WorldWideScience

Sample records for identify special nuclear

  1. 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)

  2. 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

  3. 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.

  4. 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)

  5. 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)

  6. 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)

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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...

  12. 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

  13. 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

  14. 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.

  15. 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.

  16. 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

  17. Special Experts Meeting: Identifying and Overcoming Barriers to the Effective Consideration of Human and Organizational Factors in Event Analysis and Root Cause Analysis. Nuclear Energy Agency / Working Group on Human and Organizational Factors

    International Nuclear Information System (INIS)

    2011-01-01

    The main mission of the Nuclear Energy Agency (NEA) Working Group on Human and Organisational Factors (WGHOF) is to improve the understanding and treatment of human and organisational factors (HOF) within the nuclear industry in order to support the continued safety performance of nuclear installations and improve the effectiveness of regulatory practices in member countries. WGHOF developed a CSNI (Committee on the Safety of Nuclear Installations) Activity Proposal Sheet (CAPS) outlining the work and milestones necessary towards achieving the following objectives: - Identify barriers to analyzing and correctly identifying the Human and Organisational Factors (HOF) causes of events; - Identify barriers to implementing lessons learned from these analyses; and - Develop recommendations for overcoming these barriers to: improve the identification of HOF causes of events and support the successful implementation of appropriate corrective actions The CAPS can be found in Appendix A. The first activity under the plan was the development of a questionnaire. This was distributed to WGHOF members and their counterparts from the Working Group on Operating Experience (WGOE). The questionnaire was comprised of 20 questions based on the objectives of the CSNI Activity Proposed Sheet. The intended survey participants were licensees with previous experience conducting root cause analyses. Responses were received from 26 respondents from 11 different countries. The results of the questionnaire were analyzed to identify themes for further discussion during a specialist meeting planned for September 2009. The following themes were presented during the WGHOF meeting in March of 2009 and endorsed for further work: - Roles and Influence of Senior Management, - Skills and Knowledge of the Investigators, - Qualitative Nature of HOF, - Influence of the Regulator, - Systematic Approach to Investigation. A summary of the questionnaire responses is provided in Appendix B

  18. 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

  19. 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

  20. 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)

  1. 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)

  2. 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

  3. 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)

  4. 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

  5. 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...

  6. 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

  7. Identifying Special Operations as a Distinct Foreign Policy Instrument

    DEFF Research Database (Denmark)

    Johnsen, Anton Asklund

    2017-01-01

    to clarify and explain what special operations strategic qualities exactly are. The author then elaborates on specific elements of special operations with a point of departure in the “cognitive maps of SOF” as formulated in the research question. The author recommends that in order to influence policy...... on special operations, it is essential to have insight into the instrument’s capabilities and limitations, as this provides the prerequisites for sound contextual strategic analysis....

  8. 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

  9. 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

  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. 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...

  12. 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

  13. 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

  14. Application of artificial neural network to identify nuclear materials

    International Nuclear Information System (INIS)

    Xu Peng; Wang Zhe; Li Tiantuo

    2005-01-01

    Applying the neutral network, the article studied the technology of identifying the gamma spectra of the nuclear material in the nuclear components. In the article, theory of the network identifying the spectra is described, and the results of identification of gamma spectra are given.(authors)

  15. 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)

  16. 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)

  17. 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.

  18. Detecting and identifying underground nuclear explosions

    International Nuclear Information System (INIS)

    Spiliopoulos, S.

    1996-01-01

    The monitoring of underground nuclear explosions involves, first determining that the signals have originated from a test site and if so, then a pattern recognition analysis is undertaken to determine whether the signals originate from an explosion rather than an earthquake. In this we are aided by seismic observations of previous explosions from each test site. To determine the origin of a signal use is first made of the two seismic arrays in central Australia. Each of these arrays consists of 20 spatially separated sensors (seismometers), and each of which can provide a preliminary estimate of the location of the source. In practice this is done automatically by inserting delays into the output of each of the sensors to compensate for a seismic signal taking a finite time to cross the array, and then adding the output of each sensor to form what are called 'array beams'. When the correct delays for a particular azimuth and wavespeed (corresponding to a particular source location) have been inserted, the signals recorded by each sensor will be in phase and the energy in the array beam will be a maximum. Because the seismic background noise at each sensor is not correlated, this beam forming also improves the signal-to-noise ratio. In this sense a seismic array is equivalent to other arrays of sensors - e.g. a radar antenna. Having determined that a signal originates from somewhere near a test site a more precise location can be obtained from the times that the signal arrives at different seismic stations

  19. Detecting and identifying underground nuclear explosions

    Energy Technology Data Exchange (ETDEWEB)

    Spiliopoulos, S. [Australian Geological Survey Organisation, Anzac Park, Canberra, ACT (Australia). Department of Primary Industry

    1996-12-31

    The monitoring of underground nuclear explosions involves, first determining that the signals have originated from a test site and if so, then a pattern recognition analysis is undertaken to determine whether the signals originate from an explosion rather than an earthquake. In this we are aided by seismic observations of previous explosions from each test site. To determine the origin of a signal use is first made of the two seismic arrays in central Australia. Each of these arrays consists of 20 spatially separated sensors (seismometers), and each of which can provide a preliminary estimate of the location of the source. In practice this is done automatically by inserting delays into the output of each of the sensors to compensate for a seismic signal taking a finite time to cross the array, and then adding the output of each sensor to form what are called `array beams`. When the correct delays for a particular azimuth and wavespeed (corresponding to a particular source location) have been inserted, the signals recorded by each sensor will be in phase and the energy in the array beam will be a maximum. Because the seismic background noise at each sensor is not correlated, this beam forming also improves the signal-to-noise ratio. In this sense a seismic array is equivalent to other arrays of sensors - e.g. a radar antenna. Having determined that a signal originates from somewhere near a test site a more precise location can be obtained from the times that the signal arrives at different seismic stations

  20. 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

  1. 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

  2. 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)

  3. 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)

  4. 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)

  5. 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

  6. 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

  7. 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...

  8. 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.

  9. 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

  10. 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

  11. 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

  12. 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)

  13. 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.

  14. 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.)

  15. Virtual Reality and Its Potential Use in Special Education. Identifying Emerging Issues and Trends in Technology for Special Education.

    Science.gov (United States)

    Woodward, John

    As part of a 3-year study to identify emerging issues and trends in technology for special education, this paper addresses the possible contributions of virtual reality technology to educational services for students with disabilities. An example of the use of virtual reality in medical imaging introduces the paper and leads to a brief review of…

  16. 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

  17. 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)

  18. 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)

  19. 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)

  20. 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)

  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. 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

  6. 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.

  7. 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

  8. Nuclear techniques to identify allergenic metals in orthodontic brackets

    International Nuclear Information System (INIS)

    Zenobio, E.G.; Zenobio, M.A.F.; Menezes, M.A.B.C.

    2009-01-01

    The present study determines the elementary alloy composition of ten commercial brands of brackets, especially related to Ni, Cr, and Co metals, confirmed allergenic elements. The nuclear techniques applied in the analyses were X-ray fluorescence (XRF) - Centre National de la Recherche Scientifique, France (National Center of Scientific Research), and X-ray energy spectrometry (XRES), and Instrumental Neutron Activation Analysis (INAA) - CDTN/CNEN, Brazil. The XRES and XRF techniques identified Cr in the 10 samples analyzed and Ni in eight samples. The INAA technique identified the presence of Cr (14% to 19%) and Co (42% to 2400 ppm) in all samples. The semi-quantitative analysis performed by XRF also identified Co in two samples. The techniques were effective in the identification of metals in orthodontic brackets. The elements identified in this study can be considered one of the main reason for the allergic processes among the patients studied. This finding suggests that the patients should be tested for allergy and allergenic sensibility to metals prior to the prescription of orthodontic device. (author)

  9. 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.

  10. 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.

  11. 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

  12. 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...

  13. 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.

  14. 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

  15. 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

  16. 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

  17. 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

  18. 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

  19. 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)

  20. 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.

  1. 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

  2. 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

  3. 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.

  4. 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.

  5. 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...

  6. Guidance for identifying, reporting and tracking nuclear safety noncompliances

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    This document provides Department of Energy (DOE) contractors, subcontractors and suppliers with guidance in the effective use of DOE`s Price-Anderson nuclear safety Noncompliance Tracking System (NTS). Prompt contractor identification, reporting to DOE, and correction of nuclear safety noncompliances provides DOE with a basis to exercise enforcement discretion to mitigate civil penalties, and suspend the issuance of Notices of Violation for certain violations. Use of this reporting methodology is elective by contractors; however, this methodology is intended to reflect DOE`s philosophy on effective identification and reporting of nuclear safety noncompliances. To the extent that these expectations are met for particular noncompliances, DOE intends to appropriately exercise its enforcement discretion in considering whether, and to what extent, to undertake enforcement action.

  7. 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)

  8. 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

  9. 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.

  10. Interaction Profiling Identifies the Human Nuclear Exosome Targeting Complex

    DEFF Research Database (Denmark)

    Lubas, Michal Szymon; Christensen, Marianne Skovgaard; Kristiansen, Maiken Søndergaard

    2011-01-01

    from nucleoli, and consistently NEXT is specifically required for the exosomal degradation of promoter upstream transcripts (PROMPTs). We also detect putative homolog TRAMP subunits hTRF4-2 (Trf4p) and ZCCHC7 (Air2p) in hRRP6 and hMTR4 precipitates. However, at least ZCCHC7 function is restricted...... to nucleoli. Our results suggest that human nuclear exosome degradation pathways comprise modules of spatially organized cofactors that diverge from the yeast model....

  11. 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.

  12. 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

  13. 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.

  14. Identifying Understudied Nuclear Reactions by Text-mining the EXFOR Experimental Nuclear Reaction Library

    Energy Technology Data Exchange (ETDEWEB)

    Hirdt, J.A. [Department of Mathematics and Computer Science, St. Joseph' s College, Patchogue, NY 11772 (United States); Brown, D.A., E-mail: dbrown@bnl.gov [National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000 (United States)

    2016-01-15

    The EXFOR library contains the largest collection of experimental nuclear reaction data available as well as the data's bibliographic information and experimental details. We text-mined the REACTION and MONITOR fields of the ENTRYs in the EXFOR library in order to identify understudied reactions and quantities. Using the results of the text-mining, we created an undirected graph from the EXFOR datasets with each graph node representing a single reaction and quantity and graph links representing the various types of connections between these reactions and quantities. This graph is an abstract representation of the connections in EXFOR, similar to graphs of social networks, authorship networks, etc. We use various graph theoretical tools to identify important yet understudied reactions and quantities in EXFOR. Although we identified a few cross sections relevant for shielding applications and isotope production, mostly we identified charged particle fluence monitor cross sections. As a side effect of this work, we learn that our abstract graph is typical of other real-world graphs.

  15. Identifying Understudied Nuclear Reactions by Text-mining the EXFOR Experimental Nuclear Reaction Library

    International Nuclear Information System (INIS)

    Hirdt, J.A.; Brown, D.A.

    2016-01-01

    The EXFOR library contains the largest collection of experimental nuclear reaction data available as well as the data's bibliographic information and experimental details. We text-mined the REACTION and MONITOR fields of the ENTRYs in the EXFOR library in order to identify understudied reactions and quantities. Using the results of the text-mining, we created an undirected graph from the EXFOR datasets with each graph node representing a single reaction and quantity and graph links representing the various types of connections between these reactions and quantities. This graph is an abstract representation of the connections in EXFOR, similar to graphs of social networks, authorship networks, etc. We use various graph theoretical tools to identify important yet understudied reactions and quantities in EXFOR. Although we identified a few cross sections relevant for shielding applications and isotope production, mostly we identified charged particle fluence monitor cross sections. As a side effect of this work, we learn that our abstract graph is typical of other real-world graphs.

  16. 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)

  17. 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

  18. 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

  19. 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

  20. The regulatory framework of special medical group students' physical education: identifying the problem.

    Directory of Open Access Journals (Sweden)

    Mazur Valerij Anatol'evich

    2011-09-01

    Full Text Available The question of regulatory framework for special medical group students' physical education, and their physical condition in particular is elaborated. It is found that in the current program the identified question is missing, although the assessment of individual performance standards for the physical condition of the students was envisaged in the programs of 1977 and 1982. The need for such an assessment is indicated by the large number of Ukrainian and foreign pediatricians and specialists in therapeutic physical culture. At the same time the standards for assessing these indicators are not developed. It complicates the formation of positive motivation of students to regular classes, and does not promote their self-confidence, capabilities and effectiveness of monitoring the effectiveness of exercise in various forms. The findings suggest the need to define the optimal composition of the bulk of tests and functional tests to assess the physical condition of special medical group students with various diseases and to develop appropriate indicators for their evaluation standards.

  1. Identifying suitable piercement salt domes for nuclear waste storage sites

    International Nuclear Information System (INIS)

    Kehle, R.; e.

    1980-08-01

    Piercement salt domes of the northern interior salt basins of the Gulf of Mexico are being considered as permanent storage sites for both nuclear and chemically toxic wastes. The suitable domes are stable and inactive, having reached their final evolutionary configuration at least 30 million years ago. They are buried to depths far below the level to which erosion will penetrate during the prescribed storage period and are not subject to possible future reactivation. The salt cores of these domes are themselves impermeable, permitting neither the entry nor exit of ground water or other unwanted materials. In part, a stable dome may be recognized by its present geometric configuration, but conclusive proof depends on establishing its evolutionary state. The evolutionary state of a dome is obtained by reconstructing the growth history of the dome as revealed by the configuration of sedimentary strata in a large area (commonly 3,000 square miles or more) surrounding the dome. A high quality, multifold CDP reflection seismic profile across a candidate dome will provide much of the necessary information when integrated with available subsurface control. Additional seismic profiles may be required to confirm an apparent configuration of the surrounding strata and an interpreted evolutionary history. High frequency seismic data collected in the near vicinity of a dome are also needed as a supplement to the CDP data to permit accurate depiction of the configuration of shallow strata. Such data must be tied to shallow drill hole control to confirm the geologic age at which dome growth ceased. If it is determined that a dome reached a terminal configuration many millions of years ago, such a dome is incapable of reactivation and thus constitutes a stable storage site for nuclear wastes

  2. Reactive inspection response of NRC Region III to potential technical deficiencies identified in recent Nuclear Air Cleaning Conference papers

    International Nuclear Information System (INIS)

    Gill, C.F.

    1987-01-01

    In order to effectively meet its responsibility to protect the public health and safety, the Nuclear Regulatory Commission (NRC) nuclear power plant licensing and inspection programs respond to potential technical deficiencies identified by conference and professional society meeting papers when deemed appropriate. The NRC staff's response mechanisms for such technical deficiencies include: generic letters, Bulletins, Information Notices, Standard Review Plan (NUREG-0800) revisions, docketed Final Safety Analysis Report (FSAR) questions, special studies, special (reactive) inspection, and inspection program revisions. This paper describes reactive inspection efforts by Region III in response to potential technical deficiencies identified in recent air cleaning conference papers, including: post-accident effluent sample line deposition losses; failure to implement good engineering practices in the design, construction, and testing of Nuclear Air Treatment Systems (NATS); filter bypass via filter housing drain lines; spinster carbon degradation; use of silicone sealants and other temporary patching material in NATS; filter housing fire protection deluge system problems; lack of charcoal batch traceability; Quality Assurance records problems involving equipment, vendor, filter, and personnel qualifications; inadequate ANSI/ASME N510 acceptance criteria and tests; and failure to adequately demonstrate control room habitability per 10 CFR 50, Appendix A, General Design Criterion-19. Region III inspections indicate that many of these deficiencies appear to be prevalent. Inspection findings and utility responses to the findings are discussed. NRC Region III and Headquarters programmatic reactions to the identified generic problem areas are also discussed

  3. 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...

  4. 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

  5. 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

  6. 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

  7. 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...

  8. 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.

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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)

  15. 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

  16. 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.)

  17. 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

  18. 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

  19. 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

  20. Source and special nuclear material sealing and labeling requirements

    International Nuclear Information System (INIS)

    Jordan, K.N.

    1978-04-01

    Purpose of this document is to define requirements for the use of tamper-indicating seals and identifying labels on SS Material containers at Rockwell Hanford Operations. The requirements defined in this document are applicable to all Rockwell Hanford Operation employees involved in handling, processing, packaging, transferring, shipping, receiving or storing SS Material

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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)

  8. 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

  9. Principal-Identified Challenges, Needs, and Recommendations for Instructional Leadership in Special Education

    Science.gov (United States)

    Kraft, Rose A. Liddell

    2016-01-01

    The Individuals with Disabilities Education Improvement Act of 2004, and the No Child Left Behind Act of 2002, added instructional responsibilities for school principals specific to students with disabilities. However, these laws did not require additional training in special education policy or instruction for principals, despite the existence of…

  10. Students with Self-Identified Special Educational Needs and Disabilities (Si-SEND): Flourishing or Languishing!

    Science.gov (United States)

    Skrzypiec, Grace; Askell-Williams, Helen; Slee, Phillip; Rudzinski, Adrian

    2016-01-01

    Students' wellbeing is an essential component of their ability to function well, not only at school but also in all life domains. Many studies have investigated student wellbeing. However, empirical studies about the wellbeing of students with special educational needs and disabilities (SEND) are scarce. Furthermore, many studies have adopted a…

  11. Nuclear proliferomics: A new field of study to identify signatures of nuclear materials as demonstrated on alpha-UO3.

    Science.gov (United States)

    Schwerdt, Ian J; Brenkmann, Alexandria; Martinson, Sean; Albrecht, Brent D; Heffernan, Sean; Klosterman, Michael R; Kirkham, Trenton; Tasdizen, Tolga; McDonald Iv, Luther W

    2018-08-15

    The use of a limited set of signatures in nuclear forensics and nuclear safeguards may reduce the discriminating power for identifying unknown nuclear materials, or for verifying processing at existing facilities. Nuclear proliferomics is a proposed new field of study that advocates for the acquisition of large databases of nuclear material properties from a variety of analytical techniques. As demonstrated on a common uranium trioxide polymorph, α-UO 3 , in this paper, nuclear proliferomics increases the ability to improve confidence in identifying the processing history of nuclear materials. Specifically, α-UO 3 was investigated from the calcination of unwashed uranyl peroxide at 350, 400, 450, 500, and 550 °C in air. Scanning electron microscopy (SEM) images were acquired of the surface morphology, and distinct qualitative differences are presented between unwashed and washed uranyl peroxide, as well as the calcination products from the unwashed uranyl peroxide at the investigated temperatures. Differential scanning calorimetry (DSC), UV-Vis spectrophotometry, powder X-ray diffraction (p-XRD), and thermogravimetric analysis-mass spectrometry (TGA-MS) were used to understand the source of these morphological differences as a function of calcination temperature. Additionally, the SEM images were manually segmented using Morphological Analysis for MAterials (MAMA) software to identify quantifiable differences in morphology for three different surface features present on the unwashed uranyl peroxide calcination products. No single quantifiable signature was sufficient to discern all calcination temperatures with a high degree of confidence; therefore, advanced statistical analysis was performed to allow the combination of a number of quantitative signatures, with their associated uncertainties, to allow for complete discernment by calcination history. Furthermore, machine learning was applied to the acquired SEM images to demonstrate automated discernment with

  12. 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

  13. 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.

