliferation concern is one of the world's foremost pressing problems. It is in the best national security interest of the United states to assist Russia in overcoming the legacy of the Cold War by helping to address the catastrophic environmental and public health effects of nuclear production that negatively impact economic stabilization

  13. Some considerations on the seismic stability of large slopes surrounding the nuclear power plant

    International Nuclear Information System (INIS)

    Ito, Hiroshi; Watanabe, Hiroyuki; Imaide, Hiroshi

    1982-01-01

    As a part of the researches with regard to the seismic stability of large scale slope, the authors have carried out the model test, in which the static failure has been generated by inclining the slope model. In this report, the results of static inclination tests of slope model are described and discussions are done from viewpoints of, 1. the mechanical behaviours and failure state of slope during the inclination test, 2. comparison between the results obtained by the static failure test (that is, inclination test) and those of another report with regard to the dynamic failure test which had been performed using the shaking table, and the relationship between an equivalent seismic coefficient obtained by static failure test and acceleration by dynamic failure test, 3. relationship between the failure state of inclination test and the factor of convensional circular arc slip method. (author)

  14. Microstructural stability concerning a potential nuclear use of Al-Mg-Si

    International Nuclear Information System (INIS)

    Urreta de Pereyra, S.E.

    1990-01-01

    Mechanical properties and microstructures in an Al-Mg-Si alloy (6061) are known to change during irradiation. Many authors report that mechanical strength reduces after irradiation and that the main cause of this drastic softening was shown to be the dissolution of hardening precipitates. In this work, the stability of needle-shaped precipitates before irradiation is studied. Evidence is provided to suggest that β' may not transform directly in β ' by growth, but that another nucleation event is necessary. For concentrations of about 1wt% Mg 2 Si, accidental reversion treatments of short times above 250 deg C are found to lead to a catastrophic drop in strength as a result of β' phase dissolution without simultaneous precipitation of β ' . It was also found that these phases may differ in composition as well as in structure as reported in the literature. Small precipitates are found in grain boundaries that are richer in silicon than the equilibrium phase Mg 2 Si. (Author)

  15. Thermal stability of chloroform in the steam condensate cycle of CANDU-PHW nuclear power plant

    International Nuclear Information System (INIS)

    Lepine, Louis; Gilbert, Roland; Ouellet, Lorenzo

    1992-01-01

    Analysis of samples taken at the Gentilly 2 (Quebec) CANDU-PHW (CANadian Deuterium Uranium - Pressurized Heavy Water) plant after chlorination and demineralization revealed the presence of all four trihalomethanes (THMs) (CHCl 3 , CHBrCl 2 , CHBr 2 Cl and CHBr 3 ) and other unidentified halogenated volatile compounds. Among the THMs, chloroform was the major contaminant. A study of its thermal stability in water at different temperatures confirmed the degradation of the CHCl 3 molecule according to the equation CHCl 3 + H2O → CO + 3 HCl. The reaction follows first order kinetics and has an activation energy of 100 kJ/mol. The estimated half-life is six seconds at 260 deg C, the maximum temperature of the steam condensate cycle

  16. Colloid stabilization by polyelectrolytes. Application to decontamination processes of nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Baumgartner, E.; Torok, J.

    1988-01-01

    Sodium salts of the following anionic polyelectrolytes were evaluated as particle stabilizers: polyacrylic acid, polymethacrylic acid, poly (methyl vinyl ethermaleic anhydride), sulfonated polymers. A cationic polyelectrolyte, a polyamine, was also evaluated. An active and an inactive oxidized carbon steel sample were treated in the same experimental set-up with the decontaminating reagent and with or without the polyelectrolyte. Activity pick-up by the inactive sample was measured. When no polyelectrolyte was added, 15% of the Co-60 activity was redeposited. With polyelectrolyte addition in the 5-450 mg kg/sup -1/ range, the Co60 activity redeposition ranged from 8.5 down to 0.8%. Polyacrylic acid was the most effective reagent. The transfer of the magnetite outer oxide crystals from the active to the inactive surfaces was identified on SEM micrographs.

  17. Subjects and educational objectives of specialized training courses for shift supervisors in nuclear power plants. Vol. 4

    International Nuclear Information System (INIS)

    1983-01-01

    Presentation of subjects taught, curricula, educational objectives of training courses for shift supervisors in nuclear power plants. The curricula for nuclear engineering fundamentals include subjects such as nuclear physics, reactor physics, reactor safety, radiation protection, legal provisions, job safety, reactor technology, applied thermohydraulics and thermodynamics, materials. (HAG) [de

  18. Genomic stability of lyophilized sheep somatic cells before and after nuclear transfer.

    Directory of Open Access Journals (Sweden)

    Domenico Iuso

    Full Text Available The unprecedented decline of biodiversity worldwide is urging scientists to collect and store biological material from seriously threatened animals, including large mammals. Lyophilization is being explored as a low-cost system for storage in bio-banks of cells that might be used to expand or restore endangered or extinct species through the procedure of Somatic Cell Nuclear Transfer (SCNT. Here we report that the genome is intact in about 60% of lyophylized sheep lymphocytes, whereas DNA damage occurs randomly in the remaining 40%. Remarkably, lyophilized nuclei injected into enucleated oocytes are repaired by a robust DNA repairing activity of the oocytes, and show normal developmental competence. Cloned embryos derived from lyophylized cells exhibited chromosome and cellular composition comparable to those of embryos derived from fresh donor cells. These findings support the feasibility of lyophylization as a storage procedure of mammalian cells to be used for SCNT.

  19. Genomic stability of lyophilized sheep somatic cells before and after nuclear transfer.

    Science.gov (United States)

    Iuso, Domenico; Czernik, Marta; Di Egidio, Fiorella; Sampino, Silvestre; Zacchini, Federica; Bochenek, Michal; Smorag, Zdzislaw; Modlinski, Jacek A; Ptak, Grazyna; Loi, Pasqualino

    2013-01-01

    The unprecedented decline of biodiversity worldwide is urging scientists to collect and store biological material from seriously threatened animals, including large mammals. Lyophilization is being explored as a low-cost system for storage in bio-banks of cells that might be used to expand or restore endangered or extinct species through the procedure of Somatic Cell Nuclear Transfer (SCNT). Here we report that the genome is intact in about 60% of lyophylized sheep lymphocytes, whereas DNA damage occurs randomly in the remaining 40%. Remarkably, lyophilized nuclei injected into enucleated oocytes are repaired by a robust DNA repairing activity of the oocytes, and show normal developmental competence. Cloned embryos derived from lyophylized cells exhibited chromosome and cellular composition comparable to those of embryos derived from fresh donor cells. These findings support the feasibility of lyophylization as a storage procedure of mammalian cells to be used for SCNT.

  20. Live embryo imaging to follow cell cycle and chromosomes stability after nuclear transfer.

    Science.gov (United States)

    Balbach, Sebastian T; Boiani, Michele

    2015-01-01

    Nuclear transfer (NT) into mouse oocytes yields a transcriptionally and functionally heterogeneous population of cloned embryos. Most studies of NT embryos consider only embryos at predefined key stages (e.g., morula or blastocyst), that is, after the bulk of reprogramming has taken place. These retrospective approaches are of limited use to elucidate mechanisms of reprogramming and to predict developmental success. Observing cloned embryo development using live embryo cinematography has the potential to reveal otherwise undetectable embryo features. However, light exposure necessary for live cell cinematography is highly toxic to cloned embryos. Here we describe a protocol for combined bright-field and fluorescence live-cell imaging of histone H2b-GFP expressing mouse embryos, to record cell divisions up to the blastocyst stage. This protocol, which can be adapted to observe other reporters such as Oct4-GFP or Nanog-GFP, allowed us to quantitatively analyze cleavage kinetics of cloned embryos.

  1. Monitoring of left ventricular ejection fraction with a miniature, nonimaging nuclear detector: accuracy and reliability over time with special reference to blood labeling.

    Science.gov (United States)

    Lindhardt, T B; Hesse, B; Gadsbøll, N

    1997-01-01

    The purpose of this study was to determine the accuracy of determinations of left ventricular ejection fraction (LVEF) by a nonimaging miniature nuclear detector system (Cardioscint) and to evaluate the feasibility of long-term LVEF monitoring in patients admitted to the coronary care unit, with special reference to the blood-labeling technique. Cardioscint LVEF values were compared with measurements of LVEF by conventional gamma camera radionuclide ventriculography in 33 patients with a wide range of LVEF values. In 21 of the 33 patients, long-term monitoring was carried out for 1 to 4 hours (mean 186 minutes), with three different kits: one for in vivo and two for in vitro red blood cell labeling. The stability of the labeling was assessed by determination of the activity of blood samples taken during the first 24 hours after blood labeling. The agreement between Cardioscint LVEF and gamma camera LVEF was good with automatic background correction (r = 0.82; regression equation y = 1.04x + 3.88) but poor with manual background correction (r = 0.50; y = 0.88x - 0.55). The agreement was highest in patients without wall motion abnormalities. The long-term monitoring showed no difference between morning and afternoon Cardioscint LVEF values. Short-lasting fluctuations in LVEFs greater than 10 EF units were observed in the majority of the patients. After 24 hours, the mean reduction in the physical decay-corrected count rate of the blood samples was most pronounced for the two in vitro blood-labeling kits (57% +/- 9% and 41% +/- 3%) and less for the in vivo blood-labeling kit (32% +/- 26%). This "biologic decay" had a marked influence on the Cardioscint monitoring results, demanding frequent background correction. A fairly accurate estimate of LVEF can be obtained with the nonimaging Cardioscint system, and continuous bedside LVEF monitoring can proceed for hours with little inconvenience to the patients. Instability of the red blood cell labeling during long

  2. Federal Republic of Germany R and D programme: A special issue of the journal radioactive waste management and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Merz, E.R.

    1986-01-01

    This book examines the issues of radioactive waste management and the nuclear fuel cycle in the Federal Republic of Germany. Topics considered include the challenges of waste handling and disposal, the borosilicate glass for Pamela, the treatment and conditioning of transuranelement bearing wastes in the Federal Republic of Germany, conditioning of low and intermediate level wastes, volume reduction of low level solid radioactive waste by incineration and compaction in the Federal Republic of Germany, MAW test emplacement in boreholes, treatment and disposal of special radioactive wastes comprising tritium, carbon 14, krypton 85 and iodine 129, and the German Project: ''Safety Studies for Nuclear Waste Management: Development of Safety Assessment Methodology for Final Disposal of Nuclear Waste in a Salt Dome

  3. Functional Design Criteria - plutonium stabilization and handling (PUSH) project W-460

    International Nuclear Information System (INIS)

    NELSON, D.W.

    1999-01-01

    This Functional Design Criteria (FDC) contains information to guide the design of the Stabilization and Packaging Equipment necessary to oxidize and package the remaining plutonium-bearing Special Nuclear Materials (SNM) currently in the Plutonium Finishing Plant (PFP) inventory. The FDC also guides the design of vault modifications to allow storage of 3013 packages of stabilized SNM for up to 50 years

  4. Functional Design Criteria plutonium stabilization and handling (PUSH) project W-460

    Energy Technology Data Exchange (ETDEWEB)

    NELSON, D.W.

    1999-09-02

    This Functional Design Criteria (FDC) contains information to guide the design of the Stabilization and Packaging Equipment necessary to oxidize and package the remaining plutonium-bearing Special Nuclear Materials (SNM) currently in the Plutonium Finishing Plant (PFP) inventory. The FDC also guides the design of vault modifications to allow storage of 3013 packages of stabilized SNM for up to 50 years.

  5. Opting out of the peaceful use of nuclear power in Germany. A promising special approach in the European context?

    International Nuclear Information System (INIS)

    Buedenbender, Martin

    2009-01-01

    Nuclear power is in the focus of politics and public attention in Germany not only because of the federal elections. Again and again, voices are heard which doubt the decision taken in 2000 to opt out of the use of nuclear power. The change in parliamentary majority in favor of the alliance of CDU/CSU and FDP as a result of the elections on September 27 is leading to another review of the opt-out decision, as the three parties in their platforms expressed themselves in favor of extending nuclear power plant life. This makes a stocktaking exercise of all salient arguments imperative at the present juncture. The perspective in that case should not be restricted to national aspects but include especially the influence of the European dimension of the subject. Present political positions in the 27 EU countries indicate a renaissance of nuclear power. Numerous countries, such as Italy, Sweden, Poland or the United Kingdom, revoked their historic opt-out decisions, are using nuclear power for the first time, or want to expand greatly the nuclear share in their electricity generation mix. All 3 European agencies with clear majorities advocate the extensive use of nuclear power as a long-term component of the mix of energy resources. Germany, with its decision to opt out of the use of nuclear power, is part of a minority. Being part of a European electricity market which will grow together more and more closely up to complete integration, Germany will always be supplied electricity from nuclear sources in the long run. This will be true irrespective of nuclear power plants being operated in the country. So, shutting down German nuclear power plants will not achieve the goals of nuclear opponents but merely give rise to additional challenges in power technology in an effort to ensure Germany's electricity supply. For this reason, the new German federal government should revoke the decision to opt out of the peaceful use of nuclear power. (orig.)