  14. 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

  15. 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

  16. 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)

  17. Utility of a summative scale based on the Children with Special Health Care Needs (CSHCN) Screener to identify CSHCN with special dental care needs.

    Science.gov (United States)

    Iida, Hiroko; Lewis, Charlotte W

    2012-08-01

    Our objective was to determine if a summative scale reflecting the number of positive criteria on the Children with Special Health Care Needs (CSHCN) Screener is useful in identifying subgroups of CSHCN at risk for poorer oral health and unmet dental care needs and who should be considered to have special dental care needs. Data were analyzed for a population-based sample of 91,642 US children needs in the past 12 months. Descriptive and multivariable logistic regression analyses were performed for each outcome using the survey command in Stata to account for the sampling design. A summative scale based on the number of positive CSHCN Screener criteria was independently associated with various parent-perceived poorer oral health outcomes in children. CSHCN who met 4 or 5 screener criteria had 4 and 4.5 times, respectively, the odds of having fair-poor condition of teeth and bleeding gums relative to non-CSHCN. They also had 87% higher odds for parent-perceived toothache and 2 and 2.5 times the odds of having recent broken teeth and unmet dental care needs relative to non-CSHCN, respectively. There was no dose-dependent association between summative number of positive CSHCN Screener criteria and reported cavities in children. Application of a summative score based on the CSHCN Screener has utility in identifying the CSHCN subgroup with special dental care needs.

  18. 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.

  19. 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.

  20. 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

  1. 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

  2. Methodology for identifying boundaries of systems important to safety in CANDU nuclear power plants

    International Nuclear Information System (INIS)

    Therrien, S.; Komljenovic, D.; Therrien, P.; Ruest, C.; Prevost, P.; Vaillancourt, R.

    2007-01-01

    This paper presents a methodology developed to identify the boundaries of the systems important to safety (SIS) at the Gentilly-2 Nuclear Power Plant (NPP), Hydro-Quebec. The SIS boundaries identification considers nuclear safety only. Components that are not identified as important to safety are systematically identified as related to safety. A global assessment process such as WANO/INPO AP-913 'Equipment Reliability Process' will be needed to implement adequate changes in the management rules of those components. The paper depicts results in applying the methodology to the Shutdown Systems 1 and 2 (SDS 1, 2), and to the Emergency Core Cooling System (ECCS). This validation process enabled fine tuning the methodology, performing a better estimate of the effort required to evaluate a system, and identifying components important to safety of these systems. (author)

  3. Drug and Alcohol Exposed Children: Implications for Special Education for Students Identified as Behaviorally Disordered.

    Science.gov (United States)

    Bauer, Anne M.

    1991-01-01

    This article reviews the literature on children prenatally exposed to drugs and alcohol, the potential impact on the educational and social services systems, and implications for programing for children identified as behaviorally disordered. (Author/JDD)

  4. 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

  5. A systematic method for identifying vital areas at complex nuclear facilities.

    Energy Technology Data Exchange (ETDEWEB)

    Beck, David Franklin; Hockert, John

    2005-05-01

    Identifying the areas to be protected is an important part of the development of measures for physical protection against sabotage at complex nuclear facilities. In June 1999, the International Atomic Energy Agency published INFCIRC/225/Rev.4, 'The Physical Protection of Nuclear Material and Nuclear Facilities.' This guidance recommends that 'Safety specialists, in close cooperation with physical protection specialists, should evaluate the consequences of malevolent acts, considered in the context of the State's design basis threat, to identify nuclear material, or the minimum complement of equipment, systems or devices to be protected against sabotage.' This report presents a structured, transparent approach for identifying the areas that contain this minimum complement of equipment, systems, and devices to be protected against sabotage that is applicable to complex nuclear facilities. The method builds upon safety analyses to develop sabotage fault trees that reflect sabotage scenarios that could cause unacceptable radiological consequences. The sabotage actions represented in the fault trees are linked to the areas from which they can be accomplished. The fault tree is then transformed (by negation) into its dual, the protection location tree, which reflects the sabotage actions that must be prevented in order to prevent unacceptable radiological consequences. The minimum path sets of this fault tree dual yield, through the area linkage, sets of areas, each of which contains nuclear material, or a minimum complement of equipment, systems or devices that, if protected, will prevent sabotage. This method also provides guidance for the selection of the minimum path set that permits optimization of the trade-offs among physical protection effectiveness, safety impact, cost and operational impact.

  6. Automated local bright feature image analysis of nuclear protein distribution identifies changes in tissue phenotype

    International Nuclear Information System (INIS)

    Knowles, David; Sudar, Damir; Bator, Carol; Bissell, Mina

    2006-01-01

    The organization of nuclear proteins is linked to cell and tissue phenotypes. When cells arrest proliferation, undergo apoptosis, or differentiate, the distribution of nuclear proteins changes. Conversely, forced alteration of the distribution of nuclear proteins modifies cell phenotype. Immunostaining and fluorescence microscopy have been critical for such findings. However, there is an increasing need for quantitative analysis of nuclear protein distribution to decipher epigenetic relationships between nuclear structure and cell phenotype, and to unravel the mechanisms linking nuclear structure and function. We have developed imaging methods to quantify the distribution of fluorescently-stained nuclear protein NuMA in different mammary phenotypes obtained using three-dimensional cell culture. Automated image segmentation of DAPI-stained nuclei was generated to isolate thousands of nuclei from three-dimensional confocal images. Prominent features of fluorescently-stained NuMA were detected using a novel local bright feature analysis technique, and their normalized spatial density calculated as a function of the distance from the nuclear perimeter to its center. The results revealed marked changes in the distribution of the density of NuMA bright features as non-neoplastic cells underwent phenotypically normal acinar morphogenesis. In contrast, we did not detect any reorganization of NuMA during the formation of tumor nodules by malignant cells. Importantly, the analysis also discriminated proliferating non-neoplastic cells from proliferating malignant cells, suggesting that these imaging methods are capable of identifying alterations linked not only to the proliferation status but also to the malignant character of cells. We believe that this quantitative analysis will have additional applications for classifying normal and pathological tissues

  7. Automated local bright feature image analysis of nuclear proteindistribution identifies changes in tissue phenotype

    Energy Technology Data Exchange (ETDEWEB)

    Knowles, David; Sudar, Damir; Bator, Carol; Bissell, Mina

    2006-02-01

    The organization of nuclear proteins is linked to cell and tissue phenotypes. When cells arrest proliferation, undergo apoptosis, or differentiate, the distribution of nuclear proteins changes. Conversely, forced alteration of the distribution of nuclear proteins modifies cell phenotype. Immunostaining and fluorescence microscopy have been critical for such findings. However, there is an increasing need for quantitative analysis of nuclear protein distribution to decipher epigenetic relationships between nuclear structure and cell phenotype, and to unravel the mechanisms linking nuclear structure and function. We have developed imaging methods to quantify the distribution of fluorescently-stained nuclear protein NuMA in different mammary phenotypes obtained using three-dimensional cell culture. Automated image segmentation of DAPI-stained nuclei was generated to isolate thousands of nuclei from three-dimensional confocal images. Prominent features of fluorescently-stained NuMA were detected using a novel local bright feature analysis technique, and their normalized spatial density calculated as a function of the distance from the nuclear perimeter to its center. The results revealed marked changes in the distribution of the density of NuMA bright features as non-neoplastic cells underwent phenotypically normal acinar morphogenesis. In contrast, we did not detect any reorganization of NuMA during the formation of tumor nodules by malignant cells. Importantly, the analysis also discriminated proliferating non-neoplastic cells from proliferating malignant cells, suggesting that these imaging methods are capable of identifying alterations linked not only to the proliferation status but also to the malignant character of cells. We believe that this quantitative analysis will have additional applications for classifying normal and pathological tissues.

  8. A digest of the Nuclear Safety Division report on the Fukushima Dai-ichi accident seminar (4). Issues identified by the accident

    International Nuclear Information System (INIS)

    Moriyama, Kumiaki; Abe, Kiyoharu

    2013-01-01

    AESJ Nuclear Safety Division published 'Report on the Fukushima Dai-ichi Accident Seminar - what was wrong and what should been down in future-' which would be published as five special articles of the AESJ journal. The Fukushima Dai-ichi accident identified issues of several activities directly related with nuclear safety in the areas of safety design, severe accident management and safety regulations. PRA, operational experiences and safety research could not always contribute safety assurance of nuclear power plant so much. This article (4) summarized technical issues based on related facts of the accident as much as possible and discussed' what was wrong and what should be down in future'. Important issues were identified from defense-in-depth philosophy and lessons learned on safety design were obtained from accident progression analysis. Activities against external events and continuous improvements of safety standards based on latest knowledge were most indispensable. Strong cooperation among experts in different areas was also needed. (T. Tanaka)

  9. Genome-Wide Analysis of PAPS1-Dependent Polyadenylation Identifies Novel Roles for Functionally Specialized Poly(A Polymerases in Arabidopsis thaliana.

    Directory of Open Access Journals (Sweden)

    Christian Kappel

    2015-08-01

    Full Text Available The poly(A tail at 3' ends of eukaryotic mRNAs promotes their nuclear export, stability and translational efficiency, and changes in its length can strongly impact gene expression. The Arabidopsis thaliana genome encodes three canonical nuclear poly(A polymerases, PAPS1, PAPS2 and PAPS4. As shown by their different mutant phenotypes, these three isoforms are functionally specialized, with PAPS1 modifying organ growth and suppressing a constitutive immune response. However, the molecular basis of this specialization is largely unknown. Here, we have estimated poly(A-tail lengths on a transcriptome-wide scale in wild-type and paps1 mutants. This identified categories of genes as particularly strongly affected in paps1 mutants, including genes encoding ribosomal proteins, cell-division factors and major carbohydrate-metabolic proteins. We experimentally verified two novel functions of PAPS1 in ribosome biogenesis and redox homoeostasis that were predicted based on the analysis of poly(A-tail length changes in paps1 mutants. When overlaying the PAPS1-dependent effects observed here with coexpression analysis based on independent microarray data, the two clusters of transcripts that are most closely coexpressed with PAPS1 show the strongest change in poly(A-tail length and transcript abundance in paps1 mutants in our analysis. This suggests that their coexpression reflects at least partly the preferential polyadenylation of these transcripts by PAPS1 versus the other two poly(A-polymerase isoforms. Thus, transcriptome-wide analysis of poly(A-tail lengths identifies novel biological functions and likely target transcripts for polyadenylation by PAPS1. Data integration with large-scale co-expression data suggests that changes in the relative activities of the isoforms are used as an endogenous mechanism to co-ordinately modulate plant gene expression.

  10. 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...

  11. 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.

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  17. 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

  18. Using geographic information systems to identify prospective marketing areas for a special library.

    Science.gov (United States)

    McConnaughy, Rozalynd P; Wilson, Steven P

    2006-05-04

    The Center for Disability Resources (CDR) Library is the largest collection of its kind in the Southeastern United States, consisting of over 5,200 books, videos/DVDs, brochures, and audiotapes covering a variety of disability-related topics, from autism to transition resources. The purpose of the library is to support the information needs of families, faculty, students, staff, and other professionals in South Carolina working with individuals with disabilities. The CDR Library is funded on a yearly basis; therefore, maintaining high usage is crucial. A variety of promotional efforts have been used to attract new patrons to the library. Anyone in South Carolina can check out materials from the library, and most of the patrons use the library remotely by requesting materials, which are then mailed to them. The goal of this project was to identify areas of low geographic usage as a means of identifying locations for future library marketing efforts. Nearly four years worth of library statistics were compiled in a spreadsheet that provided information per county on the number of checkouts, the number of renewals, and the population. Five maps were created using ArcView GIS software to create visual representations of patron checkout and renewal behavior per county. Out of the 46 counties in South Carolina, eight counties never checked out materials from the library. As expected urban areas and counties near the library's physical location have high usage totals. The visual representation of the data made identification of low usage regions easier than using a standalone database with no visual-spatial component. The low usage counties will be the focus of future Center for Disability Resources Library marketing efforts. Due to the impressive visual-spatial representations created with Geographic Information Systems, which more efficiently communicate information than stand-alone database information can, librarians may benefit from the software's use as a

  19. 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

  20. 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.

  1. 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

  2. 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

  3. 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

    -2050. Service sector in India accounts for about 50% of GDP which will continue to increase further and will provide more jobs and better paid jobs than core industries and there will be continued shift of choice of employment towards service sector creating deep gap of manpower resource requirement in basic and core industries. There are reports that some countries may have to abandon some future projects because of non availability skilled manpower in core industries. The installed capacity of nuclear power in India in the year 2052 will be about 200 G We from the present about 4 G We which will be a manifold increase. This will need about estimated 1,30,000 skilled manpower from the present about 12,000 persons in nuclear industries. Moreover, the need for competent persons in nuclear industries because of high safety requirements of nuclear installations will further add to the problem. The following short-term strategies to retain and attract new employees in nuclear industries may be envisaged amongst others: - Recruit employees prior to the departure of experienced technical staff to facilitate knowledge transfer in time. - Increase compensation and the number of higher level positions. - Increase permanent entry-level intake of skilled manpower taking into account historical turn-over rate. - Implement attractive student loan repayment programs by tying up with banks and financial institutions. - Implement well researched strategies and measures including reassessing the practical capacity which nations including India can achieve in power generation in future taking practical aspects of manpower shortage. - Implement advanced technology which requires lesser manpower. - Implement higher level of automation in nuclear industries. The paper aims to highlight the acute problems of future manpower shortages in nuclear industries globally with special reference to India and discusses some remedial measures which may be taken to address the issue. (author)

  4. Using the simplified case mix tool (sCMT) to identify cost in special care dental services to support commissioning.

    Science.gov (United States)

    Duane, B G; Freeman, R; Richards, D; Crosbie, S; Patel, P; White, S; Humphris, G

    2017-03-01

    To commission dental services for vulnerable (special care) patient groups effectively, consistently and fairly an evidence base is needed of the costs involved. The simplified Case Mixed Tool (sCMT) can assess treatment mode complexity for these patient groups. To determine if the sCMT can be used to identify costs of service provision. Patients (n=495) attending the Sussex Community NHS Trust Special Care Dental Service for care were assessed using the sCMT. sCMT score and costs (staffing, laboratory fees, etc.) besides patient age, whether a new patient and use of general anaesthetic/intravenous sedation. Statistical analysis (adjusted linear regression modelling) compared sCMT score and costs then sensitivity analyses of the costings to age, being a new patient and sedation use were undertaken. Regression tables were produced to present estimates of service costs. Costs increased with sCMT total scale and single item values in a predictable manner in all analyses except for 'cooperation'. Costs increased with the use of IV sedation; with each rising level of the sCMT, and with complexity in every sCMT category, except cooperation. Costs increased with increase in complexity of treatment mode as measured by sCMT scores. Measures such as the sCMT can provide predictions of the resource allocations required when commissioning special care dental services. Copyright© 2017 Dennis Barber Ltd.

  5. 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.)

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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)

  13. 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)

  14. Best practices in identifying, reporting and screening operating experience at nuclear power plants

    International Nuclear Information System (INIS)

    2008-03-01

    IAEA Safety Standards Series No. SF-1 entitled Fundamental Safety Principles: Safety Fundamentals states the need for operating organizations to establish a programme for the collection and analysis of operating experience in nuclear power plants. Such a programme ensures that operating experience is analysed, events important to safety are reviewed in depth, lessons learned are disseminated to the staff of the organization and to relevant national and international organizations, and corrective actions are effectively implemented. This publication has been developed to provide advice and assistance to nuclear installations, and related institutions including contractors and support organizations to strengthen and enhance their own feedback process through the implementation of best practices in identifying, reporting and screening processes and to assess the effectiveness of the above areas. To support a proactive safety management approach the nuclear installations are enhancing the operating experience feedback (OEF) processes. For this purpose, the nuclear industry is striving to collect more information on occurrences that are useful to address the early signs of declining performance and improve operational safety performance. In this environment a strong reporting culture that motivates people to identify and report issues is an important attribute. As a consequence, the number and diversity of issues identified increases, and there is a need to set thresholds of screening for further treatment. Thus, the establishment of an effective identification, reporting and screening process is very beneficial to streamline the efforts, and ensure that major incidents and latent weaknesses are being addressed and that operating experience is treated according to its significance. This leads to improved safety and production. This publication was written to complement the publication IAEA Services Series No. 10 - PROSPER Guidelines - Guidelines for Peer Review and for

  15. Identifying and training non-technical skills of nuclear emergency response teams

    International Nuclear Information System (INIS)

    Crichton, M.T.; Flin, R.

    2004-01-01

    Training of the non-technical (social and cognitive) skills that are crucial to safe and effective management by teams in emergency situations is an issue that is receiving increasing emphasis in many organisations, particularly in the nuclear power industry. As teams play a major role in emergency response organisations (ERO), effective functioning and interactions within, between and across teams is crucial, particularly as the management of an emergency situation often requires that teams are extended by members from various other sections and strategic groups throughout the company, as well as members of external agencies. A series of interviews was recently conducted with members of a UK nuclear emergency response organisation to identify the non-technical skills required by team members that would be required for managing an emergency. Critical skills have been identified as decision making and situation assessment, as well as communication, teamwork, and stress management. A number of training strategies are discussed which can be tailored to the roles and responsibilities of the team members and the team leader, based on the roles within the team being defined as either Decision Maker, Evaluator, or Implementor, according to Nuclear Energy Institute (NEI) classifications. It is anticipated that enhanced learning of the necessary non-technical skills, through experience and directed practice, will improve the skills of members of emergency response teams

  16. Identifying and training non-technical skills of nuclear emergency response teams

    Energy Technology Data Exchange (ETDEWEB)

    Crichton, M.T. E-mail: m.crichton@abdn.ac.uk; Flin, R

    2004-08-01

    Training of the non-technical (social and cognitive) skills that are crucial to safe and effective management by teams in emergency situations is an issue that is receiving increasing emphasis in many organisations, particularly in the nuclear power industry. As teams play a major role in emergency response organisations (ERO), effective functioning and interactions within, between and across teams is crucial, particularly as the management of an emergency situation often requires that teams are extended by members from various other sections and strategic groups throughout the company, as well as members of external agencies. A series of interviews was recently conducted with members of a UK nuclear emergency response organisation to identify the non-technical skills required by team members that would be required for managing an emergency. Critical skills have been identified as decision making and situation assessment, as well as communication, teamwork, and stress management. A number of training strategies are discussed which can be tailored to the roles and responsibilities of the team members and the team leader, based on the roles within the team being defined as either Decision Maker, Evaluator, or Implementor, according to Nuclear Energy Institute (NEI) classifications. It is anticipated that enhanced learning of the necessary non-technical skills, through experience and directed practice, will improve the skills of members of emergency response teams.