  6. Comparative evaluation of bivalent malaria rapid diagnostic tests versus traditional methods in field with special reference to heat stability testing in Central India.

    Directory of Open Access Journals (Sweden)

    Neeru Singh

    Full Text Available Malaria presents a diagnostic challenge in areas where both Plasmodium falciparum and P.vivax are co-endemic. Bivalent Rapid Diagnostic tests (RDTs showed promise as diagnostic tools for P.falciparum and P.vivax. To assist national malaria control programme in the selection of RDTs, commercially available seven malaria RDTs were evaluated in terms of their performance with special reference to heat stability.This study was undertaken in four forested districts of central India (July, 2011- March, 2012. All RDTs were tested simultaneously in field along with microscopy as gold standard. These RDTs were stored in their original packing at 25°C before transport to the field or they were stored at 35°C and 45°C upto 100 days for testing the performance of RDTs at high temperature. In all 2841 patients with fever were screened for malaria of which 26% were positive for P.falciparum, and 17% for P.vivax. The highest sensitivity of any RDT for P.falciparum was 98% (95% CI; 95.9-98.8 and lowest sensitivity was 76% (95% CI; 71.7-79.6. For P.vivax highest and lowest sensitivity for any RDT was 80% (95% CI; 94.9 - 83.9 and 20% (95% CI; 15.6-24.5 respectively. Heat stability experiments showed that most RDTs for P.falciparum showed high sensitivity at 45°C upto 90 days. While for P.vivax only two RDTs maintained good sensitivity upto day 90 when compared with RDTs kept at room temperature. Agreement between observers was excellent for positive and negative readings for both P.falciparum and P.vivax (Kappa >0.6-0.9.This is first field evaluation of RDTs regarding their temperature stability. Although RDTs are useful as diagnostic tool for P.falciparum and P.vivax even at high temperature, the quality of RDTs should be regulated and monitored more closely.

  7. Multifunctional non-viral gene vectors with enhanced stability, improved cellular and nuclear uptake capability, and increased transfection efficiency

    Science.gov (United States)

    Yang, Zhe; Jiang, Zhaozhong; Cao, Zhong; Zhang, Chao; Gao, Di; Luo, Xingen; Zhang, Xiaofang; Luo, Huiyan; Jiang, Qing; Liu, Jie

    2014-08-01

    We have developed a new multifunctional, non-viral gene delivery platform consisting of cationic poly(amine-co-ester) (PPMS) for DNA condensation, PEG shell for nanoparticle stabilization, poly(γ-glutamic acid) (γ-PGA) and mTAT (a cell-penetrating peptide) for accelerated cellular uptake, and a nuclear localization signal peptide (NLS) for enhanced intracellular transport of DNA to the nucleus. In vitro study showed that coating of the binary PPMS/DNA polyplex with γ-PGA promotes cellular uptake of the polyplex particles, particularly by γ-glutamyl transpeptidase (GGT)-positive cells through the GGT-mediated endocytosis pathway. Conjugating PEG to the γ-PGA led to the formation of a ternary PPMS/DNA/PGA-g-PEG polyplex with decreased positive charges on the surface of the polyplex particles and substantially higher stability in serum-containing aqueous medium. The cellular uptake rate was further improved by incorporating mTAT into the ternary polyplex system. Addition of the NLS peptide was designed to facilitate intracellular delivery of the plasmid to the nucleus--a rate-limiting step in the gene transfection process. As a result, compared with the binary PPMS/LucDNA polyplex, the new mTAT-quaternary PPMS/LucDNA/NLS/PGA-g-PEG-mTAT system exhibited reduced cytotoxicity, remarkably faster cellular uptake rate, and enhanced transport of DNA to the nucleus. All these advantageous functionalities contribute to the remarkable gene transfection efficiency of the mTAT-quaternary polyplex both in vitro and in vivo, which exceeds that of the binary polyplex and commercial Lipofectamine™ 2000/DNA lipoplex. The multifunctional mTAT-quaternary polyplex system with improved efficiency and reduced cytotoxicity represents a new type of promising non-viral vectors for the delivery of therapeutic genes to treat tumors.We have developed a new multifunctional, non-viral gene delivery platform consisting of cationic poly(amine-co-ester) (PPMS) for DNA condensation, PEG shell

  8. Spent nuclear fuel system dynamic stability under normal conditions of transportation

    Energy Technology Data Exchange (ETDEWEB)

    Jiang, Hao; Wang, Jy-An John, E-mail: wangja@ornl.gov

    2016-12-15

    Highlights: • A conformational potential effect of fuel assembly contact interaction induced transient shock. • Complex vibration modes and vibration load intensity were observed from fuel assembly system. • The project was able to link the periodic transient shock to spent fuel fatigue strength reduction. - Abstract: In a horizontal layout of a spent nuclear fuel (SNF) assembly under normal conditions of transportation (NCT), the fuel assembly’s skeleton formed by guide tubes and spacer grids is the primary load bearing structure for carrying and transferring the vibration loads within an SNF assembly. Therefore, the integrity of guide tubes and spacer grids will dictate the vibration amplitude/intensity of the fuel assembly during transport, and must be considered when designing multipurpose purpose canister (MPC) for safe SNF transport. This paper investigates the SNF assembly deformation dynamics during normal vibration mode, as well as the transient shock mode inside the cask during NCT. Dynamic analyses were performed in the frequency domain to study frequency characteristic of the fuel assembly system and in the time domain to simulate the transient dynamic response of the fuel assembly. To further evaluate the intensity of contact interaction induced by the local contacts’ impact loading at the spacer grid, detailed models of the actual spring and dimples of the spacer grids were created. The impacts between the fuel rod and springs and dimples were simulated with a 20 g transient shock load. The associated contact interaction intensities, in terms of reaction forces, were estimated from the finite element analyses (FEA) results. The bending moment estimated from the resultant stress on the clad under 20 g transient shock can be used to define the loading in cyclic integrated reversible-bending fatigue tester (CIRFT) vibration testing for the equivalent condition. To estimate the damage potential of the transient shock to the SNF vibration

  9. Atmospheric stability effects on potential radiological releases at a nuclear research facility in Romania: Characterising the atmospheric mixing state

    International Nuclear Information System (INIS)

    Chambers, Scott D.; Galeriu, Dan; Williams, Alastair G.; Melintescu, Anca; Griffiths, Alan D.; Crawford, Jagoda; Dyer, Leisa; Duma, Marin; Zorila, Bogdan

    2016-01-01

    A radon-based nocturnal stability classification scheme is developed for a flat inland site near Bucharest, Romania, characterised by significant local surface roughness heterogeneity, and compared with traditional meteorologically-based techniques. Eight months of hourly meteorological and atmospheric radon observations from a 60 m tower at the IFIN-HH nuclear research facility are analysed. Heterogeneous surface roughness conditions in the 1 km radius exclusion zone around the site hinder accurate characterisation of nocturnal atmospheric mixing conditions using conventional meteorological techniques, so a radon-based scheme is trialled. When the nocturnal boundary layer is very stable, the Pasquill–Gifford “radiation” scheme overestimates the atmosphere's capacity to dilute pollutants with near-surface sources (such as tritiated water vapour) by 20% compared to the radon-based scheme. Under these conditions, near-surface wind speeds drop well below 1 m s"−"1 and nocturnal mixing depths vary from ∼25 m to less than 10 m above ground level (a.g.l.). Combining nocturnal radon with daytime ceilometer data, we were able to reconstruct the full diurnal cycle of mixing depths. Average daytime mixing depths at this flat inland site range from 1200 to 1800 m a.g.l. in summer, and 500–900 m a.g.l. in winter. Using tower observations to constrain the nocturnal radon-derived effective mixing depth, we were able to estimate the seasonal range in the Bucharest regional radon flux as: 12 mBq m"−"2 s"−"1 in winter to 14 mBq m"−"2 s"−"1 in summer. - Highlights: • Site climatology accurately characterised by season and atmospheric stability class. • Comparison of "2"2"2Rn-based, Pasquill–Gifford and Richardson number stability indices. • Seasonal mixing depth estimates over the whole diurnal cycle by ceilometer and radon. • Seasonal variability in the regional radon source function well constrained.

  10. Special relativity

    International Nuclear Information System (INIS)

    Taylor, J.G.

    1975-01-01

    It is stated that the early chapters review special relativity from an elementary mathematical viewpoint, and include discussion of recent experiments which set out to test Einstein's predictions. The theory of relativity is then reformulated in more sophisticated mathematical language to show its relation to electro-magnetism, and to lay the foundation for more general viewpoints. The final chapter discusses in simple terms where activity in the field is currently centred, and where future interest lies. Chapter headings include: the constant speed of light; measuring time and distance; the Lorentz transformation (relativity of simultaneity, space-time and causality); relativistic kinematics (including - the Dopper effect); relativistic dynamics (including - nuclear binding energy, particle creation, electrodynamics); the structure of special relativity (including - the Lorentz group, the rotation group, elementary particle scattering); extensions of special relativity. (U.K.)

  11. Epstein-Barr virus nuclear antigen 3C stabilizes Gemin3 to block p53-mediated apoptosis.

    Directory of Open Access Journals (Sweden)

    Qiliang Cai

    2011-12-01

    Full Text Available The Epstein-Barr nuclear antigen 3C (EBNA3C, one of the essential latent antigens for Epstein-Barr virus (EBV-induced immortalization of primary human B lymphocytes in vitro, has been implicated in regulating cell proliferation and anti-apoptosis via interaction with several cellular and viral factors. Gemin3 (also named DDX20 or DP103 is a member of DEAD RNA helicase family which exhibits diverse cellular functions including DNA transcription, recombination and repair, and RNA metabolism. Gemin3 was initially identified as a binding partner to EBNA2 and EBNA3C. However, the mechanism by which EBNA3C regulates Gemin3 function remains unclear. Here, we report that EBNA3C directly interacts with Gemin3 through its C-terminal domains. This interaction results in increased stability of Gemin3 and its accumulation in both B lymphoma cells and EBV transformed lymphoblastoid cell lines (LCLs. Moreover, EBNA3C promotes formation of a complex with p53 and Gemin3 which blocks the DNA-binding affinity of p53. Small hairpin RNA based knockdown of Gemin3 in B lymphoma or LCL cells remarkably attenuates the ability of EBNA3C to inhibit the transcription activity of p53 on its downstream genes p21 and Bax, as well as apoptosis. These findings provide the first evidence that Gemin3 may be a common target of oncogenic viruses for driving cell proliferation and anti-apoptotic activities.

  12. Evaluation of the geologic relations and seismotectonic stability of the Yucca Mountain area, Nevada Nuclear Waste Site Investigation (NNWSI)

    International Nuclear Information System (INIS)

    1988-10-01

    This report provides a summary of progress for the project ''Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI)'' for the eighteen month period of January 1, 1987 to June 10, 1988. This final report was preceded by the final report for the initial six month period, July 1, 1986 to December 31, 1986 (submitted on January 25, 1987, and revised in June 1987). The general Task continued to coordinate project activities to meet general deadlines and responsibilities. The central office provided general secretarial support. The activities that were started during the first project period included expansion of the central copying facilities, growth of the central reprint, map, aerial and photograph collections, and some expansion of personal computer capabilities. The research and review accomplishments are mainly under the following tasks: quaternary tectonics, geochemical, mineral deposits, volcanic geology, seismology, tectonics, neotectonics, remote sensing, geotechnical assessments, geotechnical rock mass assessment, basinal studies, and strong ground motion

  13. New generation of nuclear fuels: Stability of different stearates under high doses gamma irradiation in the manufacturing process

    Energy Technology Data Exchange (ETDEWEB)

    Lebeau, D.; Esnouf, S. [Den-Service d’Etude du Comportement des Radionucléides (SECR), CEA, Université Paris-Saclay, F-91191, Gif-sur-Yvette (France); Gracia, J. [Den-Service d' Etudes des Combustibles et Matériaux à base d' Actinides (SECA), CEA, F-30207 Bagnols-sur-Cèze Cedex (France); Audubert, F. [Den-Service d' Analyse et de Caractérisation du Comportement des Combustibles (SA3C), CEA, F- 13115 Saint-Paul-lez-Durance (France); Ferry, M., E-mail: muriel.ferry@cea.fr [Den-Service d’Etude du Comportement des Radionucléides (SECR), CEA, Université Paris-Saclay, F-91191, Gif-sur-Yvette (France)

    2017-07-15

    In the future reactors, the pellets radioactivity will increase due to the modification of the plutonium concentration. The stability of the organic additive used as lubricating/deagglomerating agent has thus to be evaluated. Up to now, zinc stearate is employed, but new additives are tested in this study and compared to zinc stearate. In a first part of this paper, the order of magnitude of the dose deposited in the stearates has been estimated. Afterward, three different stearates have been irradiated, using gamma-rays at doses as high as 2000 kGy. Two atmospheres of irradiation were tested, i.e. inert atmosphere and air. Samples were characterized using the following analytical tools: mass spectrometry, thermogravimetry and infrared spectroscopy. The objective is the evaluation of the ageing of these materials. In the nuclear fuel pellets manufacturing context, the candidate which could replace zinc stearate, if this one is too degraded to fulfill its role of lubricant in the pellets of the future manufacturing, has been determined. - Highlights: •Dose deposition estimation for different stearates. •Stearates radiolysis and radio-oxidization at high doses using gamma-rays. •H{sub 2} emission estimation as a function of atmosphere and dose. •Chemical modifications in stearates as a function of atmosphere and dose. •Comparison of three stearates.

  14. Seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel

    Science.gov (United States)

    Kaláb, Zdeněk; Šílený, Jan; Lednická, Markéta

    2017-07-01

    This paper deals with the seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel in the Czech Republic. The basic source of data for historical earthquakes up to 1990 was the seismic website [1-]. The most intense earthquake described occurred on September 15, 1590 in the Niederroesterreich region (Austria) in the historical period; its reported intensity is Io = 8-9. The source of the contemporary seismic data for the period since 1991 to the end of 2014 was the website [11]. It may be stated based on the databases and literature review that in the period from 1900, no earthquake exceeding magnitude 5.1 originated in the territory of the Czech Republic. In order to evaluate seismicity and to assess the impact of seismic effects at depths of hypothetical deep geological repository for the next time period, the neo-deterministic method was selected as an extension of the probabilistic method. Each one out of the seven survey areas were assessed by the neo-deterministic evaluation of the seismic wave-field excited by selected individual events and determining the maximum loading. Results of seismological databases studies and neo-deterministic analysis of Čihadlo locality are presented.

  15. A special information campaign on decommissioning of unit 1 at the Ignalina Nuclear Power Plant started in Lithuania

    International Nuclear Information System (INIS)

    Vitkiene, E.

    2000-01-01

    A lack of understanding is felt in Lithuania of the importance of informing the public about nuclear energy, its safety and decisions related with nuclear energy in general. our swedish colleagues have noticed this flaw in our work and a joined decision has been taken to start a series of publicity projects. It was decided to work along three lines: a series of programmes on the national TV, support to the media of the town of Visaginas and creating an Internet page on the Ignalina Nuclear Power Plant decommissioning

  16. Preface to the Special Issue: Proceedings of the International Symposium on Strangeness in Nuclear and Hadronic Systems

    International Nuclear Information System (INIS)

    2010-01-01

    The International Symposium on "Strangeness in Nuclear and Hadronic Systems (SENDAI08)" was held at the Tohoku University Centennial Hall from Monday, 15th December, through Thursday, 18th December 2008; while a pre-symposium was also organized on 14th December. About 126 scientists participated in SENDAI08, including more than 46 from abroad. The symposium was organized as the third in the SENDAI symposium series on strangeness nuclear physics, which was initiated by the Tohoku University's experimental nuclear physics group in 1998. This time, it is motivated by recent progress of the research on nuclear and hadronic systems involving strangeness degree of freedom, particularly, by beams of electrons and photons at JLab, FINUDA, SPring8, LNS Tohoku, etc. and also at new facilities that will be completed in the near future such as J-PARC, etc.

  17. Utilization of nuclear energy for generating electric power in the FRG, with special regard to LWR-type reactors

    International Nuclear Information System (INIS)

    Vollradt, J.

    1977-01-01

    Comments on interdependencies in energy industry and energy generation as seen by energy supply utilities, stating that the generation of electric power in Germany can only be based on coal and nuclear energy in the long run, are followed by the most important, fundamental, nuclear-physical, technological and in part political interdependencies prevailing in the starting situation of 1955/58 when the construction of nuclear power plant reactors began. Then the development ranging to the 28000 MW nuclear power output to be expected in 1985 is outlined, totalling in 115000 MW electric power in the FRG. Finally, using the respectively latest order, the technical set up of each of the reactor types with 1300 MWe unit power offered by German manufacturers are described: BBC/BBR PWR-type reactor Neupotz, KWU-PWR-type reactor Hamm and KWU PWR-type reactor double unit B+C Gundremmingen. (orig.) [de

  18. Report of a Special Committee on the Review of U.S. Nuclear Power Plant Accident, second report

    International Nuclear Information System (INIS)

    1979-01-01

    Following on the issuance of the first report, for the accident in Three Mile Island Nuclear Power Plant in the United States there has appeared detailed information of such as reactor operation and radiation control. This has enabled technical evaluation of those items involved in nuclear power safety. The review results up to the beginning of September 1979 are presented, to meet popular desires to know the accident situation and to reflect the results in the nation's nuclear power generation. Contents are features and background of the TMI Nuclear Power Plant accident consequences, safety measures to be taken in Japan, and (in the appendix) the data on the TMI accident, countermeasures taken in Japan, etc. (Mori, K.)

  19. More than 30 years of opinion of French people on nuclear risks - Special release of the 2012 IRSN opinion survey

    International Nuclear Information System (INIS)

    El Jammal, Marie-Helene; Rollinger, Francois; Mur, Emmanuelle; Schuler, Matthieu; Tchernia, Jean-Francois

    2013-01-01

    Illustrated by many graphs and tables, this report comments and discusses the evolution of opinion surveys performed in France on the perception of nuclear risks through thirty annual IRSN opinion surveys. It appears that the opinion on nuclear is rather steady, and that French people have a rather rational perception of risk hierarchy. The first part outlines that unemployment is the main concern for French people, and that environmental concerns depend on current events. The second part analyses the perception of the nuclear risk with respect to other societal concerns and to other risks, and discusses the evolution of opinion from a quantitative to a qualitative sensitivity. The third part addresses the representations people have of nuclear activities and how they challenge the reality: perception of nuclear plants and of radioactive wastes, fear of a serious accident. The last part deals with issues related to responsibilities, abilities and governance: how actors of nuclear risk management are perceived, and expectations in terms of transparency and opinion plurality

  20. Role of the State Office for Nuclear Safety in testing special professional competence of selected personnel of nuclear facilities and selected personnel handling ionizing radiation sources

    International Nuclear Information System (INIS)

    Kovar, P.

    2003-01-01

    The laws and regulations governing the title topic are identified. The following terms are defined and their context highlighted: professional competence; special professional competence; selected personnel; requirements for selected personnel; requirements for selected personnel training; examination boards; and licensing procedure. (P.A.)

  1. A stability tool for use within TELEGRIP

    International Nuclear Information System (INIS)

    Son, W.H.; Trinkle, J.C.

    1998-12-01

    During the assembly of a product, it is vital that the partially-completed assembly be stable. To guarantee this, one must ensure that contacts among the parts and the fixtures are sufficient to stabilize the assembly. Thus, it would be desirable to have an efficient method for testing an assembly stability, and, if this is not possible, generating a set of additional fixture contact points, known as fixels, that will stabilize it. One can apply this method to the situation of safe handling of special nuclear material (SNM). To have these functionalities should help improve the safety and enhance the performance of special nuclear material (SNM) handling and storage operations, since some methods are needed for gripping objects in a stable manner. Also, one may need a way to find a pit-holding fixture inserted into containers. In this paper, the authors present a stability tool, which they call Stab Tool, which was developed to test the stability of objects grasped by robotic hands, objects placed in fixtures, or sets of objects piled randomly on top of one another. Stab Tool runs on top of a commercial software package, TELEGRIP, which is used for geometry modeling and motion creation. The successful development of the stability depends strongly on TELEGRIP's ability to compute the distances between pairs of three-dimensional bodies in the simulated environment. The interbody distance computation tool takes advantage of the polyhedral representations of bodies used by TELEGRIP and of linear programming techniques to yield an efficient algorithm

  2. A REPRINT of a July 1991 Report to Congress, Executive Summary of Verification of Nuclear Warhead Dismantlement and Special Nuclear Material Controls

    International Nuclear Information System (INIS)

    Fuller, James L.

    2008-01-01

    With the renewed thinking and debate about deep reductions in nuclear weapons, including recent proposals about eliminating nuclear warheads altogether, republishing the general conclusions of the Robinson Committee Report of 1992 appears useful. The report is sometimes referred to as the 3151 Report, from Section 3151 of the National Defense Authorization Act for FY1991, from where its requirement originated. This report contains the Executive Summary only and the forwarding letters from the Committee, the President of the United States, the Secretary of Energy, and C Paul Robinson, the head of the Advisory Committee

  3. Analysis of the morality of intention in nuclear deterrence, with special reference to final retaliation. Doctoral thesis

    Energy Technology Data Exchange (ETDEWEB)

    Zink, J.A.

    1990-01-01

    Quite apart from its apparent political obsolescence, the policy of nuclear deterrence is vulnerable to attack for its seemingly obvious immorality. Nuclear war is blatantly immoral, and nuclear deterrence requires a genuine intention to resort to the nuclear retaliation which would precipitate such a war. Therefore, since it is wrong to intend that which is wrong to do, deterrence is immoral. This thesis seeks to examine the nature of the deterrent intention as a means of verifying the soundness of the above deontological argument. This examination is carried out by first suggesting an acceptable notion of intention in general and then, after analysing the views of deterrent intention by other writers, proceeding to demonstrate the uniqueness of that intention. Having done this, and having explored the possibility that deterrence need not contain a genuine intention to retaliate, the thesis moves on to suggest and defend a moral principle which states that endeavours requiring the formation of an immoral intention may nevertheless be moral. Called the Principle of Double Intention (and based on the Principle of Double Effect), it offers a method for the moral assessment of agents who form immoral intentions within larger contexts. By applying this principle to nuclear deterrence, it is demonstrated that agents who undertake such a policy may be morally justified in doing so, provided certain conditions are met. The thesis closes with a refutation of the objection that an agent cannot rationally form an intention (such as that required in deterrence) which he has no reason to carry out.

  4. The future energy supply in Germany in a common Europe with special emphasis on the role of nuclear power

    International Nuclear Information System (INIS)

    Kopp, G.