  17. 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.

  18. 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

  19. 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)

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. Identifying nuclear power plant transients using the Discrete Binary Artificial Bee Colony (DBABC) algorithm

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Iona M.S. de; Schirru, Roberto, E-mail: ioliveira@con.ufrj.br, E-mail: schirru@lmp.ufrj.br [Coordenacoa dos Programas de Pos-Graduacao em Engenharia (UFRJ/PEN/COPPE), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2011-07-01

    The identification of possible transients in a nuclear power plant is a highly relevant problem. This is mainly due to the fact that the operation of a nuclear power plant involves a large number of state variables whose behaviors are extremely dynamic. In risk situations, besides the huge cognitive overload that operators are submitted to, there is also the problem related with the considerable decrease in the effective time for correct decision making. To minimize these problems and help operators to make the corrective actions in due time, this paper presents a new contribution in this area and introduces an experimental transient identification system based exclusively on the abilities of the Discrete Binary Artificial Bee Colony (DBABC) algorithm to find the best centroid positions that correctly identifies a transient in a nuclear power plant. The DBABC is a reworking of the Artificial Bee Colony (ABC) algorithm which presents the advantage of operating in both continuous and discrete search spaces. Through the analysis of experimental results, the effective performance of the proposed DBABC algorithm is shown against some well known best performing algorithms from the literature. (author)

  7. Identifying nuclear power plant transients using the Discrete Binary Artificial Bee Colony (DBABC) algorithm

    International Nuclear Information System (INIS)

    Oliveira, Iona M.S. de; Schirru, Roberto

    2011-01-01

    The identification of possible transients in a nuclear power plant is a highly relevant problem. This is mainly due to the fact that the operation of a nuclear power plant involves a large number of state variables whose behaviors are extremely dynamic. In risk situations, besides the huge cognitive overload that operators are submitted to, there is also the problem related with the considerable decrease in the effective time for correct decision making. To minimize these problems and help operators to make the corrective actions in due time, this paper presents a new contribution in this area and introduces an experimental transient identification system based exclusively on the abilities of the Discrete Binary Artificial Bee Colony (DBABC) algorithm to find the best centroid positions that correctly identifies a transient in a nuclear power plant. The DBABC is a reworking of the Artificial Bee Colony (ABC) algorithm which presents the advantage of operating in both continuous and discrete search spaces. Through the analysis of experimental results, the effective performance of the proposed DBABC algorithm is shown against some well known best performing algorithms from the literature. (author)

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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.

  14. 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.

  15. 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.

  16. 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.)

  17. 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...

  18. Development of the language subtest in a developmental assessment scale to identify Chinese preschool children with special needs.

    Science.gov (United States)

    Wong, Anita M-Y; Leung, Cynthia; Siu, Elaine K-L; Lam, Catherine C-C; Chan, Grace P-S

    2011-01-01

    This study reports on the development of the language subtest in the Preschool Developmental Assessment Scale (PDAS) for Cantonese-Chinese speaking children. A pilot pool of 158 items covering the two language modalities and the three language domains was developed. This initial item set was subsequently revised based on Rasch analyses of data from 324 multi-stage randomly selected children between 3 and 6 years of age. The revised 106-item set demonstrated adequate measurement properties, including targeting and uni-dimensionality. The revised 106-item set successfully discriminated preschool children in the three age groups, and between preschool children and their age peers with special education needs (SEN). Results from this study support the collection of normative data from a larger population sample of children to examine its accuracy in identifying language impairment in children with SEN. Test development procedures reported in this study provide insight for the development of language subtests in multi-domain developmental assessment tools for children speaking other varieties of Chinese. Copyright © 2010 Elsevier Ltd. All rights reserved.

  19. 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

  20. 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.

  1. 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.

  2. 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

  3. 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

  4. 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.

  5. Identifying Issues in Applying Integrated Project Delivery to Domestic Nuclear Power Plant Construction Projects

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Joo [Korean Nuclear Society, Daejeon (Korea, Republic of)

    2016-05-15

    Integrated Project Delivery (IPD) is defined as that people, systems, business structures, and practices of key stakeholders are incorporated into a single-team, with a single process, which executes a project in a way of optimizing the project's outcome, increasing values delivered to the end user, reducing waste, and maximizing efficiency throughout the phases of engineering to construction. The researcher had carried out literature review in terms of IPD to identify major characteristics of IPD which are presented in the following section and had compared such characteristics against peculiarities of nuclear power plant (NPP) construction projects in order to shed light on obstacles in possible application of IPD method to domestic NPP construction projects in the coming days. In this research, three (3) major characteristics of IPD were identified: 1) key stakeholders signing one balanced contract, forming de facto one body, sharing risk and reward 2) an integrated project team being formed in the early stage of a project and providing input to minimize time and cost loss from rework downstream 3) team members co-locating, having open and direct communication, making decisions on time, and pursuing the success of the project itself.

  6. A decision support system for identifying abnormal operating procedures in a nuclear power plant

    International Nuclear Information System (INIS)

    Hsieh, Min-Han; Hwang, Sheue-Ling; Liu, Kang-Hong; Liang, Sheau-Farn Max; Chuang, Chang-Fu

    2012-01-01

    Highlights: ► A decision support system has been constructed and verified. ► The operator's decision-making time was decreased by about 25%. ► The accuracy was increased by about 18%. ► The system prevents overlooking important information. ► Fewer erroneous solutions were implemented, and the mental workload was reduced. - Abstract: In order to prevent safety hazards that can result from inappropriate decisions made by the operators of a nuclear power plant (NPP), this study was undertaken to develop a decision support system to reduce the complexity of the decision-making process by aiding operators’ cognitive activities, integrating unusual symptoms, and identifying the most suitable abnormal operating procedure (AOP) for operators. The study was conducted from the perspective of human factors engineering in order to compare the process that operators originally used to select an AOP with a process that included a support system for AOP identification. The results of the study indicated that the existence of a support system reduces errors by quickly suggesting likely AOPs. With such a support system in place, there were clear improvements in human performance, i.e., decision-making time decreased by about 25%, and the accuracy of the operators’ decisions, judged by the successful resolution of specific problems, increased by about 18%. In addition, there were fewer erroneous solutions implemented, and the mental workload was reduced. Hence, the decision support system is proposed as a training tool in identifying AOPs in the main control room (MCR).

  7. H-1 Nuclear Magnetic Resonance Metabolomics Analysis Identifies Novel Urinary Biomarkers for Lung Function

    International Nuclear Information System (INIS)

    McClay, Joseph L.; Adkins, Daniel E.; Isern, Nancy G.; O'Connell, Thomas M.; Wooten, Jan B.; Zedler, Barbara K.; Dasika, Madhukar S.; Webb, B.T.; Webb-Robertson, Bobbie-Jo M.; Pounds, Joel G.; Murrelle, Edward L.; Leppert, Mark F.; van den Oord, Edwin J.

    2010-01-01

    Chronic obstructive pulmonary disease (COPD), characterized by chronic airflow limitation, is a serious and growing public health concern. The major environmental risk factor for COPD is tobacco smoking, but the biological mechanisms underlying COPD are not well understood. In this study, we used proton nuclear magnetic resonance (1H-NMR) spectroscopy to identify and quantify metabolites associated with lung function in COPD. Plasma and urine were collected from 197 adults with COPD and from 195 adults without COPD. Samples were assayed using a 600 MHz NMR spectrometer, and the resulting spectra were analyzed against quantitative spirometric measures of lung function. After correcting for false discoveries and adjusting for covariates (sex, age, smoking) several spectral regions in urine were found to be significantly associated with baseline lung function. These regions correspond to the metabolites trigonelline, hippurate and formate. Concentrations of each metabolite, standardized to urinary creatinine, were associated with baseline lung function (minimum p-value = 0.0002 for trigonelline). No significant associations were found with plasma metabolites. Two of the three urinary metabolites positively associated with baseline lung function, i.e. hippurate and formate, are often related to gut microflora. This suggests that the microbiome composition is variable between individuals with different lung function. Alternatively, the nature and origins of all three associated metabolites may reflect lifestyle differences affecting overall health. Our results will require replication and validation, but demonstrate the utility of NMR metabolomics as a screening tool for identifying novel biomarkers of lung disease or disease risk.

  8. A computational technique to identify the optimal stiffness matrix for a discrete nuclear fuel assembly model

    International Nuclear Information System (INIS)

    Park, Nam-Gyu; Kim, Kyoung-Joo; Kim, Kyoung-Hong; Suh, Jung-Min

    2013-01-01

    Highlights: ► An identification method of the optimal stiffness matrix for a fuel assembly structure is discussed. ► The least squares optimization method is introduced, and a closed form solution of the problem is derived. ► The method can be expanded to the system with the limited number of modes. ► Identification error due to the perturbed mode shape matrix is analyzed. ► Verification examples show that the proposed procedure leads to a reliable solution. -- Abstract: A reactor core structural model which is used to evaluate the structural integrity of the core contains nuclear fuel assembly models. Since the reactor core consists of many nuclear fuel assemblies, the use of a refined fuel assembly model leads to a considerable amount of computing time for performing nonlinear analyses such as the prediction of seismic induced vibration behaviors. The computational time could be reduced by replacing the detailed fuel assembly model with a simplified model that has fewer degrees of freedom, but the dynamic characteristics of the detailed model must be maintained in the simplified model. Such a model based on an optimal design method is proposed in this paper. That is, when a mass matrix and a mode shape matrix are given, the optimal stiffness matrix of a discrete fuel assembly model can be estimated by applying the least squares minimization method. The verification of the method is completed by comparing test results and simulation results. This paper shows that the simplified model's dynamic behaviors are quite similar to experimental results and that the suggested method is suitable for identifying reliable mathematical model for fuel assemblies

  9. 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

  10. 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

  11. 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)

  12. 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

  13. 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

  14. 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

  15. EpCAM nuclear localization identifies aggressive Thyroid Cancer and is a marker for poor prognosis

    Directory of Open Access Journals (Sweden)

    MacMillan Christina

    2010-06-01

    Full Text Available Abstract Background Proteolytic cleavage of the extracellular domain (EpEx of Epithelial cell adhesion molecule (EpCAM and nuclear signaling by its intracellular oncogenic domain Ep-ICD has recently been implicated in increased proliferation of cancer cells. The clinical significance of Ep-ICD in human tumors remains an enigma. Methods EpEx, Ep-ICD and β-catenin immunohistochemistry using specific antibodies was conducted on 58 archived thyroid cancer (TC tissue blocks from 34 patients and correlated with survival analysis of these patients for up to 17 years. Results The anaplastic (ATC and aggressive thyroid cancers showed loss of EpEx and increased nuclear and cytoplasmic accumulation of Ep-ICD. In contrast, the low grade papillary thyroid cancers (PTC showed membranous EpEx and no detectable nuclear Ep-ICD. The ATC also showed concomitant nuclear expression of Ep-ICD and β-catenin. Kaplan-Meier Survival analysis revealed reduced overall survival (OS for TC patients showing nuclear Ep-ICD expression or loss of membranous EpEx (p Conclusion We report reciprocal loss of membrane EpEx but increased nuclear and cytoplasmic accumulation of Ep-ICD in aggressive TC; nuclear Ep-ICD correlated with poor OS of TC patients. Thus nuclear Ep-ICD localization may serve as a useful biomarker for aggressive TC and may represent a novel diagnostic, prognostic and therapeutic target for aggressive TC.

  16. 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.

  17. 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.

  18. 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.

  19. 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

  20. 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...

  1. 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.

  2. Nuclear terrorism: Identifying and combating the risks. International conference on nuclear security, 16 March 2005, London, UK

    International Nuclear Information System (INIS)

    ElBaradei, M.

    2005-01-01

    Security strategies, for many centuries, have been based on boundaries: the strategic placement of cities and borders to take advantage of natural barriers; defences that relied on walls, trenches and armadas; and the use of ethnic, religious or other groupings to distinguish friend from foe. In the 20th Century, the advent of airplanes, submarines and ballistic missiles began to undermine this approach to security by enabling the remote delivery of destruction on a scale previously not envisioned. But the change that has altered the international security landscape the most drastically is, in fact, globalization. The global community has become interdependent, with the constant movement of people, ideas and goods. Many aspects of modern life, communication, the global marketplace and, most recently, the rise in international terrorism - clearly indicate that our understanding of and approaches to national and international security must be adjusted, in keeping with new realities. This statement discusses: Nuclear Security and the Protection Against Nuclear Terrorism, IAEA Nuclear Security Plan of Activities founded on measures to guard against thefts of nuclear and other radioactive material and to protect related facilities against malicious acts; cooperation with other organizations and efforts

  3. EpCAM nuclear localization identifies aggressive Thyroid Cancer and is a marker for poor prognosis

    International Nuclear Information System (INIS)

    Ralhan, Ranju; Cao, Jun; Lim, Terence; MacMillan, Christina; Freeman, Jeremy L; Walfish, Paul G

    2010-01-01

    Proteolytic cleavage of the extracellular domain (EpEx) of Epithelial cell adhesion molecule (EpCAM) and nuclear signaling by its intracellular oncogenic domain Ep-ICD has recently been implicated in increased proliferation of cancer cells. The clinical significance of Ep-ICD in human tumors remains an enigma. EpEx, Ep-ICD and β-catenin immunohistochemistry using specific antibodies was conducted on 58 archived thyroid cancer (TC) tissue blocks from 34 patients and correlated with survival analysis of these patients for up to 17 years. The anaplastic (ATC) and aggressive thyroid cancers showed loss of EpEx and increased nuclear and cytoplasmic accumulation of Ep-ICD. In contrast, the low grade papillary thyroid cancers (PTC) showed membranous EpEx and no detectable nuclear Ep-ICD. The ATC also showed concomitant nuclear expression of Ep-ICD and β-catenin. Kaplan-Meier Survival analysis revealed reduced overall survival (OS) for TC patients showing nuclear Ep-ICD expression or loss of membranous EpEx (p < 0.0004), median OS = 5 months as compared to 198 months for patients who did not show nuclear Ep-ICD or demonstrated only membranous EpE. We report reciprocal loss of membrane EpEx but increased nuclear and cytoplasmic accumulation of Ep-ICD in aggressive TC; nuclear Ep-ICD correlated with poor OS of TC patients. Thus nuclear Ep-ICD localization may serve as a useful biomarker for aggressive TC and may represent a novel diagnostic, prognostic and therapeutic target for aggressive TC

  4. 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

  5. Pre-Service Teachers' Perceptions on Procedures to Identify and Assess Children with Special Educational Needs and Disabilities: The Case of Tutors of Colleges of Education in Ghana

    Science.gov (United States)

    Gyimah, Emmanuel Kofi; Amoako, R.

    2016-01-01

    The study aimed at exploring the perceptions tutors in Colleges of Education have on how the Colleges of Education Curriculum adequately prepare pre-service teachers to enable them to identify and assess children with special educational needs and disabilities for effective inclusive education in Ghana. A descriptive survey design was adopted and…

  6. 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.

  7. 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

  8. 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.

  9. 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

  10. 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

  11. 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.

  12. 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

  13. 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.

  14. 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.)

  15. 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)

  16. 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...

  17. 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)

  18. 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

  19. 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.

  20. 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)

  1. 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

  2. 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

  3. Using operating experience and a cause coding tree to identify improvements for nuclear process control

    International Nuclear Information System (INIS)

    Paradies, M.W.; Busch, D.A.

    1987-01-01

    This paper outlines a systematic approach to identification of the root causes of incidents and the use of that information to improve nuclear plant process control. The paper describes how the system was developed, how the system is used, and how the system has been accepted

  4. Proteomics approach to identify dehydration responsive nuclear proteins from chickpea (Cicer arietinum L.).

    Science.gov (United States)

    Pandey, Aarti; Chakraborty, Subhra; Datta, Asis; Chakraborty, Niranjan

    2008-01-01

    Dehydration or water-deficit is one of the most important environmental stress factors that greatly influences plant growth and development and limits crop productivity. Plants respond and adapt to such stress by altering their cellular metabolism and activating various defense machineries. Mechanisms that operate signal perception, transduction, and downstream regulatory events provide valuable information about the underlying pathways involved in environmental stress responses. The nuclear proteins constitute a highly organized, complex network that plays diverse roles during cellular development and other physiological processes. To gain a better understanding of dehydration response in plants, we have developed a comparative nuclear proteome in a food legume, chickpea (Cicer arietinum L.). Three-week-old chickpea seedlings were subjected to progressive dehydration by withdrawing water and the changes in the nuclear proteome were examined using two-dimensional gel electrophoresis. Approximately 205 protein spots were found to be differentially regulated under dehydration. Mass spectrometry analysis allowed the identification of 147 differentially expressed proteins, presumably involved in a variety of functions including gene transcription and replication, molecular chaperones, cell signaling, and chromatin remodeling. The dehydration responsive nuclear proteome of chickpea revealed a coordinated response, which involves both the regulatory as well as the functional proteins. This study, for the first time, provides an insight into the complex metabolic network operating in the nucleus during dehydration.

  5. 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.

  6. 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

  7. 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.)

  8. 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

  9. Characterizing nuclear and mitochondrial DNA in spent embryo culture media: genetic contamination identified.

    Science.gov (United States)

    Hammond, Elizabeth R; McGillivray, Brent C; Wicker, Sophie M; Peek, John C; Shelling, Andrew N; Stone, Peter; Chamley, Larry W; Cree, Lynsey M

    2017-01-01

    To characterize nuclear and mitochondrial DNA (mtDNA) in spent culture media from normally developing blastocysts to determine whether it could be used for noninvasive genetic assessment. Prospective embryo cohort study. Academic center and private in vitro fertilization (IVF) clinic. Seventy patients undergoing intracytoplasmic sperm injection (ICSI) and 227 blastocysts. Culture media assessment, artificial blastocoele fluid collapse and DNA analysis using digital polymerase chain reaction (dPCR), long-range PCR, quantitative PCR (qPCR), and DNA fingerprinting. Presence of nuclear and mtDNA in three different commercial culture media from Vitrolife and Irvine Scientific, spent embryo media assessment at the cleavage and blastocyst stages of development, and analysis of the internal media controls for each patient that had been exposed to identical conditions as embryo media but did not come into contact with embryos. Higher levels of nuclear and mtDNA were observed in the culture media that had been exposed to embryos compared with the internal media controls. Nuclear DNA (∼4 copies) and mtDNA (∼600 copies) could be detected in spent media, and the levels increased at the blastocyst stage. No increase in DNA was detected after artificial blastocoele fluid collapse. Mixed sex chromosome DNA was detected. This originated from contamination in the culture media and from maternal (cumulus) cells. Due to the limited amount of template, the presence of embryonic nuclear DNA could not be confirmed by DNA fingerprinting analysis. Currently DNA from culture media cannot be used for genetic assessment because embryo-associated structures release DNA into the culture medium and the DNA is of mixed origin. Copyright © 2016 American Society for Reproductive Medicine. Published by Elsevier Inc. All rights reserved.