    2003-01-01

    The decision by the red-green federal government to opt out of the use of nuclear power has considerable consequences for the power industry and the national economy of Germany. In addition, there are additional burdens resulting from the Renewable Energies Act and the Cogeneration Act. Besides economic aspects, there are ecological benefits to be considered in favor of nuclear power. In addition to renewable energy sources, it is one of the important sources of energy which are free from CO 2 emissions. In opt-out decision also jeopardizes the role of Germany as a partner in international cooperation, with an acknowledged standard of nuclear know-how and a cutting-edge position in technical safety. The approaches towards a future energy supply system were put into specific terms together with the CDU/CSU within the activities of the parliamentary committee of inquiry on 'sustainable Energy Supply Under Conditions of Globalization and Deregulation'. The growing dependence on external energy sources, and the goals of climate protection, are other important tasks of future energy policy within the European framework. The Green Book by the EU Commission constitutes a remarkable basis for discussion in this respect. Current problems connected with nuclear power should be discussed seriously in order for nuclear power to continue successfully to contribute to energy supply in Europe. (orig.) [de

  5. Scandium complexes: physico-chemical study and evaluation of stability in vitro and in vivo for nuclear medicine application

    International Nuclear Information System (INIS)

    Kerdjoudj, Rabha

    2014-01-01

    Among the different isotopes of Scandium that can be used in nuclear medicine may be mentioned the 47 Sc and 44 Sc. The first decays by emitting an electron associated with a 159 keV gamma can thus be used either for radiotherapy or TEMP imaging. The 44 Sc (3.97 h) decays in 94.27% in case by emitting a positron, with a γ photon energy equal to 1.157 MeV. This isotope is then an ideal candidate for applications in PET imaging. Currently, the Cyclotron of high energy and high intensity ARRONAX produce 44 Sc and co-produces the isomeric state the 44m Sc (2.44 d). The 44m Sc has properties (E(γ) = 270 keV, 98.8%), which allows to consider its use as a potential in vivo generator. Previous work had demonstrated that the DOTA ligand is most suitable and stable for Sc. This thesis aims; make in evidence the feasibility of the in vivo 44m / 44 Sc generator. Initially a procedure was optimized and validated for the production of 44m / 44 Sc with a high specific activity and chemical purity. Radiolabeling of DOTA conjugated peptides was then developed and optimized. Theoretical and experimental studies have been performed in order to demonstrate the feasibility of 44m / 44 Sc as a potential in vivo generator. Finally, in vitro stability studies on radiolabeled 44m / 44 Sc complexes were performed, followed by biodistribution studies and PET imaging. (author)

  6. Standard test method for nondestructive assay of special nuclear material holdup using Gamma-Ray spectroscopic methods

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2007-01-01

    1.1 This test method describes gamma-ray methods used to nondestructively measure the quantity of 235U, or 239Pu remaining as holdup in nuclear facilities. Holdup occurs in all facilities where nuclear material is processed, in process equipment, in exhaust ventilation systems and in building walls and floors. 1.2 This test method includes information useful for management, planning, selection of equipment, consideration of interferences, measurement program definition, and the utilization of resources (1, 2, 3, 4). 1.3 The measurement of nuclear material hold up in process equipment requires a scientific knowledge of radiation sources and detectors, transmission of radiation, calibration, facility operations and error analysis. It is subject to the constraints of the facility, management, budget, and schedule; plus health and safety requirements; as well as the laws of physics. The measurement process includes defining measurement uncertainties and is sensitive to the form and distribution of the material...

  7. Nuclear Stability Rules

    Science.gov (United States)

    Feather, N.

    2016-03-01

    General preface; Author's preface; 1. The systematics of stable nuclei; 2. Regularities in x-disintegration; 3. Regularities in β-disintegration; 4. Spontaneous fission and the number of the elements; References and author index; Subject index.

  8. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    Short communication. Full text included in abstract. The general manager of the Cigar Lake uranium mine in northern Saskatchewan, George Peebles, says high radiation levels in the mine will prevent miners from working in direct contact with the underground ore. The exceptionally high grade of uranium will force Cigar Lake Mining Corp. to adopt unconventional mining methods in which the equipment is controlled from remote locations. Mr. Peebles said that the uranium deposits at Cigar Lake are 100 times richer than the deposits at older uranium mines in Ontario, where workers can spend a full shift in direct contact with the uranium. Because the deposits are so rich, workers cannot be exposed to the gamma radiation and radon gas for more the a few hours at a time. The mining corporation will probably use the 'raise-boring' method, in which a drill is located in a tunnel above the ore zone. A vertical hole is then drilled through the ore. Under this method, several metres of rock will separate the drill operator from the uranium. The method is commonly used in hard-rock mining, but it has never been required in uranium mining. In addition, the corporation will have to use extensive ventilation to get rid of the radon gas in the mine. Moreover, because of ground stability problems at Cigar Lake, the corporation will find it difficult to use conventional drilling and blasting techniques. Special ground-support measures will be needed. Finally, the corporation will have to take precautions to deal with groundwater in the area. If the flow is not restricted, the mine would receive 2,000 cubic metres of water an hour, Mr. Peebles said. The Cigar Lake mine is the largest high-grade uranium deposit in the world. It contains an estimated 150,000 metric tons of uranium, mostly in ore with an average grade of 12% uranium. The uranium deposits are so rich that the mine can produce 5.5 million kilograms of uranium annually from slightly more than 90 tons of ore excavated each day

  9. Nuclear Scans

    Science.gov (United States)

    Nuclear scans use radioactive substances to see structures and functions inside your body. They use a special ... images. Most scans take 20 to 45 minutes. Nuclear scans can help doctors diagnose many conditions, including ...

  10. Particular intervention plan of the Civaux Nuclear Power Plant. Public version. Special provision of the organisation plan for civil protection response

    International Nuclear Information System (INIS)

    2016-04-01

    The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Civaux nuclear power plant (Vienne, France)

  11. Feasibility study of passive gamma spectrometry of molten core material from Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy - low-volatile FP and special nuclear material inventory analysis and fundamental characteristics of gamma-rays from fuel debris

    International Nuclear Information System (INIS)

    Sagara, Hiroshi; Tomikawa, Hirofumi; Watahiki, Masaru; Kuno, Yusuke

    2014-01-01

    The technologies applied to the analysis of the Three Mile Island accident were examined in a feasibility study of gamma spectrometry of molten core material from the Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy. The focus is on low-volatile fission products and heavy metal inventory analysis, and the fundamental characteristics of gamma-rays from fuel debris with respect to passive measurements. The inventory ratios of the low-volatile lanthanides, "1"5"4Eu and "1"4"4Ce, to special nuclear materials were evaluated by the entire core inventories in units 1, 2, and 3 with an estimated uncertainty of 9%-13% at the 1σ level for homogenized molten fuel material. The uncertainty is expected to be larger locally owing to the use of the irradiation cycle averaging approach. The ratios were also evaluated as a function of burnup for specific fuel debris with an estimated uncertainty of 13%-25% at the 1σ level for units 1 and 2, and most of the fuels in unit 3, although the uncertainty regarding the separated mixed oxide fuel in unit 3 would be significantly higher owing to the burnup dependence approach. Source photon spectra were also examined and cooling-time-dependent data sets were prepared. The fundamental characteristics of high-energy gamma-rays from fuel debris were investigated by a bare-sphere model transport calculation. Mass attenuation coefficients of fuel debris were evaluated to be insensitive to its possible composition in a high-energy region. The leakage photon ratio was evaluated using a variety of parameters, and a significant impact was confirmed for a certain size of fuel debris. Its correlation was summarized with respect to the leakage photopeak ratio of source "1"5"4Eu. Finally, a preliminary study using a hypothetical canister model of fuel debris based on the experience at Three Mile Island was presented, and future plans were introduced. (author)

  12. Nuclear

    International Nuclear Information System (INIS)

    2014-01-01

    This document proposes a presentation and discussion of the main notions, issues, principles, or characteristics related to nuclear energy: radioactivity (presence in the environment, explanation, measurement, periods and activities, low doses, applications), fuel cycle (front end, mining and ore concentration, refining and conversion, fuel fabrication, in the reactor, back end with reprocessing and recycling, transport), the future of the thorium-based fuel cycle (motivations, benefits and drawbacks), nuclear reactors (principles of fission reactors, reactor types, PWR reactors, BWR, heavy-water reactor, high temperature reactor of HTR, future reactors), nuclear wastes (classification, packaging and storage, legal aspects, vitrification, choice of a deep storage option, quantities and costs, foreign practices), radioactive releases of nuclear installations (main released radio-elements, radioactive releases by nuclear reactors and by La Hague plant, gaseous and liquid effluents, impact of releases, regulation), the OSPAR Convention, management and safety of nuclear activities (from control to quality insurance, to quality management and to sustainable development), national safety bodies (mission, means, organisation and activities of ASN, IRSN, HCTISN), international bodies, nuclear and medicine (applications of radioactivity, medical imagery, radiotherapy, doses in nuclear medicine, implementation, the accident in Epinal), nuclear and R and D (past R and D programmes and expenses, main actors in France and present funding, main R and D axis, international cooperation)

  13. Specific outcomes of the research on the radiation stability of the French nuclear glass towards alpha decay accumulation

    Science.gov (United States)

    Peuget, S.; Delaye, J.-M.; Jégou, C.

    2014-01-01

    This paper presents an overview of the main results of the French research on the long-term behavior of SON68 nuclear glass towards alpha decay accumulation. The effect of the radiation damage induced by alpha decay and also helium build-up were investigated by examining glass specimens, doped with a short-lived actinide 244Cm, irradiated by light and heavy ions. Additionally, atomistic simulations by molecular dynamics have provided further information on the atomic-scale effects of the macroscopic phenomena observed. These studies have shown that some macroscopic properties vary with the accumulation of alpha decay, but then stabilize after integrated doses of the order of 4 × 1018 α g-1. For example, the glass density diminishes by about 0.6%, its Young's modulus by about 15%, and its hardness by about 30%, while its fracture toughness increases by around 50%. The SEM and TEM characterization showed that the glass is still homogeneous. No phase separation, crystallization or bubbles formation was noticed up to an alpha decay dose corresponding to several thousand years of disposal of nuclear glass canister. Moreover the initial alteration rate of the glass is not significantly affected by the glass damage induced by alpha decays or heavy ions irradiations. The comparison of the macroscopic evolutions of the Cm doped glass with those obtained for glasses irradiated with light or heavy ions (from either experimental and molecular dynamic studies) suggests that the macroscopic evolutions are induced by the nuclear interactions induced by the recoil nuclei of alpha decay. The analysis of the behavior of the glass structure subjected to ballistic effects with various spectroscopic studies, together with the results of atomistic modeling by molecular dynamics, have identified some slight changes in the local order around some cations. Moreover a modification of the medium-range order has also been demonstrated through changes in the bond angles between network

  14. Specific outcomes of the research on the radiation stability of the French nuclear glass towards alpha decay accumulation

    Energy Technology Data Exchange (ETDEWEB)

    Peuget, S., E-mail: sylvain.peuget@cea.fr; Delaye, J.-M.; Jégou, C.

    2014-01-15

    This paper presents an overview of the main results of the French research on the long-term behavior of SON68 nuclear glass towards alpha decay accumulation. The effect of the radiation damage induced by alpha decay and also helium build-up were investigated by examining glass specimens, doped with a short-lived actinide {sup 244}Cm, irradiated by light and heavy ions. Additionally, atomistic simulations by molecular dynamics have provided further information on the atomic-scale effects of the macroscopic phenomena observed. These studies have shown that some macroscopic properties vary with the accumulation of alpha decay, but then stabilize after integrated doses of the order of 4 × 10{sup 18} α g{sup −1}. For example, the glass density diminishes by about 0.6%, its Young’s modulus by about 15%, and its hardness by about 30%, while its fracture toughness increases by around 50%. The SEM and TEM characterization showed that the glass is still homogeneous. No phase separation, crystallization or bubbles formation was noticed up to an alpha decay dose corresponding to several thousand years of disposal of nuclear glass canister. Moreover the initial alteration rate of the glass is not significantly affected by the glass damage induced by alpha decays or heavy ions irradiations. The comparison of the macroscopic evolutions of the Cm doped glass with those obtained for glasses irradiated with light or heavy ions (from either experimental and molecular dynamic studies) suggests that the macroscopic evolutions are induced by the nuclear interactions induced by the recoil nuclei of alpha decay. The analysis of the behavior of the glass structure subjected to ballistic effects with various spectroscopic studies, together with the results of atomistic modeling by molecular dynamics, have identified some slight changes in the local order around some cations. Moreover a modification of the medium-range order has also been demonstrated through changes in the bond angles

  15. Special graphites

    International Nuclear Information System (INIS)

    Leveque, P.

    1964-01-01

    A large fraction of the work undertaken jointly by the Commissariat a l'Energie Atomique (CEA) and the Pechiney Company has been the improvement of the properties of nuclear pile graphite and the opening up of new fields of graphite application. New processes for the manufacture of carbons and special graphites have been developed: forged graphite, pyro-carbons, high density graphite agglomeration of graphite powders by cracking of natural gas, impervious graphites. The physical properties of these products and their reaction with various oxidising gases are described. The first irradiation results are also given. (authors) [fr

  16. Environmental impact appraisal for renewal of Special Nuclear Material License No. SNM-1097 (Docket No. 70-1113)

    International Nuclear Information System (INIS)

    1984-06-01

    The proposed action, the full 5-year renewal of License SNM-1097, is necessary for GE to continue producing fuel used in light-water nuclear reactors. The fuel manufacturing operation principally involves converting UF 6 to UO 2 powder, pressing the UO 2 powder into pellets, sintering and grinding the pellets, loading the pellets into Zircaloy tubes, and then assembling the loaded tubes into fuel bundles. A variety of radiological and nonradiological gaseous, liquid, and solid wastes are generated. After treatment, some of the wastes are released to the environment. In addition to the nuclear fuel fabrication operation, there are other operations performed at GE which do not require NRC licensing (e.g., zirconium metal processing, production of fuel bundle and mechanical reactor components, and the manufacture of aircraft engine parts) and are not associated with the proposed action. 28 references, 15 figures, 21 tables

  17. Criteria for Special Nuclear Materials Inventory and Control Procedures; Criteres a Suivre Pour Proceder a l'Inventaire des Matieres Nucleaires Speciales et aux Mesures de Controle; Kriterii dlya inventarizatsii spetsial'nykh yadernykh materialov i metody ucheta; Criterios a Que Deben Ajustarse los Procedimientos de Inventario y Control de los Materiales Nucleares Especiales

    Energy Technology Data Exchange (ETDEWEB)

    Kinderman, E. M.; Tarrice, R. R. [Stanford Research Institute, Menlo Park, CA (United States)

    1966-02-15

    One of tile most significant problems that will face investors, managers and operators in nuclear activities and especially in the field of commercial nuclear power, will be the proper control of a nuclear materials inventory that will exceed US $5000 million in value by 1980. Special nuclear materials are expensive when compared to most materials of commerce, e.g. US prices for 90% enriched uranium and 3% enriched uranium as hexafluoride, and for heavy water are $10 808, $254 and $61.60 per kg, respectively. Moreover, in many cases these materials are subjected because of health and safety requirements to special governmental controls not directly related to their monetary value. Despite the high monetary values assigned to these materials, they are destined to be used in large quantity, e.g. some 50- 75 t of 3% enriched material will be used in 500-MW light-water-moderated reactor, and perhaps the equivalent of 200 to 300 reactors of such size will be in operation throughout the world by 1980. Past experience has resulted in the development of special procedures and practice for the commercial control of the large quantity, lower-value materials such as coal or iron ore and for the small quantity, higher value materials such as the precious metals. While they have like prices, special nuclear materials are different in kind and will be handled in quantities much greater than the precious metals. However, while special techniques or special adaptations of old techniques may be necessary, proper use of various established inventory control practices should be sufficient in most cases to protect adequately the investment of nations and individuals in these expensive materials. This paper establishes criteria for materials control. It specifically considers the appropriateness of various techniques of inventory control ranging from annual balancing of book records of receipts and shipments through detailed daily physical inventory in the light of the specific value

  18. Consequences of EU enlargement for supply and demand in the electricity market with special emphasis on nuclear power

    International Nuclear Information System (INIS)

    Jaeger, G.

    2004-01-01

    After the enlargement of the European Union, Europe has acquired a new dimension which is reflected also on the electricity market. The aggregate European electricity requirement of 3 000 TWh in Europe constitutes approximately one quarter of the world electricity generation. Nuclear power contributes a major share of 966 TWh. In electricity generation from nuclear power, EU-25 is No. 1 in the world. The rising demand for electricity cannot be met by the existing power plant park in the next few decades. Insufficient possibilities of exchange among countries and, especially, the enormous requirement to replace more than 200,000 MW of electricity generating capacity in Europe by 2020, plus another 100,000 MW arising from growing demand, make a comprehensive renewal of the European power plant park indispensable. After the EU enlargement, the standards of the ''old'' European Union are the yardstick for the entire ''new'' Union. This gives rise to enormous efforts, especially in the accession countries, to curb emissions and increase safety. The need for modern power plant technology is becoming particularly apparent in these cases. The example of the ten new member countries clearly shows the options realistically available for electricity generation in the future and indispensable for a favorable infrastructure. The conventional energy resources, i. e. coal, gas, and nuclear power, will be the main sources of electricity generation in Europe over the next few decades. This finding does not meet the expectations of many members of the public who feel that renewables would make the largest contribution to power supply in twenty years' time. This makes it imperative to regain popular acceptance in order to ensure electricity generation at favorable conditions and at a high level of environmental protection in the whole of Europe, with enough leeway to further advance the expansion of renewables and support a positive economic development of Europe. (orig.)

  19. Environmental Impact Appraisal for renewal of special nuclear material license No. SNM-42 (Docket No. 70-27)

    International Nuclear Information System (INIS)

    1984-03-01

    The Babcock and Wilcox Company (B and W) Naval Nuclear Fuel Division (NNFD) facility near Lynchburg, Virginia, produces fuel assemblies and complete fuel modules for reactors used in the US Navy nuclear propulsion program and fuel components for university and other research reactors; and processes scrap material to recover the enriched uranium content. No significant modifications of the production procedures for the US Navy nuclear fuel fabrication have been made since the previous environmental assessment, and none are anticipated during the five-year license renewal period being considered. In 1982 the fabrication of fuel assemblies for university and other research reactors was begun. This environmental assessment provides a review of the past five years of operation and an analysis of future impacts, including the effect of plant changes. The proposed action is the renewal of the license necessary for B and W to continue the existing fuel fabrication operations. Principal operations in the fabrication facility include the processing of highly enriched uranium (> 90% 235 U) into fuel elements and assembling the elements into complete reactor cores for shipment and eventual installation in US Navy facilities. The principal environmental impacts of current operation of the NNFD result from release of radioactive gases to the atmosphere and of radioactively contaminated liquids to the adjacent James River. The actual gaseous and liquid pollutants released during normal operation of the plant have been monitored and documented. The principal subjects addressed in this environmental assessment include water use, pollutant controls, environmental monitoring, and environmental impact of operation and accidents. Other site factors and plant operations necessary for this assessment are described, and aspects of insignificant impacts are identified. 10 figures, 36 tables

  20. A real-time material control concept for safeguarding special nuclear material in United States licensed processing facilities

    International Nuclear Information System (INIS)

    Shea, T.E.

    1976-01-01

    This paper describes general safeguards research being undertaken by the United States Nuclear Regulatory Commission. Efforts to improve the ability of United States licensed plants to contend with the perceived threat of covert material theft are emphasized. The framework for this improvement is to break down the internal control and accounting system into subsystems to achieve material isolation, inventory control, inventory characterization, and inventory containment analysis. A general programme is outlined to develop and evaluate appropriate mechanisms, integrate selected mechanisms into subsystems, and evaluate the subsystems in the context of policy requirements. (author)

  1. Standard format and content for a licensee physical security plan for the protection of special nuclear material of moderate or low strategic significance - January 1980

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    This guide describes the information required in the physical security plan submitted as part of an application for a license to possess, use, or transport special nuclear material (SNM) of moderate strategic significance or 10 kg or more of SNM of low strategic significance and recommends a standard format for presenting the information in an orderly arrangement. This standards format will thus serve as an aid to uniformity and completeness in the preparation and review of the physical protection plan of the license application. This document can also be used as guidance by licensees possessing or transporting less than 10 kg of SNM of low strategic significance in understanding the intent and implementing the requirements of paragraphs 73.67(a), 73.67(f), and 73.67(g) of 10 CRF Part 73

  2. Standard format and content for a licensee physical security plan for the protection of special nuclear material of moderate or low strategic significance (Revision 1, Feb. 1983)

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    This regulatory guide describes the information required in the physical security plan submitted as part of an application for a license to possess, use, or transport Special Nuclear Materials (SNM) of moderate strategic significance or 10 kg or more of SNM of low strategic significance and recommends a standard format for presenting the information in an orderly arrangement. This standard format will thus serve as an aid to uniformity and completeness in the preparation and review of the physical security plan of the license application. This document can also be used as guidance by licensees possessing or transporting less than 10 kg of SNM of low strategic significance in understanding the intent and implementing the requirements of paragraphs 73.67(a), 73.67(f), and 73.67(g) of 10 CFR Part 73

  3. Stability analysis of WONDY (a hydrocode based on the artifical viscosity method of von Neumann and Richtmyer) for a special case of Maxwell's Law

    International Nuclear Information System (INIS)

    Hicks, D.L.

    1978-01-01

    The artification viscosity method of von Neumann and Richtmyer was originally designed and analyzed for stability in the case when the material was an ideal gas. Recently a hydrocode (WONDY) based on the von Neumann-Richymyer scheme was used in calculating wave progagation problems in materials obeying a form of Maxwell's material law; signs of an unstable difference scheme appeared. A stability analysis shows that the timestep restrictions required for stability in certain cases can be more stringent for material laws of the Maxwell type than they are for material laws of the ideal gas type

  4. Differential nuclear shape dynamics of invasive andnon-invasive breast cancer cells are associated with actin cytoskeleton organization and stability.

    Science.gov (United States)

    Chiotaki, Rena; Polioudaki, Hara; Theodoropoulos, Panayiotis A

    2014-08-01

    Cancer cells often exhibit characteristic aberrations in their nuclear architecture, which are indicative of their malignant potential. In this study, we have examined the nuclear and cytoskeletal composition, attachment configuration dynamics, and osmotic or drug treatment response of invasive (Hs578T and MDA-MB-231) and non-invasive (MCF-10A and MCF-7) breast cancer cell lines. Unlike MCF-10A and MCF-7, Hs578T and MDA-MB-231 cells showed extensive nuclear elasticity and deformability and displayed distinct kinetic profiles during substrate attachment. The nuclear shape of MCF-10A and MCF-7 cells remained almost unaffected upon detachment, hyperosmotic shock, or cytoskeleton depolymerization, while Hs578T and MDA-MB-231 revealed dramatic nuclear contour malformations following actin reorganization.

  5. Investigation of active interrogation techniques to detect special nuclear material in maritime environments: Boarded search of a cargo container ship

    International Nuclear Information System (INIS)

    Grogan, Brandon R.; Henkel, James J.; Johnson, Jeffrey O.; Mihalczo, John T.; Miller, Thomas M.; Patton, Bruce W.

    2013-01-01

    The detonation of a terrorist nuclear weapon in the United States would result in the massive loss of life and grave economic damage. Even if a device was not detonated, its known or suspected presence aboard a cargo container ship in a U.S. port would have major economic and political consequences. One possible means to prevent this threat would be to board a ship at sea and search for the device before it reaches port. The scenario considered here involves a small Coast Guard team with strong intelligence boarding a container ship to search for a nuclear device. Using active interrogation, the team would nonintrusively search a block of shipping containers to locate the fissile material. Potential interrogation source and detector technologies for the team are discussed. The methodology of the scan is presented along with a technique for calculating the required interrogation source strength using computer simulations. MCNPX was used to construct a computer model of a container ship, and several search scenarios were simulated. The results of the simulations are presented in terms of the source strength required for each interrogation scenario. Validation measurements were performed in order to scale these simulation results to expected performance. Interrogations through the short (2.4 m) axis of a standardized shipping container appear to be feasible given the entire range of container loadings tested. Interrogations through several containers at once or a single container through its long (12.2 m) axis do not appear to be viable with a portable interrogation system

  6. Investigation of active interrogation techniques to detect special nuclear material in maritime environments: Boarded search of a cargo container ship

    Energy Technology Data Exchange (ETDEWEB)

    Grogan, Brandon R., E-mail: groganbr@ornl.gov; Henkel, James J.; Johnson, Jeffrey O.; Mihalczo, John T.; Miller, Thomas M.; Patton, Bruce W.

    2013-12-01

    The detonation of a terrorist nuclear weapon in the United States would result in the massive loss of life and grave economic damage. Even if a device was not detonated, its known or suspected presence aboard a cargo container ship in a U.S. port would have major economic and political consequences. One possible means to prevent this threat would be to board a ship at sea and search for the device before it reaches port. The scenario considered here involves a small Coast Guard team with strong intelligence boarding a container ship to search for a nuclear device. Using active interrogation, the team would nonintrusively search a block of shipping containers to locate the fissile material. Potential interrogation source and detector technologies for the team are discussed. The methodology of the scan is presented along with a technique for calculating the required interrogation source strength using computer simulations. MCNPX was used to construct a computer model of a container ship, and several search scenarios were simulated. The results of the simulations are presented in terms of the source strength required for each interrogation scenario. Validation measurements were performed in order to scale these simulation results to expected performance. Interrogations through the short (2.4 m) axis of a standardized shipping container appear to be feasible given the entire range of container loadings tested. Interrogations through several containers at once or a single container through its long (12.2 m) axis do not appear to be viable with a portable interrogation system.