  10. 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

  11. 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...

  12. 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

  13. Are the special educational needs of children in their first year in primary school in Ireland being identified: a cross-sectional study.

    Science.gov (United States)

    Curtin, Margaret; Baker, Denise; Staines, Anthony; Perry, Ivan J

    2014-02-19

    If the window of opportunity presented by the early years is missed, it becomes increasingly difficult to create a successful life-course. A biopsychosocial model of special educational need with an emphasis on participation and functioning moves the frame of reference from the clinic to the school and the focus from specific conditions to creating supportive environments cognisant of the needs of all children. However, evidence suggests that an emphasis on diagnosed conditions persists and that the needs of children who do not meet these criteria are not identified.The Early Development Instrument (EDI) is a well-validated, teacher-completed population-level measure of five domains of child development. It is uniquely placed, at the interface between health and education, to explore the developmental status of children with additional challenges within a typically developing population. The aim of this study was to examine the extent to which the special educational needs of children in their first year of formal education have been identified. This cross-sectional study was conducted in Ireland in 2011. EDI (teacher completed) scores were calculated for 1344 children. Data were also collected on special needs and on children identified by the teacher as needing assessment. Mean developmental scores were compared using one-way ANOVA. Eighty-three children in the sample population (6.2%) had identified special educational needs. A further 132 children were judged by the teacher as needing assessment. Children with special needs had lower mean scores than typically developing children, in all five developmental domains. Children considered by the teacher as needing assessment also had lower scores, which were not significantly different from those of children with special needs. Speech, emotional or behavioural difficulties were the most commonly reported problems among children needing further assessment. There was also a social gradient among this group. A small

  14. Use of neural networks to identify transient operating conditions in nuclear power plants

    International Nuclear Information System (INIS)

    Uhrig, R.E.; Guo, Z.

    1989-01-01

    A technique using neural networks as a means of diagnosing specific abnormal conditions or problems in nuclear power plants is investigated and found to be feasible. The technique is based on the fact that each physical state of the plant can be represented by a unique pattern of instrument readings, which can be related to the condition of the plant. Neural networks are used to relate this pattern to the fault or problem. 3 refs., 2 figs., 4 tabs

  15. Synergy in the areas of NPP nuclear safety and nuclear security

    International Nuclear Information System (INIS)

    Dybach, A.M.; Kuzmyak, I.Ya.; Kukhotskij, A.V.

    2013-01-01

    The paper considers the question of synergy between nuclear safety and nuclear security. Special attention is paid to identifying interface of the two areas of safety and definition of common principles for nuclear security and nuclear safety measures. The principles of defense in depth, safety culture and graded approach are analyzed in detail.Specific features characteristic of nuclear safety and security are outlined

  16. 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.)

  17. 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

  18. 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.

  19. 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

  20. 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

  1. 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)

  2. Neural signal processing for identifying failed fuel rods in nuclear reactors

    International Nuclear Information System (INIS)

    Seixas, Jose M. de; Soares Filho, William; Pereira, Wagner C.A.; Teles, Claudio C.B.

    2002-01-01

    Ultrasonic pulses were used for automatic detection of failed nuclear fuel rods. For experimental tests of the proposed method, an assembly prototype of 16 x 16 rods was built by using genuine rods but without fuel inside (just air). Some rods were partially filled with water to simulate cracked rods. Using neural signal processing on the received echoes of the emitted ultrasonic pulses, a detection efficiency of 97% was obtained. Neural detection is shown to outperform other classical discriminating methods and can also reveal important features of the signal structure of the received echoes. (author)

  3. 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)

  4. 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

  5. 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)

  6. 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

  7. 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)

  8. Developing a program to identify and track corrosion in nuclear plant raw water systems

    International Nuclear Information System (INIS)

    Spires PE, G.V.; Pickles PE, S.B.

    2001-01-01

    Findings derived from a comprehensive plant performance survey at Ontario Power Generation's (OPG) nuclear units convinced management that it would be prudent to expand the ongoing power piping Flow Accelerated Corrosion (FAC) induced wall thinning base-lining and tracking program to encompass the raw cooling water systems as well. Such systems are subject to a distinctly different class of pipe wall thinning (PWT) mechanisms than the FAC that degrades high-energy power piping. This paper describes the PWT corrosion assessment and tracking program that has been developed and is currently being implemented by OPG for the raw cooling water (i.e., Service Water) systems within it's nuclear generating stations. Interim databases are used prior to initial inspection rounds to catalogue the prospective locations. For each piping system being surveyed, these interim databases include physical coordinates for the candidate locations, the type and wall thickness of the components comprising each location, ranking indications and recommended NDE methodologies as a function of the anticipated corrosion mechanisms. Rationales for assessing corrosion susceptibility and ranking prospective inspection sites are expounded by way of notations built into the database. (authors)

  9. 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)

  10. 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)

  11. 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.

  12. Methodology for identifying credible disruptions to isolation of nuclear waste within Columbia River basalts

    International Nuclear Information System (INIS)

    Davis, J.D.

    1982-01-01

    Analysis of potential preclosure and postclosure disruptive events and processes is comprised of evaluation of (1) potential uncertainties and omissions associated with characterization of the site; (2) credible events and processes resulting from the dynamics of natural systems; (3) potential, credible changes in isolation conditions induced by the presence of the repository, and (4) potential, credible future changes impacting isolation capability resulting from man's activities, independent of repository construction/operation. This report presents the overall methodology for identification, classification and analysis of disruptive events based on Nuclear Regulatory Commission and Environmental Protection Agency guidelines proposed in drafts of 10 CFR 60 and 40 CFR 191. Potential credible disruptive events, processes, and conditions are considered with respect to whether they are anticipated or unanticipated, and determined to have reasonably foreseeable, very unlikely, or extremely unlikely probability of occurrence. 85 refs., 2 figs., 7 tabs

  13. 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

  14. 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

  15. Process and device for identifying nuclear reactor neutron absorber rod etancheity defect

    International Nuclear Information System (INIS)

    Pelletier, J.; Parrat, D.

    1990-01-01

    For identifying defects in the sealing of neutron absorbing rods. The rod is placed in a pressure tight enclosure filled with a chemically agressive solution. After a time the pressure is released to allow the solution come out of the rod. An analysis of the solution allows the detection of radioactive isotopes of metals which are in the rod [fr

  16. 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

  17. A sex-specific metabolite identified in a marine invertebrate utilizing phosphorus-31 nuclear magnetic resonance.

    Directory of Open Access Journals (Sweden)

    Robert A Kleps

    Full Text Available Hormone level differences are generally accepted as the primary cause for sexual dimorphism in animal and human development. Levels of low molecular weight metabolites also differ between men and women in circulating amino acids, lipids and carbohydrates and within brain tissue. While investigating the metabolism of blue crab tissues using Phosphorus-31 Nuclear Magnetic Resonance, we discovered that only the male blue crab (Callinectes sapidus contained a phosphorus compound with a chemical shift well separated from the expected phosphate compounds. Spectra obtained from male gills were readily differentiated from female gill spectra. Analysis from six years of data from male and female crabs documented that the sex-specificity of this metabolite was normal for this species. Microscopic analysis of male and female gills found no differences in their gill anatomy or the presence of parasites or bacteria that might produce this phosphorus compound. Analysis of a rare gynandromorph blue crab (laterally, half male and half female proved that this sex-specificity was an intrinsic biochemical process and was not caused by any variations in the diet or habitat of male versus female crabs. The existence of a sex-specific metabolite is a previously unrecognized, but potentially significant biochemical phenomenon. An entire enzyme system has been synthesized and activated only in one sex. Unless blue crabs are a unique species, sex-specific metabolites are likely to be present in other animals. Would the presence or absence of a sex-specific metabolite affect an animal's development, anatomy and biochemistry?

  18. 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)

  19. 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

  20. 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

  1. 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.)

  2. 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.

  3. 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)

  4. 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.

  5. 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

  6. Use of percentile rank sum method in identifying repetitive high occupational radiation dose jobs in a nuclear power plant

    International Nuclear Information System (INIS)

    Cho, Y.H.; Ko, H.S.; Kim, S.H.; Kang, C.S.; Moon, J.H.; Kim, K.D.

    2004-01-01

    The cost-effective reduction of occupational radiation dose (ORD) at a nuclear power plant could not be achieved without going through an extensive analysis of accumulated ORD data of existing plants. Through the data analysis, it is required to identify what are the jobs of repetitive high ORD at the nuclear power plant. In general the point value method commonly used, over-estimates the role of mean and median values to identify the high ORD jobs which can lead to misjudgment. In this study, Percentile Rank Sum Method (PRSM) is proposed to identify repetitive high ORD jobs, which is based on non-parametric statistical theory. As a case study, the method is applied to ORD data of maintenance and repair jobs at Kori units 3 and 4 that are pressurized water reactors with 950 MWe capacity and have been operated since 1986 and 1987, respectively in Korea. The results were verified and validated, and PRSM has been demonstrated to be an efficient method of analyzing the data. (authors)

  7. 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

  8. 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.

  9. 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)

  10. 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

  11. 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.

  12. 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)

  13. 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

  14. 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

  15. Criteria to identify and define territories with productive development potential to establish Special Economic Zones of Development (SEZD in Costa Rica

    Directory of Open Access Journals (Sweden)

    Rafael Arias Ramírez

    2015-07-01

    Full Text Available This study is aimed to identify, based on a series of variables and indicators, territories that have characteristics to propitiate an endogenous development, from the basis of the resource endowment they have, along with a productive policy, at the national and local level to promote it. A county´s index of productive potential is built around three components (productive, infrastructure and institutions; then a cluster analysis is applied. The outcomes of the study are not only new for the country, also they make a contribution with the elaboration of a matrix of variables and indicators, which provide criteria, empirically validated, to identify and define Special Economic Zones of Development (SEZD for Costa Rica.

  16. 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.

  17. USE OF PORTABLE GAMMA SPECTROMETERS FOR IDENTIFYING PERSONS EXPOSED IN A NUCLEAR CRITICALITY

    Energy Technology Data Exchange (ETDEWEB)

    Veinot, K. G. [Y-12 National Security Complex; Gose, B. T. [Y-12 National Security Complex; Bogard, James S [ORNL

    2009-01-01

    At Y-12 triage-style assessments are used to identify persons potentially exposed to high doses from criticality accident radiations using portable instruments by assessing the presence of activated sodium atoms in a person's blood. Historically, simple hand-held Geiger-Mueller (G-M) probes were used for these purposes although it was recognized that, since these instruments contain no information on incident photon energy, it was impossible to differentiate between photons emitted by contamination on the potentially exposed worker from activation of sodium in the person s blood. This works examines the use of a portable gamma spectrometer for assessing blood sodium activation. Irradiations of a representative phantom were performed using two neutron source configurations (unmoderated and polyethylene-moderated 252Cf) and measurements were made using the spectrometer and a G-M detector following irradiation. Detection limits in terms of personnel neutron dose are given for two neutron fields representing metaland solution criticality spectra. Both Geiger-Mueller and spectrometer results indicate a low minimum detectable neutron dose indicating that both instrument are useful as an emergency response instrument. The spectrometer has the added benefit of discriminating between surface contamination and blood sodium activation.

  18. USE OF PORTABLE GAMMA SPECTROMETERS FOR IDENTIFYING PERSONS EXPOSED IN A NUCLEAR CRITICALITY

    International Nuclear Information System (INIS)

    Veinot, K.G.; Gose, B.T.; Bogard, James S.

    2009-01-01

    At Y-12 triage-style assessments are used to identify persons potentially exposed to high doses from criticality accident radiations using portable instruments by assessing the presence of activated sodium atoms in a person's blood. Historically, simple hand-held Geiger-Mueller (G-M) probes were used for these purposes although it was recognized that, since these instruments contain no information on incident photon energy, it was impossible to differentiate between photons emitted by contamination on the potentially exposed worker from activation of sodium in the persons blood. This works examines the use of a portable gamma spectrometer for assessing blood sodium activation. Irradiations of a representative phantom were performed using two neutron source configurations (unmoderated and polyethylene-moderated 252Cf) and measurements were made using the spectrometer and a G-M detector following irradiation. Detection limits in terms of personnel neutron dose are given for two neutron fields representing metal and solution criticality spectra. Both Geiger-Mueller and spectrometer results indicate a low minimum detectable neutron dose indicating that both instrument are useful as an emergency response instrument. The spectrometer has the added benefit of discriminating between surface contamination and blood sodium activation.

  19. 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

  20. 77 FR 61443 - Acceptance of Application for Special Nuclear Materials License From Rensselaer Polytechnic...

    Science.gov (United States)

    2012-10-09

    ... previously available; and (iii) the filing has been submitted in a timely fashion based on the availability... proceeding may, in the discretion of the presiding officer, be permitted to make a limited appearance... Orders, in a timely fashion to minimize unnecessary delays in identifying those petitioners who have...

  1. 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.)

  2. 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

  3. 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...

  4. 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

  5. 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)

  6. 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

  7. 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,

  8. Identifying cognitive complexity factors affecting the complexity of procedural steps in emergency operating procedures of a nuclear power plant

    International Nuclear Information System (INIS)

    Park, Jinkyun; Jeong, Kwangsup; Jung, Wondea

    2005-01-01

    In complex systems such as a nuclear and chemical plant, it is well known that the provision of understandable procedures that allow operators to clarify what needs to be done and how to do it is one of the requisites to secure their safety. As a previous study in providing understandable procedures, the step complexity (SC) measure that can quantify the complexity of procedural steps in emergency operating procedures (EOPs) of a nuclear power plant (NPP) was suggested. However, the necessity of additional complexity factors that can consider a cognitive aspect in evaluating the complexity of procedural steps is raised. To this end, the comparisons between operators' performance data measured by the form of a step performance time with their behavior in carrying out the prescribed activities of procedural steps are conducted in this study. As a result, two kinds of complexity factors (the abstraction level of knowledge and the level of engineering decision) that could affect an operator's cognitive burden are identified. Although a well-designed experiment is indispensable for confirming the appropriateness of the additional complexity factors, it is strongly believed that the change of operators' performance data can be more authentically explained if the additional complexity factors are taken into consideration

  9. Identifying cognitive complexity factors affecting the complexity of procedural steps in emergency operating procedures of a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jinkyun [Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, P.O. Box 105, Duckjin-Dong, Yusong-Ku, Taejon 305-600 (Korea, Republic of)]. E-mail: kshpjk@kaeri.re.kr; Jeong, Kwangsup [Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, P.O. Box 105, Duckjin-Dong, Yusong-Ku, Taejon 305-600 (Korea, Republic of); Jung, Wondea [Integrated Safety Assessment Division, Korea Atomic Energy Research Institute, P.O. Box 105, Duckjin-Dong, Yusong-Ku, Taejon 305-600 (Korea, Republic of)

    2005-08-01

    In complex systems such as a nuclear and chemical plant, it is well known that the provision of understandable procedures that allow operators to clarify what needs to be done and how to do it is one of the requisites to secure their safety. As a previous study in providing understandable procedures, the step complexity (SC) measure that can quantify the complexity of procedural steps in emergency operating procedures (EOPs) of a nuclear power plant (NPP) was suggested. However, the necessity of additional complexity factors that can consider a cognitive aspect in evaluating the complexity of procedural steps is raised. To this end, the comparisons between operators' performance data measured by the form of a step performance time with their behavior in carrying out the prescribed activities of procedural steps are conducted in this study. As a result, two kinds of complexity factors (the abstraction level of knowledge and the level of engineering decision) that could affect an operator's cognitive burden are identified. Although a well-designed experiment is indispensable for confirming the appropriateness of the additional complexity factors, it is strongly believed that the change of operators' performance data can be more authentically explained if the additional complexity factors are taken into consideration.

  10. Identifying cognitive complexity factors affecting the complexity of procedural steps in emergency operating procedures of a nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Jinkyun Park; Kwangsup Jeong; Wondea Jung [Korea Atomic Energy Research Institute, Taejon (Korea). Integrated Safety Assessment Division

    2005-08-15

    In complex systems such as a nuclear and chemical plant, it is well known that the provision of understandable procedures that allow operators to clarify what needs to be done and how to do it is one of the requisites to secure their safety. As a previous study in providing understandable procedures, the step complexity (SC) measure that can quantify the complexity of procedural steps in emergency operating procedures (EOPs) of a nuclear power plant (NPP) was suggested. However, the necessity of additional complexity factors that can consider a cognitive aspect in evaluating the complexity of procedural steps is raised. To this end, the comparisons between operator' performance data measured by the form of a step performance time with their behavior in carrying out the prescribed activities of procedural steps are conducted in this study. As a result, two kinds of complexity factors (the abstraction level of knowledge and the level of engineering decision) that could affect an operator's cognitive burden are identified. Although a well-designed experiment is indispensable for confirming the appropriateness of the additional complexity factors, it is strongly believed that the change of operators' performance data can be more authentically explained if the additional complexity factors are taken into consideration. (author)

  11. Pilot program to identify valve failures which impact the safety and operation of light water nuclear power plants

    International Nuclear Information System (INIS)

    Tsacoyeanes, J.C.; Raju, P.P.

    1980-04-01

    The pilot program described has been initiated under the Department of Energy Light Water Reactor Safety Research and Development Program and has the following specific objectives: to identify the principal types and causes of failures in valves, valve operators and their controls and associated hardware, which lead to, or could lead to plant trip; and to suggest possible remedies for the prevention of these failures and recommend future research and development programs which could lead to minimizing these valve failures or mitigating their effect on plant operation. The data surveyed cover incidents reported over the six-year period, beginning 1973 through the end of 1978. Three sources of information on valve failures have been consulted: failure data centers, participating organizations in the nuclear power industry, and technical documents

  12. Detection of Special Nuclear Material in Cargo Containers Using Neutron Interrogation

    International Nuclear Information System (INIS)

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

    2003-01-01

    The goal of the work reported here is to develop a concept for an active neutron interrogation system that can detect small targets of SNM contraband in cargo containers, roughly 5 kg HEU or 1 kg Pu, even when well shielded by a thick cargo. It is essential that the concept be reliable and have low false-positive and false-negative error rates. It also must be rapid to avoid interruption of commerce, completing the analysis in minutes. A new radiation signature unique to SNM has been identified that utilizes high-energy (E γ = 3-7 MeV) fission product γ-ray emission. Fortunately, this high-energy γ-ray signature is robust in that it is very distinct compared to normal background radiation where there is no comparable high-energy γ-ray radiation. Equally important, it has a factor of 10 higher yield than delayed neutrons that are the basis of classical interrogation technique normally used on small unshielded specimens of SNM. And it readily penetrates two meters of low-Z and high-Z cargo at the expected density of ∼ 0.5 gm/cm 3 . Consequently, we expect that in most cases the signature flux at the container wall is at least 2-3 decades more intense than delayed neutron signals used historically and facilitates the detection of SNM even when shielded by thick cargo. Experiments have verified this signature and its predicted characteristics. However, they revealed an important interference due to the activation of 16 O by the 16 O(n,p) 16 N reaction that produces a 6 MeV γ-ray following a 7-sec β-decay of the 16 N. This interference is important when irradiating with 14 MeV neutrons but is eliminated when lower energy neutron sources are utilized since the reaction threshold for 16 O(n,p) 16 N is 10 MeV. The signature γ-ray fluxes exiting a thick cargo can be detected in large arrays of scintillation detectors to produce useful signal count rates of 2-4 x 10 4 cps. That is high enough to quickly identify SNM fission by its characteristic high energy

  13. Molecular phylogeny and systematics of the banana family (Musaceae) inferred from multiple nuclear and chloroplast DNA fragments, with a special reference to the genus Musa.