  7. Greenpeace and the EIA process with special reference to the siting of a repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    Fredriksson, A.

    1995-01-01

    The author argues as follows: The legislation which currently regulates EIS, does not give any party other than the proponent the possibility of exercising influence over the EIA. Therefore, an extensive review and amendment of the existing legislation is necessary if the general public is to participate in the process. This should be regarded as necessary, if SKB is to gain general acceptance of its work. Work on developing a suitable method and identifying a suitable site is going on, but is not conducted in such a manner that it gives the general public an adequate possibility of participating. Furthermore, decision-makers in the candidate municipalities are not being given insight into the work. A specially established EIA authority, charged with the task of supervising the EIA, may lead to that the problems will be investigated in a better way, that can lead to the selection of the best method as well as the best site

  8. Greenpeace and the EIA process with special reference to the siting of a repository for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Fredriksson, A. [Greenpeace (Sweden)

    1995-12-01

    The author argues as follows: The legislation which currently regulates EIS, does not give any party other than the proponent the possibility of exercising influence over the EIA. Therefore, an extensive review and amendment of the existing legislation is necessary if the general public is to participate in the process. This should be regarded as necessary, if SKB is to gain general acceptance of its work. Work on developing a suitable method and identifying a suitable site is going on, but is not conducted in such a manner that it gives the general public an adequate possibility of participating. Furthermore, decision-makers in the candidate municipalities are not being given insight into the work. A specially established EIA authority, charged with the task of supervising the EIA, may lead to that the problems will be investigated in a better way, that can lead to the selection of the best method as well as the best site.

  9. Municipalities' opinions about decontamination in special decontamination area. Records from three and a half years after the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Kawasaki, Kota

    2015-01-01

    This study discusses opinions of 11 municipalities in Fukushima Prefecture designated as Special Decontamination Area as of the end of September 2014, about three and a half years after the Fukushima Daiichi Nuclear Power Plant accident. This study shows that (1) more than half of the municipalities recognize that decontamination activities of the national government which is responsible for decontamination in Special Decontamination Area are inadequate, (2) more than half of the municipalities recognize that residents cannot live their lives with a sense of safety and security unless air radiation dose is reduced to the level before the accident or less than 0.23 μSv/h, and (3) many municipalities recognize that residents will not be able to live their lives with a sense of safety and security even if the national government implements decontamination, (4) many municipalities points out 'Inability to secure enough temporary storage sites' and 'Inappropriateness of the decontamination policy and methods for forests or reservoir' as problems for the promotion of decontamination, and (5) almost all the municipalities recognize the necessity of the installation of interim storage facilities to accelerate the reconstruction of towns. (author)

  10. Municipalities' opinions about decontamination in special decontamination area. Records from four and a half years after the Fukushima Daiichi Nuclear Power Plant accident

    International Nuclear Information System (INIS)

    Kawasaki, Kota

    2016-01-01

    This study discusses opinions of 11 municipalities in Fukushima Prefecture designated as Special Decontamination Area as of the end of September 2015, about four and a half years afters the Fukushima Daiichi Nuclear Power Plant accident. This study shows that (1) more than half of the municipalities recognize that decontamination activities of the national government which is responsible for decontamination in Special Decontamination Area are inadequate, (2) most municipalities recognize that residents cannot live their lives with a sense of safety and security unless air radiation dose is reduced to the level before the accident or less than 0.23 μSv/h, (3) many municipalities recognize that residents will not be able to live their lives with a sense of safety and security even if the national government implements decontamination, (4) municipalities points out 'decontamination of forests or rivers and reconsideration of decontamination methods of forests or rivers', 'securement and maintenance of temporary storage site' and 'setting forth a numeric target concerning decontamination and implementation of additional decontamination after the first decontamination' as issues for the promotion of decontamination, and (5) all the municipalities recognize that that there are a lot of problems concerning the installation of interim storage facilities by the national government. (author)

  11. Plutonium stabilization and handling quality assurance program plan

    International Nuclear Information System (INIS)

    Weiss, E.V.

    1998-01-01

    This Quality Assurance Program Plan (QAPP) identifies project quality assurance requirements for all contractors involved in the planning and execution of Hanford Site activities for design, procurement, construction, testing and inspection for Project W-460, Plutonium Stabilization and Handling. The project encompasses procurement and installation of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing special nuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM

  12. Research contract: Seismic stability of nuclear power plants in Eastern Europe. Final report. From 15 April 1998 to 15 April 1999

    International Nuclear Information System (INIS)

    Ambriashvili, Y.

    1999-01-01

    General scientific scope of the presented program is assessment of stability and functionality of the nuclear power plants with RBMK type reactors in relation to External Evens including following: seismic capacity of structures, equipment and distribution systems; capacity of structures for impact type loading; capacity of structures for blast type loading. For the analyses only structures, equipment and distribution systems which are responsible for safety shutdown path are used. Since 1980 Atomenergoproject has been participated in development and carrying out the Research Program related to investigation of seismic stability of RBMK NPPs. This investigation was done for Smolensk and Kursk NPPs. It is known that the design basis of seismic analyses is investigation of dynamic characteristic (main frequencies and main modes) of structures, equipment and distribution systems. Therefore the assessment of capacity of structures and systems can be based on the results of seismic stability investigations. In the present final report some main results of dynamic analyses reactor building, electrical buildings, storage building, pipe lines, separators, electrical equipment, etc. are described. On the basis of the data site seismological investigation, calculations and different type of testing structures and equipment it was accepted, that the RBMK NPP is the Seismic Stability NPP up to 6 intensity by MSK64 scale. The results of calculation and testing investigations can be use for the dynamic analyses on the external events blast and impact loading. Using the results the probability analysis should be done

  13. Nuclear power

    International Nuclear Information System (INIS)

    Abd Khalik Wood

    2005-01-01

    This chapter discussed the following topics related to the nuclear power: nuclear reactions, nuclear reactors and its components - reactor fuel, fuel assembly, moderator, control system, coolants. The topics titled nuclear fuel cycle following subtopics are covered: , mining and milling, tailings, enrichment, fuel fabrication, reactor operations, radioactive waste and fuel reprocessing. Special topic on types of nuclear reactor highlighted the reactors for research, training, production, material testing and quite detail on reactors for electricity generation. Other related topics are also discussed: sustainability of nuclear power, renewable nuclear fuel, human capital, environmental friendly, emission free, impacts on global warming and air pollution, conservation and preservation, and future prospect of nuclear power

  14. Special irradiation techniques

    International Nuclear Information System (INIS)

    Colomez, Gerard; Veyrat, J.F.

    1981-01-01

    Irradiation trials conducted on materials-testing reactors should provide a better understanding of the phenomena which characterize the working and evolution in time of electricity-generating nuclear reactors. The authors begin by outlining the objectives behind experimental irradiation (applied to the various nuclear chains) and then describe the special techniques deployed to achieve these objectives [fr

  15. Physical fitness training reference manual for security force personnel at fuel cycle facilities possessing formula quantities of special nuclear materials

    International Nuclear Information System (INIS)

    Arzino, P.A.; Caplan, C.S.; Goold, R.E.

    1991-09-01

    The recommendations contained throughout this NUREG are being provided to the Nuclear Regulatory Commission (NRC) as a reference manual which can be used by licensee management as they develop a program plan for the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The recommendations in this NUREG are similar in part to those contained within the Department of Energy (DOE) Medical and Fitness Implementation Guide which was published in March 1991. The guidelines contained in this NUREG are not requirements, and compliance is not required. 25 refs

  16. Medical screening reference manual for security force personnel at fuel cycle facilities possessing formula quantities of special nuclear materials

    International Nuclear Information System (INIS)

    Arzino, P.A.; Brown, C.H.

    1991-09-01

    The recommendations contained throughout this NUREG were provided to the Nuclear Regulatory Commission (NRC) as medical screening information that could be used by physicians who are evaluating the parameters of the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The medical recommendations in this NUREG are similar in content to the medical standards contained in 10 CFR Part 1046 which, in part, specifies medical standards for the protective force personnel regulated by the Department of Energy. The guidelines contained in this NUREG are not requirements, and compliance is not required. 3 refs

  17. Introduction of unlimited liability into the atomic law with special regard to the international nuclear liability conventions

    International Nuclear Information System (INIS)

    Hohlefelder, W.

    1984-01-01

    The paper was read at the international symposium on nuclear liability held in Munich in September 1984 by OECD/NEA and IAEA. It outlines the basic principles of the Paris liability convention and the international development. The author pleads in favour of unlimited liability for hazards on grounds of history, legal policy, legal dogmatics and practice. Moreover he thinks it useful and appropriate because it also improves the protection of the citizens. The same as the federal government the author holds that unlimited liability for hazards is compatible with the maximum damages and the congruity regulations of the Paris and Brussels liability convention. An amendment to the liability convention, though not necessary, would be desirable to make clear that both options - limited and unlimited liability - are open. (HSCH) [de

  18. Physical fitness training reference manual for security force personnel at fuel cycle facilities possessing formula quantities of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Arzino, P.A.; Caplan, C.S.; Goold, R.E. (California State Univ., Hayward, CA (United States). Foundation)

    1991-09-01

    The recommendations contained throughout this NUREG are being provided to the Nuclear Regulatory Commission (NRC) as a reference manual which can be used by licensee management as they develop a program plan for the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The recommendations in this NUREG are similar in part to those contained within the Department of Energy (DOE) Medical and Fitness Implementation Guide which was published in March 1991. The guidelines contained in this NUREG are not requirements, and compliance is not required. 25 refs.

  19. Medical screening reference manual for security force personnel at fuel cycle facilities possessing formula quantities of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Arzino, P.A.; Brown, C.H. (California State Univ., Hayward, CA (United States). Foundation)

    1991-09-01

    The recommendations contained throughout this NUREG were provided to the Nuclear Regulatory Commission (NRC) as medical screening information that could be used by physicians who are evaluating the parameters of the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The medical recommendations in this NUREG are similar in content to the medical standards contained in 10 CFR Part 1046 which, in part, specifies medical standards for the protective force personnel regulated by the Department of Energy. The guidelines contained in this NUREG are not requirements, and compliance is not required. 3 refs.

  20. Nuclear-coupled thermal-hydraulic nonlinear stability analysis using a novel BWR reduced order model. Pt. 1. The effects of using drift flux versus homogeneous equilibrium models

    International Nuclear Information System (INIS)

    Dokhane, A.; Henning, D.; Chawla, R.; Rizwan-Uddin

    2003-01-01

    BWR stability analysis at PSI, as at other research centres, is usually carried out employing complex system codes. However, these do not allow a detailed investigation of the complete manifold of all possible solutions of the associated nonlinear differential equation set. A novel analytical, reduced order model for BWR stability has been developed at PSI, in several successive steps. In the first step, the thermal-hydraulic model was used for studying the thermal-hydraulic instabilities. A study was then conducted of the one-channel nuclear-coupled thermal-hydraulic dynamics in a BWR by adding a simple point kinetic model for neutron kinetics and a model for the fuel heat conduction dynamics. In this paper, a two-channel nuclear-coupled thermal-hydraulic model is introduced to simulate the out-of phase oscillations in a BWR. This model comprises three parts: spatial mode neutron kinetics with the fundamental and fist azimuthal modes; fuel heat conduction dynamics; and thermal-hydraulics model. This present model is an extension of the Karve et al. model i.e., a drift flux model is used instead of the homogeneous equilibrium model for two-phase flow, and lambda modes are used instead of the omega modes for the neutron kinetics. This two-channel model is employed in stability and bifurcation analyses, carried out using the bifurcation code BIFDD. The stability boundary (SB) and the nature of the Poincare-Andronov-Hopf bifurcation (PAF-B) are determined and visualized in a suitable two-dimensional parameter/state space. A comparative study of the homogeneous equilibrium model (HEM) and the drift flux model (DFM) is carried out to investigate the effects of the DFM parameters the void distribution parameter C 0 and the drift velocity V gi -on the SB, the nature of PAH bifurcation, and on the type of oscillation mode (in-phase or out-of-phase). (author)

  1. Nuclear and isotopic techniques for addressing nutritional problems, with special reference to current applications in developing countries.

    Science.gov (United States)

    Iyengar, Venkatesh

    2002-03-01

    Nuclear and isotopic techniques are valuable tools in human nutritional research studies. Isotopes, both radioactive and nonradioactive, enable detailed evaluations of nutrient intake, body composition, energy expenditure, status of micronutrients, and nutrient bioavailability. In recent times, isotopic methods have been widely used in a number of coordinated research projects and technical cooperation projects of the International Atomic Energy Agency's Nutrition Programme. The doubly labeled water technique combines the use of the stable isotopes oxygen-18 and hydrogen-2 (deuterium) to measure total energy expenditure in free-living human subjects, and to investigate the magnitude and causes of both undernutrition and the emergence of obesity in developing countries. The deuterium dilution technique is a reliable tool to measure breastmilk intake and thereby infant growth and development. In collaboration with the World Health Organization's Growth Monitoring Program, this technique is being used to generate new data on growth standards for children in developing countries. This technique is also used in the measurement of body composition by the estimation of lean body mass and fat mass in individuals. Stable isotopes of iron and zinc have been successfully used to assess the nutritional impact of several nationwide food supplementation-programs conducted on pregnant and lactating women and children in both industrialized and developing countries. Isotopic techniques are especially suitable for monitoring changes in body composition, energy metabolism, and mineral status (with particular reference to osteoporosis) in the elderly. Nuclear methods have also served to develop models for a physiological reference man in Asia in support of radiological health and safety issues, for establishing elemental composition of foods, and for measurement of pollutants in the environment.

  2. Seismic stability evaluation using 2-D FEM analysis for modeling nuclear power plants sited on gravel soil

    International Nuclear Information System (INIS)

    Iba, T.; Konno, T.; Irino, K.; Hama, I.; Oguro, E.; Iizuka, S.; Enami, A.

    1995-01-01

    Throughout Europe and the United States, many nuclear power plants have been built on Quaternary deposit sites. While in Japan, all nuclear power plants have been built at rock sites primarily to maintain a high seismic resistivity. However, as more nuclear power plants are planned for the future, it has become necessary to develop new siting technology from the stand point of expanding the available range of site selection and effective utilization of land. A draft on guidelines of the seismic design for siting on Quaternary deposits is being carried out with a purpose to ensure proper design and construction for such sites. (author). 10 figs., 2 tabs

  3. Emerging role of N- and C-terminal interactions in stabilizing (β/α8 fold with special emphasis on Family 10 xylanases

    Directory of Open Access Journals (Sweden)

    Amit Bhardwaj

    2012-09-01

    Full Text Available Xylanases belong to an important class of industrial enzymes. Various xylanases have been purified and characterized from a plethora of organisms including bacteria, marine algae, plants, protozoans, insects, snails and crustaceans. Depending on the source, the enzymatic activity of xylanases varies considerably under various physico-chemical conditions such as temperature, pH, high salt and in the presence of proteases. Family 10 or glycosyl hydrolase 10 (GH10 xylanases are one of the well characterized and thoroughly studied classes of industrial enzymes. The TIM-barrel fold structure which is ubiquitous in nature is one of the characteristics of family 10 xylanases. Family 10 xylanases have been used as a “model system” due to their TIM-barrel fold to dissect and understand protein stability under various conditions. A better understanding of structure-stability-function relationships of family 10 xylanases allows one to apply these governing molecular rules to engineer other TIM-barrel fold proteins to improve their stability and retain function(s under adverse conditions. In this review, we discuss the implications of N-and C-terminal interactions, observed in family 10 xylanases on protein stability under extreme conditions. The role of metal binding and aromatic clusters in protein stability is also discussed. Studying and understanding family 10 xylanase structure and function, can contribute to our protein engineering knowledge.

  4. EMERGING ROLE OF N- AND C-TERMINAL INTERACTIONS IN STABILIZING (β;/α8 FOLD WITH SPECIAL EMPHASIS ON FAMILY 10 XYLANASES

    Directory of Open Access Journals (Sweden)

    Amit Bhardwaj

    2012-09-01

    Full Text Available Xylanases belong to an important class of industrial enzymes. Various xylanases have been purified and characterized from a plethora of organisms including bacteria, marine algae, plants, protozoans, insects, snails and crustaceans. Depending on the source, the enzymatic activity of xylanases varies considerably under various physico-chemical conditions such as temperature, pH, high salt and in the presence of proteases. Family 10 or glycosyl hydrolase 10 (GH10 xylanases are one of the well characterized and thoroughly studied classes of industrial enzymes. The TIM-barrel fold structure which is ubiquitous in nature is one of the characteristics of family 10 xylanases. Family 10 xylanases have been used as a “model system” due to their TIM-barrel fold to dissect and understand protein stability under various conditions. A better understanding of structure-stability-function relationships of family 10 xylanases allows one to apply these governing molecular rules to engineer other TIM-barrel fold proteins to improve their stability and retain function(s under adverse conditions. In this review, we discuss the implications of N-and C-terminal interactions, observed in family 10 xylanases on protein stability under extreme conditions. The role of metal binding and aromatic clusters in protein stability is also discussed. Studying and understanding family 10 xylanase structure and function, can contribute to our protein engineering knowledge.

  5. The development of a specialized in-vivo body counter for radiation monitoring in the nuclear industry

    International Nuclear Information System (INIS)

    1981-01-01

    The design, construction, calibration and testing of a prototype mobile counting system to measure natural uranium in the lungs of workers in the nuclear fuel industry is described. The measurement method is based on the detection of gamma rays emitted during the decay of the daughters of uranium. The mobile facility consisted of a shadow shield and phoswich detector system mounted in a medium-sized trunk. Care was taken to ensure undistorted visual and verbal contact between the subject and the operator. Tests were made to optimize the location and thickness of the lead shielding. A single axle truck was insulated and a heater was installed for winter operation. There was sufficient room in the box to include a change room and waiting area as well as the shadow shield and electronics rack. An extensive series of test measurements was made at a number of locations. Control group studies of males were carried out and a model was developed which correctly predicted the subject background in the uranium region of the gamma spectrum when no uranium was present. The mobile counter was calibrated using the Rando Phantom. On a field trip to Bancroft In February 1981 the shadow shield configuration was shown to provide adequate background reduction for accurate uranium-in-lung measurements. With repeated measurements, changes in an individual's lung burden as small as 2 mg uranium could be detected. The minimum detectable amount of uranium on the basis of one measurement was 5.4 mg

  6. Report of special study meeting on 'Atomic energy research aiming at consistent nuclear fuel cycle', fiscal year 1992

    International Nuclear Information System (INIS)

    Nishina, Kojiro; Nishihara, Hideaki; Mishima, Kaichiro

    1994-12-01

    This meeting was held on March 4, 1993. Since the first power generation with the JPDR and the initial criticality of the KUR, 30 years, and since the initial criticality of the KUCA, 20 years have elapsed. The researchers in universities have contributed greatly to the research and education of atomic energy, but the perspective of leading the world hereafter in this field is very uncertain. This study meeting was held to seek the way to make the proper contribution. In the meeting, lectures were given on Japanese policy on nuclear fuel cycle, the present state of the upstream research and the downstream research in Japan, the experimental plan in NUCEF, the present state of the researches on TRU decay heat data and TRU nucleus data, the present state of the experimental researches at KUCA and at FCA, the present state of the research on the heat removal from high conversion LWRs and the KUR, the present state of the research on radioactive waste treatment, and the present state of TRU chemical research. The record of the holding of this study meeting is added. (K.I.)

  7. Assessment of biofouling community development on test panels submerged in Kudankulam coast with special reference to the Nuclear Power Project

    International Nuclear Information System (INIS)

    Satheesh, S.; Wesley, S. Godwin

    2008-01-01

    Biofouling is known to be one of the common problems in cooling water systems of power plants and several incidents of plant shutdown have been reported from various parts of the world. The settlement of marine organisms on an exposed hard surface depends obviously on the species, which are naturally present at a given site as well as their ability to attach and grow on that surface. Information on the organisms forming the fouling complex is necessary in view of the damages they cause to various marine structures and for devising protective measures. The present paper reports the results of the investigations of biofouling carried out for a period of two years from November 2003 to October 2004 at Kudankulam coast where a mega nuclear power project is under construction. Wooden test panels (10x10x3 cm) were fitted to a raft and submerged in the coastal waters. Total fouling biomass, thickness, coverage and community composition were analysed from the panels. Barnacles, mussels, ascidians, polychaetes, amphipods and seaweeds were the common fouling groups settled on the test panels. The total biomass reached to a maximum of 69.9 g.dm -2 (dry weight) after 330 days of exposure. The fouling thickness reached a maximum of 42.3 mm after 225 days of exposure. Results also showed a strong temporal variation in the fouling community recruitment. Based on the observations, Kudankulam coast could be categorized as a moderate fouling station mainly due to the low abundance of mussels in this region. (author)

  8. Special features of nuclear waste repository ventilation system VIS-A-VIS experiences at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    Sethi, S.C.

    1991-01-01

    The paper presents an analysis and discussion of the underground ventilation system at the Waste Isolation Pilot Plant (WIPP). Particular emphasis is placed on specific repository-related requirements and the gradual evolution of engineering designs relative to the WIPP Project scope. The ventilation system for a nuclear waste facility similar to WIPP is designed to provide a suitable environment for personnel and equipment during normal activities. It is also designed to provide confinement and channeling of potential airborne radioactive material in the event of an accidental release. It is desirable to identify and design all parallel activities and the required process equipment prior to completion of the repository mine final design. Such factors as ventilation requirements, drift sizes, bulkhead sizes, and placement are dependent on these items. Mine creep closure properties must be factored into the mine and ventilation equipment design considerations. Effects of natural ventilation pressures deserve due consideration in the design. Mine ventilation requirements are dominated by the diesel equipment to be operated in the underground horizon. WIPP engineers have also found it extremely desirable to have automated real-time monitoring and control for the underground ventilation air. Final testing and balancing of the ventilation system is an extremely important startup requirement. 3 refs., 2 figs

  9. Quivers For Special Fuel Rods-Disposal Of Special Fuel Rods In CASTOR V Casks

    International Nuclear Information System (INIS)

    Bannani, Amin; Cebula, Wojciech; Buchmuller, Olga; Huggenberg, Roland; Helmut Kuhl

    2015-01-01

    While GNS casks of the CASTOR family are a suitable means to transfer fuel assemblies (FA) from the NPP to an interim dry storage site, Germanys phase-out of nuclear energy has triggered the demand for an additional solution to dispose of special fuel rods (SFR), normally remaining in the fuel pond until the final shutdown of the NPP. SFR are fuel rods that had to be removed from fuel assemblies mainly due to their special condition, e. g. damages in the cladding of the fuel rods which may have occurred during reactor operations. SFR are usually stored in the spent fuel pond after they are removed from the FA. The quiver for special fuel rods features a robust yet simple design, with a high mechanical stability, a reliable leak-tightness and large safety margins for future requirements on safety analysis. The quiver for special fuel rods can be easily adapted to a large variety of different damaged fuel rods and tailored to the specific need of the customer. The quiver for special fuel rods is adaptable e.g. in length and diameter for use in other types of transport and storage casks and is applicable in other countries as well. The overall concept presented here is a first of its kind solution for the disposal of SFRs via Castor V-casks. This provides an important precondition in achieving the status 'free from nuclear fuel' of the shut down German NPPs

  10. Quivers For Special Fuel Rods-Disposal Of Special Fuel Rods In CASTOR V Casks

    Energy Technology Data Exchange (ETDEWEB)

    Bannani, Amin; Cebula, Wojciech; Buchmuller, Olga; Huggenberg, Roland [GNS, Essen (Germany); Helmut Kuhl [WTI, Julich (Germany)

    2015-05-15

    While GNS casks of the CASTOR family are a suitable means to transfer fuel assemblies (FA) from the NPP to an interim dry storage site, Germanys phase-out of nuclear energy has triggered the demand for an additional solution to dispose of special fuel rods (SFR), normally remaining in the fuel pond until the final shutdown of the NPP. SFR are fuel rods that had to be removed from fuel assemblies mainly due to their special condition, e. g. damages in the cladding of the fuel rods which may have occurred during reactor operations. SFR are usually stored in the spent fuel pond after they are removed from the FA. The quiver for special fuel rods features a robust yet simple design, with a high mechanical stability, a reliable leak-tightness and large safety margins for future requirements on safety analysis. The quiver for special fuel rods can be easily adapted to a large variety of different damaged fuel rods and tailored to the specific need of the customer. The quiver for special fuel rods is adaptable e.g. in length and diameter for use in other types of transport and storage casks and is applicable in other countries as well. The overall concept presented here is a first of its kind solution for the disposal of SFRs via Castor V-casks. This provides an important precondition in achieving the status 'free from nuclear fuel' of the shut down German NPPs.