    Science.gov (United States)

    Li, Lin-Feng; Häkkinen, Markku; Yuan, Yong-Ming; Hao, Gang; Ge, Xue-Jun

    2010-10-01

    Musaceae is a small paleotropical family. Three genera have been recognised within this family although the generic delimitations remain controversial. Most species of the family (around 65 species) have been placed under the genus Musa and its infrageneric classification has long been disputed. In this study, we obtained nuclear ribosomal ITS and chloroplast (atpB-rbcL, rps16, and trnL-F) DNA sequences of 36 species (42 accessions of ingroups representing three genera) together with 10 accessions of ingroups retrieved from GenBank database and 4 accessions of outgroups, to construct the phylogeny of the family, with a special reference to the infrageneric classification of the genus Musa. Our phylogenetic analyses elaborated previous results in supporting the monophyly of the family and suggested that Musella and Ensete may be congeneric or at least closely related, but refuted the previous infrageneric classification of Musa. None of the five sections of Musa previously defined based on morphology was recovered as monophyletic group in the molecular phylogeny. Two infrageneric clades were identified, which corresponded well to the basic chromosome numbers of x=11 and 10/9/7, respectively: the former clade comprises species from the sections Musa and Rhodochlamys while the latter contains sections of Callimusa, Australimusa, and Ingentimusa. Copyright 2010 Elsevier Inc. All rights reserved.

  14. 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

  15. 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.

  16. 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

  17. Ergonomics as aid tool to identify and to analyze factors that can affect the operational performance of nuclear power plants

    International Nuclear Information System (INIS)

    Luquetti Santos, I.J.A.; Carvalho, P.V.R.

    2005-01-01

    The study of ergonomics has evolved around the world as one of the keys to understand human behavior in interaction with complex systems as nuclear power plant and to achieve the best match between the system and its users in the context of task to be performed. Increasing research efforts have yielded a considerable body of knowledge concerning the design of workstations, workplace, control rooms, human-system interfaces, user-interface interaction and organizational design to prevent worker discomfort, illness and also to improve productivity, product quality, ease of use and safety. The work ergonomics analysis consists of gathering a series of observation in order to better understand the work done and to propose changes and improvements in the working conditions. The work ergonomics analysis implies both the correction of existing situations (safety, reliability and production problems) and the development of new work system. Operator activity analysis provides a useful tool for the ergonomics approach, based on work ergonomics analysis. The operators will be systematically observed in their real work environment (control room) or in simulators. The focus is on description of the distributed regulated mechanisms (in the sense that operators work in crew), both in nominal and degraded situations, observing how operators regulate collectively their work during an increase in workload or when confronted with situations where incidents or accidents occur. Audio, video recorders and field notes can be used to collect empirical data, conversations and interactions that occur naturally within the work environment. Our research develops an applied ergonomics methodology, based on field studies, that permits to identify and analyze situations, factors that may affect the operational performance of nuclear power plants. Our contribution is related to the following technical topic: How best to learn from and share operational safety experience and manage changes during

  18. Necessidades especiais de escolares com diabetes mellitus tipo 1 identificadas por familiares Special needs of students with diabetes mellitus type 1 identified by relatives

    Directory of Open Access Journals (Sweden)

    Tania Moron Saes Braga

    2012-09-01

    purpose of this study was to identify the special needs of children with diabetes mellitus type 1. The participants were 37 family members of students in treatment in an outpatient center at a state of São Paulo medical school. A semi-structured interview was carried, which was audio recorded and transcribed for analysis. The results showed that all participants informed the school informed about their child's condition, however 29,7% reported that inclusion or access to school was difficult, due to the teacher being uninformed about diabetes control, inadequate school lunches, and preconceptions of peers and school supervisor, or the student's embarrassment. Absenteeism occurred among 70,3% of the students, mainly due to doctor appointments. Special needs were identified by 32,4%, including meals, performance in school tasks and the need to better inform school professionals about the condition. Furthermore, 72,9% reported some kind of support to cope with diabetes had been provided, mainly by health professionals. In order to improve their child's development at school 51,3% presented suggestions such as including appropriate school meals, better preparation of school for dealing with diabetes, i.e. lectures and training for teachers. Our suggestion is that there should be a closer relationship between the school and health services, but the first step towards intersector integration is to identify the needs of students with chronic diseases, such as this study showed, by focusing on diabetes mellitus and its impact on the school.

  19. 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

  20. 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

  1. Nonlinear Methodologies for Identifying Seismic Event and Nuclear Explosion Using Random Forest, Support Vector Machine, and Naive Bayes Classification

    Directory of Open Access Journals (Sweden)

    Longjun Dong

    2014-01-01

    Full Text Available The discrimination of seismic event and nuclear explosion is a complex and nonlinear system. The nonlinear methodologies including Random Forests (RF, Support Vector Machines (SVM, and Naïve Bayes Classifier (NBC were applied to discriminant seismic events. Twenty earthquakes and twenty-seven explosions with nine ratios of the energies contained within predetermined “velocity windows” and calculated distance are used in discriminators. Based on the one out cross-validation, ROC curve, calculated accuracy of training and test samples, and discriminating performances of RF, SVM, and NBC were discussed and compared. The result of RF method clearly shows the best predictive power with a maximum area of 0.975 under the ROC among RF, SVM, and NBC. The discriminant accuracies of RF, SVM, and NBC for test samples are 92.86%, 85.71%, and 92.86%, respectively. It has been demonstrated that the presented RF model can not only identify seismic event automatically with high accuracy, but also can sort the discriminant indicators according to calculated values of weights.

  2. Study of the method of water-injected meat identifying based on low-field nuclear magnetic resonance

    Science.gov (United States)

    Xu, Jianmei; Lin, Qing; Yang, Fang; Zheng, Zheng; Ai, Zhujun

    2018-01-01

    The aim of this study to apply low-field nuclear magnetic resonance technique was to study regular variation of the transverse relaxation spectral parameters of water-injected meat with the proportion of water injection. Based on this, the method of one-way ANOVA and discriminant analysis was used to analyse the differences between these parameters in the capacity of distinguishing water-injected proportion, and established a model for identifying water-injected meat. The results show that, except for T 21b, T 22e and T 23b, the other parameters of the T 2 relaxation spectrum changed regularly with the change of water-injected proportion. The ability of different parameters to distinguish water-injected proportion was different. Based on S, P 22 and T 23m as the prediction variable, the Fisher model and the Bayes model were established by discriminant analysis method, qualitative and quantitative classification of water-injected meat can be realized. The rate of correct discrimination of distinguished validation and cross validation were 88%, the model was stable.

  3. 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

  4. 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

  5. Listen-Identify-Brainstorm-Reality-Test-Encourage (LIBRE) Problem-Solving Model: Addressing Special Education Teacher Attrition through a Cognitive-Behavioral Approach to Teacher Induction

    Science.gov (United States)

    Guerra, Norma S.; Hernandez, Art; Hector, Alison M.; Crosby, Shane

    2015-01-01

    Special education teacher attrition rates continue to challenge the profession. A cognitive-behavioral problem-solving approach was used to examine three alternative certification program special education teachers' professional development through a series of 41 interviews conducted over a 2-year period. Beginning when they were novice special…

  6. 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

  7. 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.)

  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. Identifying emerging trends for implementing learning technology in special education: a state-of-the-art review of selected articles published in 2008-2012.

    Science.gov (United States)

    Liu, Gi-Zen; Wu, No-Wei; Chen, Yi-Wen

    2013-10-01

    As electronic learning (e-learning) becomes increasingly popular in education worldwide, learning technology (LT) has been applied in various learning environments and activities to promote meaningful, efficient, and effective learning. LT has also been adopted by researchers and teacher-practitioners in the field of special education, but as yet little review-based research has been published. This review research thus carefully examined the trends of LT implementations in special education, providing a comprehensive analysis of 26 studies published in indexed journals in the past five years (2008-2012). Two research questions were addressed: (a) What are the major research aims, methodologies, and outcomes in these studies of implementing LT in the field of special education? and (b) What types of LT are mainly used with special education students, and for what kinds of students? Major findings include that examining the learning effectiveness of LT using was the most common research purpose (75%); researchers primarily relied on experimental studies (46%, 12 studies), followed by interviews and questionnaires (19%, 5 studies). Moreover, the most common use of LT was computer-assisted technology (such as web-based mentoring, educational computer games, laptop computers) in special education; studies investigating the use of LT with mentally disabled students were more than those with physically disabled ones. It is expected that the findings of this work and their implications will serve as valuable references with regard to the use of LT with special education students. Copyright © 2013 Elsevier Ltd. All rights reserved.

  10. A convergence/divergence schema to identify impacts: The case of the Palo Verde nuclear generating station

    International Nuclear Information System (INIS)

    Pasqualetti, M.J.

    1984-01-01

    Until fairly recently, geographers have contributed only slightly to research on nuclear power plants. Most studies have dealt with ''site selection,'' though lately topics including socioeconomics, waste disposal, and emergency preparedness, have been addressed. Currently NRC-mandated investigations into many of the impacts of nuclear power plants tend to focus on local effects, but these often are not detailed and are only during the early planning stages. Little attention continues to be paid to questions of socioeconomic impacts and land use changes during or after construction. This limited approach is neither necessary nor imaginative, cohesive nor wise, because it fails to encompass or probe an appropriately wide geographical range of possible contributions. This traditionally small and parochial sphere of inquiry can be expanded by using the conceptual framework of convergence and divergence. Suggested examples include land use changes in value or function in association with various nuclear facilities, transportation and socioeconomic factors associated with the complexities of the nuclear fuel cycle, and the exportation of fuel and the nuclear fuel cycle, and the exportation of fuel and technology. The application of such a geographical perspective in the study of PVNGS illustrates the influence (often distant and unrecognized) which can follow a local decision to build a nuclear power plant

  11. 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.)

  12. 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

  13. 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.

  14. 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

  15. 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.)

  16. Identifying the ‘subnormal’ child in an age of expansion of special schooling and child science in the Netherlands (c.1945-1965)

    NARCIS (Netherlands)

    Bakker, Nelleke

    2015-01-01

    Between c.1945 and 1965 across the West special education has grown and differentiated substantially. In the Netherlands this expansion ran parallel to the academic recognition and rapid development of the study of learning disabilities. How are these two processes related? This article argues that

  17. Identifying the "Subnormal" Child in an Age of Expansion of Special Education and Child Science in the Netherlands (c.1945-1965)

    Science.gov (United States)

    Bakker, Nelleke

    2015-01-01

    Between c.1945 and 1965 across the West special education has grown and differentiated substantially. In the Netherlands this expansion ran parallel to the academic recognition and rapid development of the study of learning disabilities. How are these two processes related? This article argues that in this country child science and special…

  18. 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

  19. Can Physicians Identify Inappropriate Nuclear Stress Tests? An Examination of Inter-rater Reliability for the 2009 Appropriate Use Criteria for Radionuclide Imaging

    Science.gov (United States)

    Ye, Siqin; Rabbani, LeRoy E.; Kelly, Christopher R.; Kelly, Maureen R.; Lewis, Matthew; Paz, Yehuda; Peck, Clara L.; Rao, Shaline; Bokhari, Sabahat; Weiner, Shepard D.; Einstein, Andrew J.

    2014-01-01

    Background We sought to determine inter-rater reliability of the 2009 Appropriate Use Criteria (AUC) for radionuclide imaging (RNI) and whether physicians at various levels of training can effectively identify nuclear stress tests with inappropriate indications. Methods and Results Four hundred patients were randomly selected from a consecutive cohort of patients undergoing nuclear stress testing at an academic medical center. Raters with different levels of training (including cardiology attending physicians, cardiology fellows, internal medicine hospitalists, and internal medicine interns) classified individual nuclear stress tests using the 2009 AUC. Consensus classification by two cardiologists was considered the operational gold standard, and sensitivity and specificity of individual raters for identifying inappropriate tests was calculated. Inter-rater reliability of the AUC was assessed using Cohen’s kappa statistics for pairs of different raters. The mean age of patients was 61.5 years; 214 (54%) were female. The cardiologists rated 256 (64%) of 400 NSTs as appropriate, 68 (18%) as uncertain, 55 (14%) as inappropriate; 21 (5%) tests were unable to be classified. Inter-rater reliability for non-cardiologist raters was modest (unweighted Cohen’s kappa, 0.51, 95% confidence interval, 0.45 to 0.55). Sensitivity of individual raters for identifying inappropriate tests ranged from 47% to 82%, while specificity ranged from 85% to 97%. Conclusions Inter-rater reliability for the 2009 AUC for RNI is modest, and there is considerable variation in the ability of raters at different levels of training to identify inappropriate tests. PMID:25563660

  20. 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

  1. 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.

  2. 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

  3. 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...

  4. Dibaryons and nuclear matter

    International Nuclear Information System (INIS)

    Besliu, C.; Popa, L.; Popa, V.

    1992-01-01

    We discuss some recent ideas concerning the structure and the properties of the dibaryonic resonances, with special emphasis on their behaviour when produced in dense nuclear matter. Some features of their de-excitation mechanism and consequent experimentally identifiable signatures are predicted. (Author)

  5. 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 ...

  6. 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)

  7. Nuclear material control systems for nuclear power plants

    International Nuclear Information System (INIS)

    1975-06-01

    Paragraph 70.51(c) of 10 CFR Part 70 requires each licensee who is authorized to possess at any one time special nuclear material in a quantity exceeding one effective kilogram to establish, maintain, and follow written material control and accounting procedures that are sufficient to enable the licensee to account for the special nuclear material in his possession under license. While other paragraphs and sections of Part 70 provide specific requirements for nuclear material control systems for fuel cycle plants, such detailed requirements are not included for nuclear power reactors. This guide identifies elements acceptable to the NRC staff for a nuclear material control system for nuclear power reactors. (U.S.)

  8. 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)

  9. 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)

  10. 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

  11. 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

  12. 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

  13. 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.)

  14. 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)

  15. 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

  16. 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

  17. 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

  18. 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.

  19. 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)

  20. 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)

  1. KHNP special safety review

    International Nuclear Information System (INIS)

    Lee, Tae-Ho; Lee, Bang-Jin; Lee, Soung-Hee; Park, Goon-Cherl

    2009-01-01

    Commemorating the 30 year anniversary of commercial nuclear power plant operation in KOREA, Korea Hydro and Nuclear Power Co., Ltd. (KHNP) has conducted a Special Safety Review (SSR) of its 20 operating units to understand their safety performance and to identify any areas that need improvement. The SSR reviewed all 20 operating units for 2 weeks per site. Areas that were reviewed are Safety Margins, Plant Performance, Employee Safety, Employee Performance and Performance Improvement Process. Each review team consisted of international and domestic members. The international reviewers were from IAEA, WANO and INPO. The domestic reviewers consisted of professors, Engineering Company, Research Institute and KHNP experts. The review confirmed safe and reliable operations of the 20 nuclear units. The common understanding resulted from the SSR is as follows. Firstly, KHNP corporate and its plants confirmed and shared mutual understanding on recurring areas for improvements, especially in the areas of Organizational Effectiveness, Industrial Safety, Human Performance, Configuration Management, Operations, Equipment Performance and Material Condition. Secondly, KHNP understood that plant and department level performances are directly related to the leadership and competency of the management team including supervisors. Thirdly, the strengths of individual stations that consistently have produced good results need to be shared with the other KHNP stations. Finally, KHNP learned that strong corporate leadership and support are needed to resolve most of the areas for improvement since they are common to all KHNP stations. (author)

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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.

  8. 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.

  9. 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.

  10. Signalling properties of identified deep cerebellar nuclear neurons related to eye and head movements in the alert cat.

    Science.gov (United States)

    Gruart, A; Delgado-García, J M

    1994-07-01

    1. The spike activity of deep cerebellar nuclear neurons was recorded in the alert cat during spontaneous and during vestibularly and visually induced eye movements. 2. Neurons were classified according to their location in the nuclei, their antidromic activation from projection sites, their sensitivity to eye position and velocity during spontaneous eye movements, and their responses to vestibular and optokinetic stimuli. 3. Type I EPV (eye position and velocity) neurons were located mainly in the posterior part of the fastigial nucleus and activated antidromically almost exclusively from the medial longitudinal fasciculus close to the oculomotor complex. These neurons, reported here for the first time, increased their firing rate during saccades and eye fixations towards the contralateral hemifield. Their position sensitivity to eye fixations in the horizontal plane was 5.3 +/- 2.6 spikes s-1 deg-1 (mean +/- S.D.). Eye velocity sensitivity during horizontal saccades was 0.71 +/- 0.52 spikes s-1 deg-1 s-1. Variability of their firing rate during a given eye fixation was higher than that shown by abducens motoneurons. 4. Type I EPV neurons increased their firing rate during ipsilateral head rotations at 0.5 Hz with a mean phase lead over eye position of 95.3 +/- 9.5 deg. They were also activated by contralateral optokinetic stimulation at 30 deg s-1. Their sensitivity to eye position and velocity in the horizontal plane during vestibular and optokinetic stimuli yielded values similar to those obtained for spontaneous eye movements. 5. Type II neurons were located in both fastigial and dentate nuclei and were activated antidromically from the restiform body, the medial longitudinal fasciculus close to the oculomotor complex, the red nucleus and the pontine nuclei. Type II neurons were not related to spontaneous eye movements. These neurons increased their firing rate in response to contralateral head rotation and during ipsilateral optokinetic stimulation, and

  11. Development and Implementation of a High-Throughput High-Content Screening Assay to Identify Inhibitors of Androgen Receptor Nuclear Localization in Castration-Resistant Prostate Cancer Cells

    Science.gov (United States)

    Nguyen, Minh M.; Dar, Javid A.; Ai, Junkui; Wang, Yujuan; Masoodi, Khalid Z.; Shun, Tongying; Shinde, Sunita; Camarco, Daniel P.; Hua, Yun; Huryn, Donna M.; Wilson, Gabriela Mustata; Lazo, John S.; Nelson, Joel B.; Wipf, Peter

    2016-01-01

    Abstract Patients with castration-resistant prostate cancer (CRPC) can be treated with abiraterone, a potent inhibitor of androgen synthesis, or enzalutamide, a second-generation androgen receptor (AR) antagonist, both targeting AR signaling. However, most patients relapse after several months of therapy and a majority of patients with relapsed CRPC tumors express the AR target gene prostate-specific antigen (PSA), suggesting that AR signaling is reactivated and can be targeted again to inhibit the relapsed tumors. Novel small molecules capable of inhibiting AR function may lead to urgently needed therapies for patients resistant to abiraterone, enzalutamide, and/or other previously approved antiandrogen therapies. Here, we describe a high-throughput high-content screening (HCS) campaign to identify small-molecule inhibitors of AR nuclear localization in the C4-2 CRPC cell line stably transfected with GFP-AR-GFP (2GFP-AR). The implementation of this HCS assay to screen a National Institutes of Health library of 219,055 compounds led to the discovery of 3 small molecules capable of inhibiting AR nuclear localization and function in C4-2 cells, demonstrating the feasibility of using this cell-based phenotypic assay to identify small molecules targeting the subcellular localization of AR. Furthermore, the three hit compounds provide opportunities to develop novel AR drugs with potential for therapeutic intervention in CRPC patients who have relapsed after treatment with antiandrogens, such as abiraterone and/or enzalutamide. PMID:27187604

  12. Expression profiling of nuclear receptors in breast cancer identifies TLX as a mediator of growth and invasion in triple-negative breast cancer.

    Science.gov (United States)

    Lin, Meng-Lay; Patel, Hetal; Remenyi, Judit; Banerji, Christopher R S; Lai, Chun-Fui; Periyasamy, Manikandan; Lombardo, Ylenia; Busonero, Claudia; Ottaviani, Silvia; Passey, Alun; Quinlan, Philip R; Purdie, Colin A; Jordan, Lee B; Thompson, Alastair M; Finn, Richard S; Rueda, Oscar M; Caldas, Carlos; Gil, Jesus; Coombes, R Charles; Fuller-Pace, Frances V; Teschendorff, Andrew E; Buluwela, Laki; Ali, Simak

    2015-08-28

    The Nuclear Receptor (NR) superfamily of transcription factors comprises 48 members, several of which have been implicated in breast cancer. Most important is estrogen receptor-α (ERα), which is a key therapeutic target. ERα action is facilitated by co-operativity with other NR and there is evidence that ERα function may be recapitulated by other NRs in ERα-negative breast cancer. In order to examine the inter-relationships between nuclear receptors, and to obtain evidence for previously unsuspected roles for any NRs, we undertook quantitative RT-PCR and bioinformatics analysis to examine their expression in breast cancer. While most NRs were expressed, bioinformatic analyses differentiated tumours into distinct prognostic groups that were validated by analyzing public microarray data sets. Although ERα and progesterone receptor were dominant in distinguishing prognostic groups, other NR strengthened these groups. Clustering analysis identified several family members with potential importance in breast cancer. Specifically, RORγ is identified as being co-expressed with ERα, whilst several NRs are preferentially expressed in ERα-negative disease, with TLX expression being prognostic in this subtype. Functional studies demonstrated the importance of TLX in regulating growth and invasion in ERα-negative breast cancer cells.

  13. 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

  14. 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.)

  15. 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)

  16. Function Allocation in Complex Socio-Technical Systems: Procedure usage in nuclear power and the Context Analysis Method for Identifying Design Solutions (CAMIDS) Model

    Science.gov (United States)

    Schmitt, Kara Anne

    This research aims to prove that strict adherence to procedures and rigid compliance to process in the US Nuclear Industry may not prevent incidents or increase safety. According to the Institute of Nuclear Power Operations, the nuclear power industry has seen a recent rise in events, and this research claims that a contributing factor to this rise is organizational, cultural, and based on peoples overreliance on procedures and policy. Understanding the proper balance of function allocation, automation and human decision-making is imperative to creating a nuclear power plant that is safe, efficient, and reliable. This research claims that new generations of operators are less engaged and thinking because they have been instructed to follow procedures to a fault. According to operators, they were once to know the plant and its interrelations, but organizationally more importance is now put on following procedure and policy. Literature reviews were performed, experts were questioned, and a model for context analysis was developed. The Context Analysis Method for Identifying Design Solutions (CAMIDS) Model was created, verified and validated through both peer review and application in real world scenarios in active nuclear power plant simulators. These experiments supported the claim that strict adherence and rigid compliance to procedures may not increase safety by studying the industry's propensity for following incorrect procedures, and when it directly affects the outcome of safety or security of the plant. The findings of this research indicate that the younger generations of operators rely highly on procedures, and the organizational pressures of required compliance to procedures may lead to incidents within the plant because operators feel pressured into following the rules and policy above performing the correct actions in a timely manner. The findings support computer based procedures, efficient alarm systems, and skill of the craft matrices. The solution to

  17. iNR-PhysChem: a sequence-based predictor for identifying nuclear receptors and their subfamilies via physical-chemical property matrix.

    Directory of Open Access Journals (Sweden)

    Xuan Xiao

    Full Text Available Nuclear receptors (NRs form a family of ligand-activated transcription factors that regulate a wide variety of biological processes, such as homeostasis, reproduction, development, and metabolism. Human genome contains 48 genes encoding NRs. These receptors have become one of the most important targets for therapeutic drug development. According to their different action mechanisms or functions, NRs have been classified into seven subfamilies. With the avalanche of protein sequences generated in the postgenomic age, we are facing the following challenging problems. Given an uncharacterized protein sequence, how can we identify whether it is a nuclear receptor? If it is, what subfamily it belongs to? To address these problems, we developed a predictor called iNR-PhysChem in which the protein samples were expressed by a novel mode of pseudo amino acid composition (PseAAC whose components were derived from a physical-chemical matrix via a series of auto-covariance and cross-covariance transformations. It was observed that the overall success rate achieved by iNR-PhysChem was over 98% in identifying NRs or non-NRs, and over 92% in identifying NRs among the following seven subfamilies: NR1--thyroid hormone like, NR2--HNF4-like, NR3--estrogen like, NR4--nerve growth factor IB-like, NR5--fushi tarazu-F1 like, NR6--germ cell nuclear factor like, and NR0--knirps like. These rates were derived by the jackknife tests on a stringent benchmark dataset in which none of protein sequences included has ≥60% pairwise sequence identity to any other in a same subset. As a user-friendly web-server, iNR-PhysChem is freely accessible to the public at either http://www.jci-bioinfo.cn/iNR-PhysChem or http://icpr.jci.edu.cn/bioinfo/iNR-PhysChem. Also a step-by-step guide is provided on how to use the web-server to get the desired results without the need to follow the complicated mathematics involved in developing the predictor. It is anticipated that iNR-PhysChem may

  18. INEEL special case waste storage and disposal alternatives

    International Nuclear Information System (INIS)

    Larson, L.A.; Bishop, C.W.; Bhatt, R.N.

    1997-07-01

    Special case waste is historically defined as radioactive waste that does not have a path forward or fit into current Department of Energy management plans for final treatment or disposal. The objectives of this report, relative to special case waste at the Idaho National Engineering and Environmental Laboratory, are to (a) identify its current storage locations, conditions, and configuration; (b) review and verify the currently reported inventory; (c) segregate the inventory into manageable categories; (d) identify the portion that has a path forward or is managed under other major programs/projects; (e) identify options for reconfiguring and separating the disposable portions; (f) determine if the special case waste needs to be consolidated into a single storage location; and (g) identify a preferred facility for storage. This report also provides an inventory of stored sealed sources that are potentially greater than Class C or special case waste based on Nuclear Regulatory Commission and Site-Specific Waste Acceptance Criteria

  19. Environmental Assessment for renewal of Special Nuclear Material License No. SNM-368 (Docket No. 70-371)

    International Nuclear Information System (INIS)

    1985-01-01

    The proposed action is the renewal of the license necessary for UNC to continue the existing fuel fabrication operation. Principal operations in the fabrication facility include the processing of highly enriched uranium (>90% 235 U) into fuel elements and assembling of the elements into complete reactor cores. The present application for renewal involves no major changes in the current authorization and no new facilities are planned. The current operation of the UNC facilities results in the release of radioactive and nonradioactive effluent to the environment. The 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. 7 figures, 23 tables

  20. 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.)

  1. Comparative genomics in Chlamydomonas and Plasmodium identifies an ancient nuclear envelope protein family essential for sexual reproduction in protists, fungi, plants, and vertebrates.

    Science.gov (United States)

    Ning, Jue; Otto, Thomas D; Pfander, Claudia; Schwach, Frank; Brochet, Mathieu; Bushell, Ellen; Goulding, David; Sanders, Mandy; Lefebvre, Paul A; Pei, Jimin; Grishin, Nick V; Vanderlaan, Gary; Billker, Oliver; Snell, William J

    2013-05-15

    Fertilization is a crucial yet poorly characterized event in eukaryotes. Our previous discovery that the broadly conserved protein HAP2 (GCS1) functioned in gamete membrane fusion in the unicellular green alga Chlamydomonas and the malaria pathogen Plasmodium led us to exploit the rare biological phenomenon of isogamy in Chlamydomonas in a comparative transcriptomics strategy to uncover additional conserved sexual reproduction genes. All previously identified Chlamydomonas fertilization-essential genes fell into related clusters based on their expression patterns. Out of several conserved genes in a minus gamete cluster, we focused on Cre06.g280600, an ortholog of the fertilization-related Arabidopsis GEX1. Gene disruption, cell biological, and immunolocalization studies show that CrGEX1 functions in nuclear fusion in Chlamydomonas. Moreover, CrGEX1 and its Plasmodium ortholog, PBANKA_113980, are essential for production of viable meiotic progeny in both organisms and thus for mosquito transmission of malaria. Remarkably, we discovered that the genes are members of a large, previously unrecognized family whose first-characterized member, KAR5, is essential for nuclear fusion during yeast sexual reproduction. Our comparative transcriptomics approach provides a new resource for studying sexual development and demonstrates that exploiting the data can lead to the discovery of novel biology that is conserved across distant taxa.

  2. Identification of new unresolved safety issues relating to nuclear power plants - special report to Congress. Congressional report

    International Nuclear Information System (INIS)

    1981-03-01

    As a result of NRC staff review and extended collegial consultations and investigations within the NRC, the Commission has designated four new Unresolved Safety Issues (USIs). This report describes the process used to evaluate the large number of concerns and recommendations which resulted from the major investigations of the Three Mile Island-2 accident as well as other events and investigations of the past year, and the report identifies the four new USIs selected as follows: (1) Shutdown decay heat removal requirements (Task A-45); (2) Seismic qualification of equipment in operating plants (Task A-46); (3) Safety implications of control systems (Task A-47); and (4) Hydrogen control measures and effects of hydrogen burns on safety equipment (Task A-48). Appendix A of the report presents an expanded discussion of each new USI including issue definition, a preliminary discussion of the action plan and a basis for continued plant operations and licensing. Appendix B of the report provides a brief discussion of each of the candidate safety issues not designated as an USI

  3. Reaction Coordinate Leading to H2 Production in [FeFe]-Hydrogenase Identified by Nuclear Resonance Vibrational Spectroscopy and Density Functional Theory.

    Science.gov (United States)

    Pelmenschikov, Vladimir; Birrell, James A; Pham, Cindy C; Mishra, Nakul; Wang, Hongxin; Sommer, Constanze; Reijerse, Edward; Richers, Casseday P; Tamasaku, Kenji; Yoda, Yoshitaka; Rauchfuss, Thomas B; Lubitz, Wolfgang; Cramer, Stephen P

    2017-11-22

    [FeFe]-hydrogenases are metalloenzymes that reversibly reduce protons to molecular hydrogen at exceptionally high rates. We have characterized the catalytically competent hydride state (H hyd ) in the [FeFe]-hydrogenases from both Chlamydomonas reinhardtii and Desulfovibrio desulfuricans using 57 Fe nuclear resonance vibrational spectroscopy (NRVS) and density functional theory (DFT). H/D exchange identified two Fe-H bending modes originating from the binuclear iron cofactor. DFT calculations show that these spectral features result from an iron-bound terminal hydride, and the Fe-H vibrational frequencies being highly dependent on interactions between the amine base of the catalytic cofactor with both hydride and the conserved cysteine terminating the proton transfer chain to the active site. The results indicate that H hyd is the catalytic state one step prior to H 2 formation. The observed vibrational spectrum, therefore, provides mechanistic insight into the reaction coordinate for H 2 bond formation by [FeFe]-hydrogenases.

  4. Conceptual design of the special nuclear material nondestructive assay and accountability system for the HTGR fuel refabrication pilot plant

    International Nuclear Information System (INIS)

    Jenkins, J.D.; McNeany, S.R.; Rushton, J.E.

    1975-07-01

    The conceptual design of the fissile material assay and accountability system for the HTGR refabrication pilot plant has been established. The primary feature affecting the design is the high, time varying, gamma activity of the process material due to the unavoidable presence of uranium-232. This imposes stringent requirements for remote operation and remote maintainability of system components. At the same time, the remote operation lends itself to implementation of an automated data collection and processing system for real-time accountability. The high time-varying gamma activity of the material also precludes application of a number of techniques presently employed for light-water reactor fuel assay. The techniques selected for application in the refabrication facility are (1) active thermal neutron interrogation with fast-fission or delayed-neutron counting for fuel-rod and small-sample assay, (2) calorimetry for high-level waste assay, and (3) passive gamma scanning for low-level waste assay, and rapid on-line relative rod-loading measurements. The principal nondestructive assay subsystems are identified as (1) on-line devices for 100 percent product fuel rod assay and quality control, (2) a multipurpose device in the sample inspection laboratory for small- sample assay and secondary standards calibration, and (3) equipment for assay of high- and low-uranium content scrap and waste materials. A data processing system, which coordinates data from these subsystems with information from other process control sensors, is included to provide real-time material balance information. (U.S.)

  5. 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 ...

  6. 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)

  7. 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

  8. 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)

  9. 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.)

  10. Some factors in the calculation of the neutron intensity from (α,n) reactions with reference to the assay of special nuclear materials

    International Nuclear Information System (INIS)

    West, D.

    1985-07-01

    The application of neutron coincidence counting to the assay of special nuclear material involves a major correction for neutron multiplication. The correction commonly used at present requires an accurate knowledge of the intensity ratio of neutrons from (α,n) reactions to those from spontaneous fission. This paper covers various factors, which need to be evaluated in order to assess their importance, in the calculation of (α,n) neutron production using measured thick target yields. They include: accuracy of (α,n) thick target yield measurements; errors introduced by deriving yields in compounds from the measured yields in the constituents and vice-versa; the likely effect of neglecting the difference of α-particle stopping power between Pu and U on the calculated neutron yield from mixed oxide fuel pellets; the intensity of neutrons produced from 1 to 2% of Al used to alloy plutonium metal; the intensity of neutrons produced in Al, used as canning material, from α-particles escaping from the surface layers of oxide or metal fuel; and neutron production from oxygen in the air spaces of powdered PuO 2 prior to sintering. (author)

  11. Investigations of active interrogation techniques to detect special nuclear material in maritime environments: Standoff interrogation of small- and medium-sized cargo ships

    Energy Technology Data Exchange (ETDEWEB)

    Miller, Thomas M., E-mail: millertm@ornl.gov; Patton, Bruce W.; Grogan, Brandon R.; Henkel, James J.; Murphy, Brian D.; Johnson, Jeffrey O.; Mihalczo, John T.

    2013-12-01

    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.

  12. Program specialization

    CERN Document Server

    Marlet, Renaud

    2013-01-01

    This book presents the principles and techniques of program specialization - a general method to make programs faster (and possibly smaller) when some inputs can be known in advance. As an illustration, it describes the architecture of Tempo, an offline program specializer for C that can also specialize code at runtime, and provides figures for concrete applications in various domains. Technical details address issues related to program analysis precision, value reification, incomplete program specialization, strategies to exploit specialized program, incremental specialization, and data speci

  13. Qualification, training, licensing/authorization and retraining of operating personnel in nuclear power plants. Noteworthy topics identified by evaluation of the practices in countries of the European Communities

    International Nuclear Information System (INIS)

    Kraut, A.; Pfeffer, W.

    1987-01-01

    In the report EUR 10118 '' Qualification, training, licensing and retraining of operating shift personnel in nuclear power plants'' the current practice in the countries of the European Communities as well as the procedures and programmes applied in Sweden, Switzerland and the USA are outlined and evaluated. The intent was to derive fundamental and generally valid concepts concerning shift-staff training and other relevant aspects. Those items were identified that seemed to be noteworthy because they give some guidance on how to achieve and maintain the qualification of the shift staff of NPPs or how to improve the staffing of the control room. These noteworthy topics identified by evaluation of the practice in countries of the European Communities and also elsewhere are presented in the publication at hand. The report addresses the following topics: tasks of the shift personnel, nomenclature for different grades of the personnel; shift staffing and staffing of the control room; criteria for personnel selection when recruiting new shift staff; personnel qualification necessary for recruitment; training of shift personnel; retraining and preservation of qualification standards; training facilities, especially simulators; responsibility for training; licensing/authorization; retirement from shift work. Consideration of these more general aspects and concepts may lead to improvement in training. The job descriptions given in the Annex to the document are only intended to give a general understanding of the typical designations, tasks and responsibilities of shift staff

  14. Establishment of professional nuclear power architectural engineering company

    International Nuclear Information System (INIS)

    Guo Dongli; Chen Hua

    2006-01-01

    The rapid development of nuclear power industry in China requires specialized management for the nuclear power engineering projects. It is necessary to establish the nuclear power architectural engineering company to meet the increasing market needs by providing the owner with specialized nuclear engineering project management and overall contracting services. It is imperative that the purpose of establishing the corporation and enterprise core competitiveness should be clearly identified when it is established. Its organizational structure should be geared to the enterprise operation management and development to facilitate the intensified project management and control, and improve its risk-proof ability. (authors)

  15. Challenges for nuclear regulators

    International Nuclear Information System (INIS)

    Allen, M.R.

    1994-01-01

    The paper discusses issues that will present particular challenges to the nuclear industry, during the next decade, that should be addressed in order to achieve increased public acceptance of the industry. The issues of safety culture, peer review of safety, severe accidents, transport accidents and public communication are suggest as meriting special consideration. The need for nuclear regulatory agencies to establish credibility and for operating organisations to demonstrate accountability is emphasised, and the Australian experiences are reviewed. Increased collaboration by nuclear regulatory agencies in the Asian-pacific region is suggested, in order to encourage consistency of regulatory safety standards for the nuclear safety issues identified. Methods whereby this could be achieved within the framework of existing agreements and arrangements are suggested. 2 refs

  16. Developing A/E capabilities; areas of special interest

    International Nuclear Information System (INIS)

    Gonzalez, A.; Gurbindo, J.

    1988-01-01

    During the last few years, the methods used by Empresarios Agrupados and INITEC to perform Architect-Engineering work in Spain for nuclear projects has undergone a process of significant change in project management and engineering approaches. Specific practical examples of management techniques and design practices which represent a good record of results will be discussed. They are identified as areas of special interest in developing A/E capabilities for nuclear projects. Command of these areas should produce major payoffs in local participation and contribute to achieving real nuclear engineering capabilities in the country

  17. Identifying Patient-Specific Epstein-Barr Nuclear Antigen-1 Genetic Variation and Potential Autoreactive Targets Relevant to Multiple Sclerosis Pathogenesis.