  11. A direct, single-step plasma arc-vitreous ceramic process for stabilizing spent nuclear fuels, sludges, and associated wastes

    International Nuclear Information System (INIS)

    Feng, X.; Einziger, R.E.; Eschenbach, R.C.

    1997-01-01

    A single-step plasma arc-vitreous ceramic (PAVC) process is described for converting spent nuclear fuel (SNF), SNF sludges, and associated wastes into a vitreous ceramic waste form. This proposed technology is built on extensive experience of nuclear waste form development and nuclear waste treatment using the commercially available plasma arc centrifugal (PAC) system. SNF elements will be loaded directly into a PAC furnace with minimum additives and converted into vitreous ceramics with up to 90 wt% waste loading. The vitreous ceramic waste form should meet the functional requirements for borosilicate glasses for permanent disposal in a geologic repository and for interim storage. Criticality safety would be ensured through the use of batch modes, and controlling the amount of fuel processed in one batch. The minimum requirements on SNF characterization and pretreatment, the one-step process, and minimum secondary waste generation may reduce treatment duration, radiation exposure, and treatment cost

  12. The fanconi anemia proteins FANCA and FANCG stabilize each other and promote the nuclear accumulation of the Fanconi anemia complex.

    Science.gov (United States)

    Garcia-Higuera, I; Kuang, Y; Denham, J; D'Andrea, A D

    2000-11-01

    Fanconi anemia (FA) is an autosomal recessive cancer susceptibility syndrome with 8 complementation groups. Four of the FA genes have been cloned, and at least 3 of the encoded proteins, FANCA, FANCC, and FANCG/XRCC9, interact in a multisubunit protein complex. The FANCG protein binds directly to the amino terminal nuclear localization sequence (NLS) of FANCA, suggesting that FANCG plays a role in regulating FANCA nuclear accumulation. In the current study the functional consequences of FANCG/FANCA binding were examined. Correction of an FA-G cell line with the FANCG complementary DNA (cDNA) resulted in FANCA/FANCG binding, prolongation of the cellular half-life of FANCA, and an increase in the nuclear accumulation of the FA protein complex. Similar results were obtained upon correction of an FA-A cell line, with a reciprocal increase in the half-life of FANCG. Patient-derived mutant forms of FANCA, containing an intact NLS sequence but point mutations in the carboxy-terminal leucine zipper region, bound FANCG in the cytoplasm. The mutant forms failed to translocate to the nucleus of transduced cells, thereby suggesting a model of coordinated binding and nuclear translocation. These results demonstrate that the FANCA/FANCG interaction is required to maintain the cellular levels of both proteins. Moreover, at least one function of FANCG and FANCA is to regulate the nuclear accumulation of the FA protein complex. Failure to accumulate the nuclear FA protein complex results in the characteristic spectrum of clinical and cellular abnormalities observed in FA.

  13. J-integral elastic plastic fracture mechanics evaluation of the stability of cracks in nuclear reactor pressure vessels

    International Nuclear Information System (INIS)

    Gomez, M.P.; McMeeking, R.M.; Parks, D.M.

    1980-06-01

    Contributions were made toward developing a new methodology to assess the stability of cracks in pressure vessels made from materials that exhibit a significant increase in toughness during the early increments of crack growth. It has a wide range of validity from linear elastic to fully plastic behavior

  14. X-ray comb generation from nuclear-resonance-stabilized x-ray free-electron laser oscillator for fundamental physics and precision metrology

    Directory of Open Access Journals (Sweden)

    B. W. Adams

    2015-03-01

    Full Text Available An x-ray free-electron laser oscillator (XFELO is a next-generation x-ray source, similar to free-electron laser oscillators at VUV and longer wavelengths but using crystals as high-reflectivity x-ray mirrors. Each output pulse from an XFELO is fully coherent with high spectral purity. The temporal coherence length can further be increased drastically, from picoseconds to microseconds or even longer, by phase-locking successive XFELO output pulses, using the narrow nuclear resonance lines of nuclei such as ^{57}Fe as a reference. We show that the phase fluctuation due to the seismic activities is controllable and that due to spontaneous emission is small. The fluctuation of electron-bunch spacing contributes mainly to the envelope fluctuation but not to the phase fluctuation. By counting the number of standing-wave maxima formed by the output of the nuclear-resonance-stabilized (NRS XFELO over an optically known length, the wavelength of the nuclear resonance can be accurately measured, possibly leading to a new length or frequency standard at x-ray wavelengths. A NRS-XFELO will be an ideal source for experimental x-ray quantum optics as well as other fundamental physics. The technique can be refined for other, narrower resonances such as ^{181}Ta or ^{45}Sc.

  15. Nuclear

    International Nuclear Information System (INIS)

    Anon.

    2000-01-01

    The first text deals with a new circular concerning the collect of the medicine radioactive wastes, containing radium. This campaign wants to incite people to let go their radioactive wastes (needles, tubes) in order to suppress any danger. The second text presents a decree of the 31 december 1999, relative to the limitations of noise and external risks resulting from the nuclear facilities exploitation: noise, atmospheric pollution, water pollution, wastes management and fire prevention. (A.L.B.)

  16. Standard test method for nondestructive assay of special nuclear material in low density scrap and waste by segmented passive gamma-Ray scanning

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2010-01-01

    1.1 This test method covers the transmission-corrected nondestructive assay (NDA) of gamma-ray emitting special nuclear materials (SNMs), most commonly 235U, 239Pu, and 241Am, in low-density scrap or waste, packaged in cylindrical containers. The method can also be applied to NDA of other gamma-emitting nuclides including fission products. High-resolution gamma-ray spectroscopy is used to detect and measure the nuclides of interest and to measure and correct for gamma-ray attenuation in a series of horizontal segments (collimated gamma detector views) of the container. Corrections are also made for counting losses occasioned by signal processing limitations (1-3). 1.2 There are currently several systems in use or under development for determining the attenuation corrections for NDA of radioisotopic materials (4-8). A related technique, tomographic gamma-ray scanning (TGS), is not included in this test method (9, 10, 11). 1.2.1 This test method will cover two implementations of the Segmented Gamma Scanning ...

  17. Radiation portal monitor with {sup 10}B+ZnS(Ag) neutron detector performance for the detection of special nuclear materials

    Energy Technology Data Exchange (ETDEWEB)

    Guzman G, K. A.; Gallego, E.; Lorente, A.; Ibanez F, S. [Universidad Politecnica de Madrid, Departamento de Ingenieria Energetica, ETSI Industriales, C. Jose Gutierrez Abascal 2, 28006 Madrid (Spain); Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas, Zac. (Mexico); Gonzalez, J. A. [Universidad Politecnica de Madrid, Laboratorio de Ingenieria Nuclear, ETSI Caminos, Canales y Puertos, C. Prof. Aranguren 3, 28040 Madrid (Spain); Mendez, R., E-mail: ingkarenguzman@gmail.com [Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, Laboratorio de Patrones Neutronicos, Av. Complutense 40, 28040 Madrid (Spain)

    2016-10-15

    In homeland security, neutron detection is used to prevent the smuggling of special nuclear materials. Thermal neutrons are normally detected with {sup 3}He proportional counters, in the radiation portal monitors, Rpms, however due to the {sup 3}He shortage new procedures are being studied. In this work Monte Carlo methods, using the MCNP6 code, have been used to study the neutron detection features of a {sup 10}B+ZnS(Ag) under real conditions inside of a Rpm. The performance for neutron detection was carried out for {sup 252}Cf, {sup 238}U and {sup 239}Pu under different conditions. In order to mimic an actual situation occurring at border areas, a sample of SNM sited inside a vehicle was simulated and the Rpm with {sup 10}B+ZnS(Ag) response was calculated. At 200 cm the {sup 10}B+ZnS(Ag) on Rpm response is close to 2.5 cps-ng {sup 252}Cf, when the {sup 252}Cf neutron source is shielded with 0.5 cm-thick lead and 2.5 cm-thick polyethylene fulfilling the ANSI recommendations. Three different geometries of neutron detectors of {sup 10}B+ZnS(Ag) in a neutron detection system in Rpm were modeled. Therefore, the {sup 10}B+ZnS(Ag) detectors are an innovative and viable replacement for the {sup 3}He detectors in the Rpm. (Author)

  18. Investigations of active interrogation techniques to detect special nuclear material in maritime environments: Standoff interrogation of small- and medium-sized cargo ships

    International Nuclear Information System (INIS)

    Miller, Thomas M.; Patton, Bruce W.; Grogan, Brandon R.; Henkel, James J.; Murphy, Brian D.; Johnson, Jeffrey O.; Mihalczo, John T.

    2013-01-01

    In this work, several active interrogation (AI) sources are evaluated to determine their usefulness in detecting the presence of special nuclear material (SNM) in fishing trawlers, small cargo transport ships, and luxury yachts at large standoff distances from the AI source and detector. This evaluation is performed via computational analysis applying Monte Carlo methods with advanced variance reduction techniques. The goal is to determine the AI source strength required to detect the presence of SNM. The general conclusion of this study is that AI is not reliable when SNM is heavily shielded and not tightly coupled geometrically with the source and detector, to the point that AI should not be considered a via interrogation option in these scenarios. More specifically, when SNM is shielded by hydrogenous material large AI source strengths are required if detection is based on neutrons, which is not surprising. However, if the SNM is shielded by high-Z material the required AI source strengths are not significantly different if detection is based on neutrons or photons, which is somewhat surprising. Furthermore, some of the required AI source strengths that were calculated are very large. These results coupled with the realities of two ships moving independently at sea and other assumptions made during this analysis make the use of standoff AI in the maritime environment impractical

  19. Radiation portal monitor with "1"0B+ZnS(Ag) neutron detector performance for the detection of special nuclear materials

    International Nuclear Information System (INIS)

    Guzman G, K. A.; Gallego, E.; Lorente, A.; Ibanez F, S.; Vega C, H. R.; Gonzalez, J. A.; Mendez, R.

    2016-10-01

    In homeland security, neutron detection is used to prevent the smuggling of special nuclear materials. Thermal neutrons are normally detected with "3He proportional counters, in the radiation portal monitors, Rpms, however due to the "3He shortage new procedures are being studied. In this work Monte Carlo methods, using the MCNP6 code, have been used to study the neutron detection features of a "1"0B+ZnS(Ag) under real conditions inside of a Rpm. The performance for neutron detection was carried out for "2"5"2Cf, "2"3"8U and "2"3"9Pu under different conditions. In order to mimic an actual situation occurring at border areas, a sample of SNM sited inside a vehicle was simulated and the Rpm with "1"0B+ZnS(Ag) response was calculated. At 200 cm the "1"0B+ZnS(Ag) on Rpm response is close to 2.5 cps-ng "2"5"2Cf, when the "2"5"2Cf neutron source is shielded with 0.5 cm-thick lead and 2.5 cm-thick polyethylene fulfilling the ANSI recommendations. Three different geometries of neutron detectors of "1"0B+ZnS(Ag) in a neutron detection system in Rpm were modeled. Therefore, the "1"0B+ZnS(Ag) detectors are an innovative and viable replacement for the "3He detectors in the Rpm. (Author)

  20. Utilization of special computerized tomography and nuclear medicine techniques for quality control and for the optimization of combined precision chemotherapy and precision radiation therapy

    International Nuclear Information System (INIS)

    Wiley, A.L. Jr.; Wirtanen, G.W.; Chien, I.-C.

    1984-01-01

    A combination of precision (selective, intra-arterial) chemotherapy and precision radiotherapy can be used for advanced pancreatic, biliary tract, and sarcomatous malignancies. There were some remarkable responses, but also a few poor responses and even some morbidity. Accordingly, methods are developed of pre-selecting those patients whose tumors are likely to respond to such therapy, as well as methods for improving the therapeutic ratio by the rational optimization of combined therapy. Specifically, clinical tumor blood flow characteristics (monitored with nuclear medicine techniques) may provide useful criteria for such selection. The authors also evaluate qualitatively the drug distribution or exposure space with specialized color-coded computerized tomography images, which demonstrate spatially dependent enhancement of intra-arterial contrast in tumor and in adjacent normal tissues. Such clinical data can improve the quality control aspects of intra-arterial chemotherapy administration, as well as the possibility of achievement of a significant therapeutic ratio by the integration of precision chemotherapy and precision radiation therapy. (Auth.)