    Directory of Open Access Journals (Sweden)

    Monika Tschochner

    Full Text Available Epstein-Barr virus (EBV infection represents a major environmental risk factor for multiple sclerosis (MS, with evidence of selective expansion of Epstein-Barr Nuclear Antigen-1 (EBNA1-specific CD4+ T cells that cross-recognize MS-associated myelin antigens in MS patients. HLA-DRB1*15-restricted antigen presentation also appears to determine susceptibility given its role as a dominant risk allele. In this study, we have utilised standard and next-generation sequencing techniques to investigate EBNA-1 sequence variation and its relationship to HLA-DR15 binding affinity, as well as examining potential cross-reactive immune targets within the central nervous system proteome.Sanger sequencing was performed on DNA isolated from peripheral blood samples from 73 Western Australian MS cases, without requirement for primary culture, with additional FLX 454 Roche sequencing in 23 samples to identify low-frequency variants. Patient-derived viral sequences were used to predict HLA-DRB1*1501 epitopes (NetMHCII, NetMHCIIpan and candidates were evaluated for cross recognition with human brain proteins.EBNA-1 sequence variation was limited, with no evidence of multiple viral strains and only low levels of variation identified by FLX technology (8.3% nucleotide positions at a 1% cut-off. In silico epitope mapping revealed two known HLA-DRB1*1501-restricted epitopes ('AEG': aa 481-496 and 'MVF': aa 562-577, and two putative epitopes between positions 502-543. We identified potential cross-reactive targets involving a number of major myelin antigens including experimentally confirmed HLA-DRB1*15-restricted epitopes as well as novel candidate antigens within myelin and paranodal assembly proteins that may be relevant to MS pathogenesis.This study demonstrates the feasibility of obtaining autologous EBNA-1 sequences directly from buffy coat samples, and confirms divergence of these sequences from standard laboratory strains. This approach has identified a number of

  18. Radioactive waste isolation in salt: special advisory report on the status of the Office of Nuclear Waste Isolation's plans for repository performance assessment

    International Nuclear Information System (INIS)

    Ditmars, J.D.; Walbridge, E.W.; Rote, D.M.; Harrison, W.; Herzenberg, C.L.

    1983-10-01

    Repository performance assessment is analysis that identifies events and processes that might affect a repository system for isolation of radioactive waste, examines their effects on barriers to waste migration, and estimates the probabilities of their occurrence and their consequences. In 1983 Battelle Memorial Institute's Office of Nuclear Waste Isolation (ONWI) prepared two plans - one for performance assessment for a waste repository in salt and one for verification and validation of performance assessment technology. At the request of the US Department of Energy's Salt Repository Project Office (SRPO), Argonne National Laboratory reviewed those plans and prepared this report to advise SRPO of specific areas where ONWI's plans for performance assessment might be improved. This report presents a framework for repository performance assessment that clearly identifies the relationships among the disposal problems, the processes underlying the problems, the tools for assessment (computer codes), and the data. In particular, the relationships among important processes and 26 model codes available to ONWI are indicated. A common suggestion for computer code verification and validation is the need for specific and unambiguous documentation of the results of performance assessment activities. A major portion of this report consists of status summaries of 27 model codes indicated as potentially useful by ONWI. The code summaries focus on three main areas: (1) the code's purpose, capabilities, and limitations; (2) status of the elements of documentation and review essential for code verification and validation; and (3) proposed application of the code for performance assessment of salt repository systems. 15 references, 6 figures, 4 tables

  19. The Social Determinants of Attitudes towards Nuclear Energy:Examination for the Value Mediated Mechanism(Special Issue Dedicated to Professor SUZUKI Tomihisa)

    OpenAIRE

    阪口, 祐介

    2016-01-01

    Since the 2011 Fukushima Daiichi nuclear power plant accident, the negative opinion to nuclear power plant has increased and the political debates over the pros and cons of nuclear energy has been activated. This paper attempts to reveal empirically the social determinants of attitudes towards nuclear energy. We focus on generation, gender, and social stratification as the determinants, and examine for the value mediated mechanism. Previous researches have indicated that women tend to have ne...

  20. Advanced nuclear technologies. Hearing before a subcommittee of the Committee on Appropriations, United States Senate, One Hundred Fifth Congress, First Session, Special Hearing

    International Nuclear Information System (INIS)

    1999-01-01

    This hearing focuses on the subject of advanced nuclear technologies; in particular, two aspects are of interest: The renewal of nuclear power in this country and furthering technologies for the future use of nuclear power. Several witnesses testified. Some topics covered by the witnesses were: reactor technologies; proliferation; and radioactive waste management

  1. Handbook on nuclear law

    International Nuclear Information System (INIS)

    Stoiber, C.; Baer, A.; Pelzer, N.; Tonhauser, W.

    2003-07-01

    The objective of this handbook is to assist States in drafting national legislation that provides an adequate legal basis for pursuing the economic and social benefits of nuclear energy and ionizing radiation. At the outset, therefore, it is important to offer a basic concept of nuclear law. In the light of these basic factors, nuclear law can be defined as: The body of special legal norms created to regulate the conduct of legal or natural persons engaged in activities related to fissionable materials, ionizing radiation and exposure to natural sources of radiation. Before attempting to identify which special aspects of nuclear law distinguish it from other types of law, it is important to highlight briefly the fundamental reason why a State would decide to make the major effort necessary in order to promulgate such legislation. Simply stated, the primary objective of nuclear law is: To provide a legal framework for conducting activities related to nuclear energy and ionizing radiation in a manner which adequately protects individuals, property and the environment. In light of this objective, it is particularly important that responsible authorities carefully assess their current nuclear energy activities and their plans for future nuclear energy development so that the legislation ultimately adopted is adequate. What are the characteristics of nuclear law that distinguish it from the other aspects of national law? A number of basic concepts, often expressed as fundamental principles, can be mentioned in this regard: (a) The safety principle; (b) The security principle; (c) The responsibility principle; (d) The permission principle; (e) The continuous control principle; (f) The compensation principle; (g) The sustainable development principle; (h) The compliance principle; (i) The independence principle; (j) The transparency principle; (k) The international co-operation principle

  2. Handbook on nuclear law

    International Nuclear Information System (INIS)

    Stoiber, C.; Baer, A.; Pelzer, N.; Tonhauser, W.

    2006-02-01

    The objective of this handbook is to assist States in drafting national legislation that provides an adequate legal basis for pursuing the economic and social benefits of nuclear energy and ionizing radiation. At the outset, therefore, it is important to offer a basic concept of nuclear law. In the light of these basic factors, nuclear law can be defined as: The body of special legal norms created to regulate the conduct of legal or natural persons engaged in activities related to fissionable materials, ionizing radiation and exposure to natural sources of radiation. Before attempting to identify which special aspects of nuclear law distinguish it from other types of law, it is important to highlight briefly the fundamental reason why a State would decide to make the major effort necessary in order to promulgate such legislation. Simply stated, the primary objective of nuclear law is: To provide a legal framework for conducting activities related to nuclear energy and ionizing radiation in a manner which adequately protects individuals, property and the environment. In light of this objective, it is particularly important that responsible authorities carefully assess their current nuclear energy activities and their plans for future nuclear energy development so that the legislation ultimately adopted is adequate. What are the characteristics of nuclear law that distinguish it from the other aspects of national law? A number of basic concepts, often expressed as fundamental principles, can be mentioned in this regard: (a) The safety principle. (B) The security principle. (C) The responsibility principle. (D) The permission principle. (E) The continuous control principle. (F) The compensation principle. (G) The sustainable development principle. (H) The compliance principle. (I) The independence principle. (J) The transparency principle. (K) The international co-operation principle

  3. Handbook on nuclear law

    International Nuclear Information System (INIS)

    Stoiber, C.; Baer, A.; Pelzer, N.; Tonhauser, W.

    2006-06-01

    The objective of this handbook is to assist States in drafting national legislation that provides an adequate legal basis for pursuing the economic and social benefits of nuclear energy and ionizing radiation. At the outset, therefore, it is important to offer a basic concept of nuclear law. In the light of these basic factors, nuclear law can be defined as: The body of special legal norms created to regulate the conduct of legal or natural persons engaged in activities related to fissionable materials, ionizing radiation and exposure to natural sources of radiation. Before attempting to identify which special aspects of nuclear law distinguish it from other types of law, it is important to highlight briefly the fundamental reason why a State would decide to make the major effort necessary in order to promulgate such legislation. Simply stated, the primary objective of nuclear law is: To provide a legal framework for conducting activities related to nuclear energy and ionizing radiation in a manner which adequately protects individuals, property and the environment. In light of this objective, it is particularly important that responsible authorities carefully assess their current nuclear energy activities and their plans for future nuclear energy development so that the legislation ultimately adopted is adequate. What are the characteristics of nuclear law that distinguish it from the other aspects of national law? A number of basic concepts, often expressed as fundamental principles, can be mentioned in this regard: (a) The safety principle. (B) The security principle. (C) The responsibility principle. (D) The permission principle. (E) The continuous control principle. (F) The compensation principle. (G) The sustainable development principle. (H) The compliance principle. (I) The independence principle. (J) The transparency principle. (K) The international co-operation principle

  4. Summary report on transportation of nuclear fuel materials in Japan : transportation infrastructure, threats identified in open literature, and physical protection regulations.

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, John Russell; Ouchi, Yuichiro (Japan Atomic Energy Agency, Japan); Furaus, James Phillip; Marincel, Michelle K.

    2008-03-01

    This report summarizes the results of three detailed studies of the physical protection systems for the protection of nuclear materials transport in Japan, with an emphasis on the transportation of mixed oxide fuel materials1. The Japanese infrastructure for transporting nuclear fuel materials is addressed in the first section. The second section of this report presents a summary of baseline data from the open literature on the threats of sabotage and theft during the transport of nuclear fuel materials in Japan. The third section summarizes a review of current International Atomic Energy Agency, Japanese and United States guidelines and regulations concerning the physical protection for the transportation of nuclear fuel materials.

  5. 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

  6. Specialization Patterns

    DEFF Research Database (Denmark)

    Schultz, Ulrik Pagh; Lawall, Julia Laetitia; Consel, Charles

    2000-01-01

    Design patterns offer many advantages for software development, but can introduce inefficiency into the final program. Program specialization can eliminate such overheads, but is most effective when targeted by the user to specific bottlenecks. Consequently, we propose that these concepts...... are complementary. Program specialization can optimize programs written using design patterns, and design patterns provide information about the program structure that can guide specialization. Concretely, we propose specialization patterns, which describe how to apply program specialization to optimize uses...... of design patterns. In this paper, we analyze the specialization opportunities provided by specific uses of design patterns. Based on the analysis of each design pattern, we define the associated specialization pattern. These specialization opportunities can be declared using the specialization classes...

  7. Non-nuclear radiological emergencies. Special plan for radiological risk of the Valencian Community; Emergencias radiológicas no nucleares. Plan especial ante el riesgo radiológico de la Comunidad Valenciana

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-01

    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. [Spanish] Tras la publicación de la Directriz Básica de Riesgo Radiológico, la Generalitat inició la redacción del correspondiente Plan Especial, con el objetivo de articular la respuesta de todos los organismos de Seguridad y Emergencias, y las Fuerzas Armadas, en una emergencia radiológica que afecte al territorio de la Comunidad Valenciana, bajo la dirección de un mando único. Aprobado y homologado el Plan Especial ante el Riesgo Radiológico, la Generalitat ha acometido el proceso de implantación que finalizará en junio de 2015. Por analogía con otros planes de la Comunidad, la implantación se estructura en una primera fase divulgativa e informativa, seguida de una fase formativa y de adiestramiento, culminando con un simulacro de activación del Plan

  8. Joint Analysis of Nuclear and Mitochondrial Variants in Age-Related Macular Degeneration Identifies Novel Loci TRPM1 and ABHD2/RLBP1

    NARCIS (Netherlands)

    Persad, P.J.; Heid, I.M.; Weeks, D.E.; Baird, P.N.; Jong, E.K.; Haines, J.L.; Pericak-Vance, M.A.; Scott, W.K.

    2017-01-01

    Purpose: Presently, 52 independent nuclear single nucleotide polymorphisms (nSNPs) have been associated with age-related macular degeneration (AMD) but their effects do not explain all its variance. Genetic interactions between the nuclear and mitochondrial (mt) genome may unearth additional genetic

  9. Special Nuclear Material Control by the Power Reactor Operator; Controle des Matieres Nucleaires Speciales par l'Exploitant d'une Centrale Nucleaire; Spetsial'nyj kontrol' nalichiya yadernykh materialov operatorom ehnergeticheskogo reaktora; Control de Materiales Nucleares Especiales por Parte de Quienes Operan el Reactor de Potencia

    Energy Technology Data Exchange (ETDEWEB)

    Cordin, R. A. [Yankee Atomic Electric Company, Boston, MA (United States)

    1966-02-15

    A relatively new and extremely valuable fuel for electric power production, uranium, requires very careful inventory control from the time the reactor operator assumes financial responsibility for this material until, as partially expended fuel, it is transferred to another facility and the remaining part of its initial value is recovered. Most power reactor operators were operating fossil-fuelled power plants before the advent of nuclear power and have long since established rather complete and adequate controls for these fossil fuels. The reactor operator must have no less adequate controls for the special nuclear material used in his nuclear plant. Power reactor, operation is not an ancient science and during its relatively short history our engineers and scientists have been constantly improving plant designs and methods of operation to reduce costs and make our nuclear plants competitive with fossil-fuelled conventional plants. Nuclear material management must be as modern and efficient as is humanly possible to ensure that technological advances leading to reduced costs are not lost by poor handling of nuclear fuel and the records pertaining to fuel inventory. Nuclear material management requires the maintaining of complete and informative records by the power reactor operator. These records need not be complex to satisfy the criteria of completeness and adequacy. In fact, simplicity is extremely desirable. Despite the fact that nuclear fuel is new and completely different to our conventional fuels no mystery should be attached thereto. Nuclear material control as part of nuclear material management is not limited to simple inventory work but it is the basis for a great deal of other activity that is an inherent part of any power reactor operations such as irradiated fuel shipments, reprocessing of spent fuel, with its associated accounting for reclaimed fuel and material produced during reactor operation, and the establishing and maintaining of an adequate

  10. 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

  11. Attributes identification of nuclear material by non-destructive radiation measurement methods

    International Nuclear Information System (INIS)

    Gan Lin

    2002-01-01

    Full text: The nuclear materials should be controlled under the regulation of National Safeguard System. The non-destructive analysis method, which is simple and quick, provide a effective process in determining the nuclear materials, nuclear scraps and wastes. The method play a very important role in the fields of nuclear material control and physical protection against the illegal removal and smuggling of nuclear material. The application of non-destructive analysis in attributes identification of nuclear material is briefly described in this paper. The attributes determined by radioactive detection technique are useful tolls to identify the characterization of special nuclear material (isotopic composition, enrichment etc.). (author)

  12. Safety philosophy for nuclear power plants in egypt

    International Nuclear Information System (INIS)

    Mervat, S.A.; Hammad, F.H.

    1988-01-01

    This work establishes the basic principles of a safety philosophy for nuclear power plants in egypt. A number of deterministic requirements stemming the multiple barriers and the defense-in-depth concept are emphasised. other requirements in the areas of siting, operational safety, safety analysis, special issues, and experience feedback are also identified. The role of international cooperation in nuclear safety technology-transfer and nuclear emergencies is highlighted. In addition probabilistic ally based guidelines are set for acceptable risk and dose limits

  13. Vertiefungskurs 2014. Safety margins in nuclear power plants. Identify, quantify and extend; Vertiefungskurs 2014 zum Thema ''Sicherheitsmargen in Kernkraftwerken. Identifizieren, quantifizieren, erweitern''

    Energy Technology Data Exchange (ETDEWEB)

    Rey, Matthias

    2015-02-15

    Fifteen speakers dealt with the topic safety margins in nuclear power plants from different points of view at the ''Vertiefungskurs 2014'' of the Nuklearforum Schweiz in Olten, 4 and 5 November 2014. In the context of the ''Vertiefungskurs 2014'' the safety margins in power plants were considered and quantified and possible extensions have been discussed. The conference started with an in-depth introduction of the basis design of existing nuclear power plants. Thereafter speakers told about the main topics emergency preparedness, knowledge management and safety retrofit of nuclear power plants in operation.

  14. Special protective concretes

    International Nuclear Information System (INIS)

    Bouniol, P.

    2001-01-01

    Concrete is the most convenient material when large-scale radiation protection is needed. Thus, special concretes for nuclear purposes are used in various facilities like reactors, reprocessing centers, storage sites, accelerators, hospitals with nuclear medicine equipment, food ionization centers etc.. The recent advances made in civil engineering for the improvement of concrete durability and compactness are for a large part transposable to protection concretes. This article presents the basic knowledge about protection concretes with the associated typological and technological aspects. A large part is devoted to the intrinsic properties of concretes and to their behaviour in irradiation and temperature conditions: 1 - definition and field of application of special protective concretes; 2 - evolution of concepts and technologies (durability of structures, techniques of formulation, new additives, market evolution); 3 - design of protective structures (preliminary study, radiation characteristics, thermal constraints, damping and dimensioning, mechanical criteria); 4 - formulation of special concretes (general principles, granulates, hydraulic binders, pulverulent additives, water/cement ratio, reference composition of some special concretes); 5 - properties of special concretes (damping and thermo-mechanical properties); 6 - induced-irradiation and temperature phenomena (activation, radiolysis, mineralogical transformations, drying, shrinking, creep, corrosion of reinforcement). (J.S.)

  15. Nuclear Law: A Key Against Nuclear Terrorism

    International Nuclear Information System (INIS)

    Cardozo, P.

    2004-01-01

    The role of the legal instruments in the war against nuclear terrorism. Control of radioactive sources. Elements of Nuclear Law: Definition: it is the body of special legislation that regulates the pacific uses of nuclear energy and the conduct of the persons engaged in activities related to fissionable materials and ionizing radiation . Objective: to provide a legal framework in order to protect individuals , property and the environment against the harmful effects of the use of nuclear energy and ionising radiation. Principles of nuclear energy legislation: safety principle, exclusively operator responsibility, authorization, independence of the regulatory body, inspections and enforcement, nuclear damage compensation, international cooperation. National regulatory infrastructure. Establishment of special law in Emergency Preparedness for nuclear or radiological disaster. IAEA Conventions. Transportation of nuclear material. IAEA regulations on radioactive material. Compensation for nuclear damage. Nuclear safety, security and terrorism. International and domestic instruments. Anti terrorism acts. International agreements on Safety Cooperation. (Author)

  16. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... physician who has specialized training in nuclear medicine will interpret the images and send a report to your referring physician. top of page What are the benefits vs. risks? Benefits The information provided by nuclear ...

  17. Children's (Pediatric) Nuclear Medicine

    Medline Plus

    Full Text Available ... Nuclear Medicine Children’s (pediatric) nuclear medicine imaging uses small amounts of radioactive materials called radiotracers, a special ... is a branch of medical imaging that uses small amounts of radioactive material to diagnose and determine ...

  18. Specialization Patterns

    OpenAIRE

    Schultz , Ulrik Pagh; Lawall , Julia ,; Consel , Charles

    1999-01-01

    Design patterns offer numerous advantages for software development, but can introduce inefficiency into the finished program. Program specialization can eliminate such overheads, but is most effective when targeted by the user to specific bottlenecks. Consequently, we propose to consider program specialization and design patterns as complementary concepts. On the one hand, program specialization can optimize object-oriented programs written using design patterns. On the other hand, design pat...

  19. Special Weapons

    Data.gov (United States)

    Federal Laboratory Consortium — Supporting Navy special weapons, the division provides an array of engineering services, technical publication support services, logistics support services, safety...

  20. Special training of shift personnel

    International Nuclear Information System (INIS)

    Martin, H.D.

    1981-01-01

    The first step of on-the-job training is practical observation phase in an operating Nuclear Plant, where the participants are assigned to shift work. The simulator training for operating personnel, for key personnel and, to some extent, also for maintenance personnel and specialists give the practical feeling for Nuclear Power Plant behaviour during normal and abnormal conditions. During the commissioning phase of the own Nuclear Power Plant, which is the most important practical training, the participants are integrated into the commissioning staff and assisted during their process of practical learning by special instructors. The preparation for the licensing exams is vitally important for shift personnel and special courses are provided after the first non-nuclear trial operation of the plant. Personnel training also includes performance of programmes and material for retraining, training of instructors and assistance in building up special training programmes and material as well as training centers. (orig./RW)

  1. Investigation: revelations about Three Mile Island disaster raise doubts over nuclear plant safety: a special facing south investigation by Sue Sturgis.

    Science.gov (United States)

    Sturgis, Sue

    2009-01-01

    A series of mishaps in a reactor at the Three Mile Island (TMI) nuclear plant led to the 1979 meltdown of almost half the uranium fuel and uncontrolled releases of radiation into the air and surrounding Susquehanna River. It was the single worst disaster ever to befall the U.S. nuclear power industry. Health physics technician Randall Thompson's story about what he witnessed while monitoring radiation there after the incident is being publicly disclosed for the first time. It is supported by a growing body of evidence and it contradicts the U.S. government's contention that the TMI accident posed no threat to the public. Thompson and his wife, a nuclear health physicist who also worked at TMI in the disaster's wake, warn that the government's failure to acknowledge the full scope of the disaster is leading officials to underestimate the risks posed by a new generation of nuclear power plants.

  2. Reperes, the information magazine of the Institute for Radiation Protection and Nuclear Safety - IRSN, No. 12 - January 2012, Special issue Fukushima - First lessons from the accident

    International Nuclear Information System (INIS)

    2012-01-01

    A first set of articles addresses the nuclear crisis in Japan (description of the accident, information mission sent by France, and support actions undertaken by France in Japan in the fields of education, civilian security, culture, sailing, media, dosimeters, robotics). A second set discusses lessons learned in terms of nuclear safety (complementary safety assessments, stress test in Gravelines), radiological consequences (impact on Japanese population, the Symbiose software, the Teleray network), crisis management, and research

  3. Trends in Special Library Buildings.

    Science.gov (United States)

    Cohen, Elaine; Cohen, Aaron

    1987-01-01

    Examines special library facilities, noting impact of organizational structure, and discusses the concept of information resources management in this context. Development of online and telecommunications systems, corporate and government campuses, and special library systems are identified as reasons for growth of special libraries. Furniture and…

  4. Nuclear Asia

    National Research Council Canada - National Science Library

    Ferguson, Joseph; Tarleton, Gael

    2004-01-01

    .... This event was an opportunity for policy makers, security analysts, nuclear scientists and engineers, regional experts, and military planners to share perspectives and identify those issues requiring...

  5. Specialized science.

    Science.gov (United States)

    Casadevall, Arturo; Fang, Ferric C

    2014-04-01

    As the body of scientific knowledge in a discipline increases, there is pressure for specialization. Fields spawn subfields that then become entities in themselves that promote further specialization. The process by which scientists join specialized groups has remarkable similarities to the guild system of the middle ages. The advantages of specialization of science include efficiency, the establishment of normative standards, and the potential for greater rigor in experimental research. However, specialization also carries risks of monopoly, monotony, and isolation. The current tendency to judge scientific work by the impact factor of the journal in which it is published may have roots in overspecialization, as scientists are less able to critically evaluate work outside their field than before. Scientists in particular define themselves through group identity and adopt practices that conform to the expectations and dynamics of such groups. As part of our continuing analysis of issues confronting contemporary science, we analyze the emergence and consequences of specialization in science, with a particular emphasis on microbiology, a field highly vulnerable to balkanization along microbial phylogenetic boundaries, and suggest that specialization carries significant costs. We propose measures to mitigate the detrimental effects of scientific specialism.

  6. Special geometry

    International Nuclear Information System (INIS)

    Strominger, A.

    1990-01-01

    A special manifold is an allowed target manifold for the vector multiplets of D=4, N=2 supergravity. These manifolds are of interest for string theory because the moduli spaces of Calabi-Yau threefolds and c=9, (2,2) conformal field theories are special. Previous work has given a local, coordinate-dependent characterization of special geometry. A global description of special geometries is given herein, and their properties are studied. A special manifold M of complex dimension n is characterized by the existence of a holomorphic Sp(2n+2,R)xGL(1,C) vector bundle over M with a nowhere-vanishing holomorphic section Ω. The Kaehler potential on M is the logarithm of the Sp(2n+2,R) invariant norm of Ω. (orig.)

  7. Environmental impact assessment of nuclear desalination

    International Nuclear Information System (INIS)

    2010-03-01

    Nuclear desalination is gaining interest among the IAEA Member States, as indicated by the planned projects, and it is expected that the number of nuclear desalination plants will increase in the near future. The IAEA has already provided its Member States with reports and documents that disseminate information regarding the technical and economic feasibility of nuclear desalination. With the rising environmental awareness, in the scope of IAEA's activities on seawater desalination using nuclear power, a need was identified for a report that would provide a generic assessment of the environmental issues in nuclear desalination. In order to offer an overview of specific environmental impacts which are to be expected, their probable magnitude, and recommended mitigation measures, this publication encompasses information provided by the IAEA Member States as well as other specialized sources. It is intended for decision makers and experts dealing with environmental, desalination and water management issues, offering insight into the environmental aspects that are essential in planning and developing nuclear desalination

  8. Reactor Noise: A study of Neutronic Fluctuations in Low-Power Nuclear Reactors, with Special Emphasis on Accurate Time-Domain Analysis. RCN Report

    Energy Technology Data Exchange (ETDEWEB)

    Dragt, J. B.

    1968-10-15

    Nuclear reactors can be considered as devices in which nuclear energy is produced as a result of neutron-induced fission reactions. Reactor physics is a branch of applied physics, and is concerned with the physical aspects of the design and study of nuclear reactors. The motivation is the achievement of configurations, which meet certain requirements regarding safety, reliability, economy, etc. The reactor physical method is to study neutron populations in a reactor. This study has two aspects : - the microscopic aspect: a study of the nuclear processes that take place. This aspect belongs to nuclear physics. Reaction probabilities can be expressed in cross sections,which are assumed to be known for the second part: - the macroscopic aspect, concerned with neutron migration and multiplication. All basic features may be traced back to a knowledge of neutron distribution functions. For most phenomena it is sufficient to study the singulet density, i.e. the mean number of neutrons per unit volume, unit velocity, moving in unit solid angle. For the subject of this thesis this singulet density will appear to be insufficient. The theory for the macroscopic aspect is part of statistical mechanics, and is closely related to other statistical theories, for phenomena like transfer of radiation in stellar atmosphere, penetration of radiation in scattering media, cosmic ray showers, etc.

  9. Reactor Noise: A study of Neutronic Fluctuations in Low-Power Nuclear Reactors, with Special Emphasis on Accurate Time-Domain Analysis. RCN Report

    International Nuclear Information System (INIS)

    Dragt, J.B.

    1968-10-01

    Nuclear reactors can be considered as devices in which nuclear energy is produced as a result of neutron-induced fission reactions. Reactor physics is a branch of applied physics, and is concerned with the physical aspects of the design and study of nuclear reactors. The motivation is the achievement of configurations, which meet certain requirements regarding safety, reliability, economy, etc. The reactor physical method is to study neutron populations in a reactor. This study has two aspects : - the microscopic aspect: a study of the nuclear processes that take place. This aspect belongs to nuclear physics. Reaction probabilities can be expressed in cross sections,which are assumed to be known for the second part: - the macroscopic aspect, concerned with neutron migration and multiplication. All basic features may be traced back to a knowledge of neutron distribution functions. For most phenomena it is sufficient to study the singulet density, i.e. the mean number of neutrons per unit volume, unit velocity, moving in unit solid angle. For the subject of this thesis this singulet density will appear to be insufficient. The theory for the macroscopic aspect is part of statistical mechanics, and is closely related to other statistical theories, for phenomena like transfer of radiation in stellar atmosphere, penetration of radiation in scattering media, cosmic ray showers, etc

  10. Differing professional opinions: 1987 special review panel

    International Nuclear Information System (INIS)

    1988-01-01

    In November 1987, the five-member Differing Professional Opinions Special Review Panel established by the Executive Director for Operations of the US Nuclear Regulatory Commission to review agency policies and procedures for handling differing professional opinions (DPOs) presented its findings and recommendations in NUREG-1290. The issuance of that report completed the first task of the panel's charter. In accordance with Manual chapter 4125, Section L, and the charter of the Special Review Panel, the panel's second task was to ''...review...the DPOs submitted subsequent to the previous Panel's review, in order to identify any employee whose DPO made a significant contribution to the Agency or to the public safety but who has not yet been recognized for such contribution.'' This Addendum provides the findings of that review

  11. Nuclear arms control in the post-Cold War era. New conditions, new requirements, and nonproliferation (with special emphasis on Japan and East Asia)

    International Nuclear Information System (INIS)

    Imai, Ryukichi

    1994-01-01

    The paper starts with a general survey of post-Cold War nuclear disarmament, pointing out Japan's positions, policies, and problems in the process. The discussion is not Japan-centered, nor is it an explanation of the Japanese view. It is useful, in this context, to recall that during the Cold War period, Japan was firmly in the ''Western Camp'', relying on the protection of the extended nuclear deterrence provided by the United States. This article is written with that history very much in mind, and by an author who for some years was in a position to represent Japan in such a context. (orig./DG)

  12. Steam generator and condenser design of WWER-1000 type of nuclear power plant

    International Nuclear Information System (INIS)

    Zare Shahneh, Abolghasem.

    1995-03-01

    Design process of steam generator and condenser at Russian nuclear power plant type WWER-1000 is identified. The four chapter of the books are organized as nuclear power plant, types of steam generators specially horizontal steam generator, process of steam generator design and the description of condenser and its process design

  13. Nuclear energy

    International Nuclear Information System (INIS)

    Panait, A.

    1994-01-01

    This is a general report presenting the section VII entitled Nuclear Power of the National Conference on Energy (CNE '94) held in Neptun, Romania, on 13-16 June 1994. The problems addressed were those relating to electric power produced by nuclear power plant, to heat secondary generation, to quality assurance, to safety, etc. A special attention was paid to the commissioning of the first Romanian nuclear power unit, the Cernavoda-1 reactor of CANDU type. The communications were grouped in four subsections. These were: 1. Quality assurance, nuclear safety, and environmental protection; 2. Nuclear power plant, commissioning, and operation; 3. Nuclear power plant inspection, maintenance, and repairs, heavy water technology; 4. Public opinion education. There were 22 reports, altogether

  14. Nuclear power

    International Nuclear Information System (INIS)

    King, P.

    1990-01-01

    Written from the basis of neutrality, neither for nor against nuclear power this book considers whether there are special features of nuclear power which mean that its development should be either promoted or restrained by the State. The author makes it dear that there are no easy answers to the questions raised by the intervention of nuclear power but calls for openness in the nuclear decision making process. First, the need for energy is considered; most people agree that energy is the power to progress. Then the historicalzed background to the current position of nuclear power is given. Further chapters consider the fuel cycle, environmental impacts including carbon dioxide emission and the greenhouse effect, the costs, safety and risks and waste disposal. No conclusion either for or against nuclear power is made. The various shades of opinion are outlined and the arguments presented so that readers can come to their own conclusions. (UK)

  15. Nuclear power

    International Nuclear Information System (INIS)

    Porter, Arthur.

    1980-01-01

    This chapter of the final report of the Royal Commission on Electric Power Planning in Ontario updates its interim report on nuclear power in Ontario (1978) in the light of the Three Mile Island accident and presents the commission's general conclusions and recommendations relating to nuclear power. The risks of nuclear power, reactor safety with special reference to Three Mile Island and incidents at the Bruce generating station, the environmental effects of uranium mining and milling, waste management, nuclear power economics, uranium supplies, socio-political issues, and the regulation of nuclear power are discussed. Specific recommendations are made concerning the organization and public control of Ontario Hydro, but the commission concluded that nuclear power is acceptable in Ontario as long as satisfactory progress is made in the disposal of uranium mill tailings and spent fuel wastes. (LL)

  16. Specialized languages

    DEFF Research Database (Denmark)

    Mousten, Birthe; Laursen, Anne Lise

    2016-01-01

    Across different fields of research, one feature is often overlooked: the use of language for specialized purposes (LSP) as a cross-discipline. Mastering cross-disciplinarity is the precondition for communicating detailed results within any field. Researchers in specialized languages work cross...... science fields communicate their findings. With this article, we want to create awareness of the work in this special area of language studies and of the inherent cross-disciplinarity that makes LSP special compared to common-core language. An acknowledgement of the importance of this field both in terms...... of more empirical studies and in terms of a greater application of the results would give language specialists in trade and industry a solid and updated basis for communication and language use....

  17. A review of the status of nuclear safety in the Central and East European Countries with special reference to the evaluation of the situation in Romania

    International Nuclear Information System (INIS)

    Webster, Simon

    2001-01-01

    This paper briefly presents the status of nuclear safety in the candidate countries in the light of the progress towards accession to the European Union, and draws particular attention to the recent evaluation made by the Atomic Questions Group of the Council of Ministers by reference to the general recommendations and the specific recommendations addressed to Romania appearing in the evaluation report. (author)

  18. Nuclear energy in Germany. Annual report 1999 - Deutsches Atomforum e.V.. Working report 1999. Special issue for members of Deutsches Atomforum e.V

    International Nuclear Information System (INIS)

    Gey, A.

    2000-01-01

    Total nuclear power generation in Germany in 1999 sums up to 169.7 billion kWh and thus almost equals the all-time high of the operating year 1997, which was at 170.4 billion kWh. Power generation in nuclear power plants has been contributing well a third of the total domestic power supply since 1988, which is about ten per cent of the national power consumption. This is one aspect of the information contained in the annual report of Deutsches Atomforum e.V. Expressing this 1999 output in terms of carbon dioxide emissions avoided, the figure is 170 million tonnes. This is equal to the annual CO2 emissions in 1999 emanating from road transport and traffic in Germany. From the very beginning of nuclear power generation in 1961 until today, aggregated nuclear power generation from uranium and plutonium fuels amounts to about 2.8 billion kWh, which means that over this period, more than two billion tonnes of carbon dioxide emissions have been avoided. (orig./CB) [de

  19. Seguro Nuclear

    International Nuclear Information System (INIS)

    Oliveira, S.C.C. de.

    1978-04-01

    A description of the constitutive elements of insurance and its features in the field of law, and special legislation about the matter are given. The relationship between the liability of the nuclear power plant operator and the international conventions about civil liability on nuclear damage is discussed. Some considerations on damage reparing in the United States, Germany, France and Spain are presented. (A.L.S.L.) [pt

  20. Nuclear astrophysics: An application of nuclear physics

    International Nuclear Information System (INIS)

    Fueloep, Z.

    2005-01-01

    Nuclear astrophysics, a fruitful combination of nuclear physics and astrophysics can be viewed as a special application of nuclear physics where the study of nuclei and their reactions are motivated by astrophysical problems. Nuclear astrophysics is also a good example for the state of the art interdisciplinary research. The origin of elements studied by geologists is explored by astrophysicists using nuclear reaction rates provided by the nuclear physics community. Due to the high interest in the field two recent Nuclear Physics Divisional Conferences of the European Physical Society were devoted to nuclear astrophysics and a new conference series entitled 'Nuclear Physics in Astrophysics' has been established. Selected problems of nuclear astrophysics will be presented emphasizing the interplay between nuclear physics and astrophysics. As an example the role of 14 N(p,r) 15 O reaction rate in the determination of the age of globular clusters will be discussed in details

  1. Efficacy of nuclear forensics

    International Nuclear Information System (INIS)

    Kazi, Reshmi

    2011-01-01

    In a strange turn of history, the threat of global nuclear war has gone down, but the risk of a nuclear attack has gone up. The danger of nuclear terrorism and ways to thwart it, tackle it and manage it in the event of an attack is increasingly gaining the attention of nuclear analysts all over the world. There is rising awareness among nuclear experts to develop mechanisms to prevent, deter and deal with the threat of nuclear terrorism. Nuclear specialists are seeking to develop and improve the science of nuclear forensics so as to provide faster analysis during a crisis. Nuclear forensics can play an important role in detecting illicit nuclear materials to counter trafficking in nuclear and radiological materials. An effective nuclear forensic and attribution strategy can enable policy makers, decision makers and technical managers to respond to situations involving interception of special nuclear materials

  2. Quantitative evaluation of subchondral bone injury of the plantaro-lateral condyles of the third metatarsal bone in Thoroughbred horses identified using nuclear scintigraphy: 48 cases.

    Science.gov (United States)

    Parker, R A; Bladon, B M; Parkin, T D H; Fraser, B S L

    2010-09-01

    Increased radio-isotope uptake (IRU) in the subchondral bone of the plantaro-lateral condyle of the third metatarsus (MTIII) is a commonly reported scintigraphic finding and potential cause of lameness in UK Thoroughbred racehorses in training and has not been fully documented. To characterise lameness attributable to IRU of the subchondral bone of MTIII, compare the scintigraphic findings of these horses with a normal population and evaluate the use of scintigraphy as an indicator of prognosis. IRU will be in significantly higher in horses with subchondral bone injury and will be related to prognosis and future racing performance. Data were analysed from 48 horses in which subchondral bone injury of the plantaro-lateral condyle of MTIII had been diagnosed using nuclear scintigraphy and that met the inclusion criteria. Data recorded included age, sex, trainer, racing discipline, lameness assessment, treatment regimes, radiographic and scintigraphic findings, response to diagnostic analgesia where performed and racing performance pre- and post diagnosis. Region of interest (ROI) counts were obtained for the plantar condyle and the mid diaphysis from the latero-medial view, the ratio calculated and then compared with a control group of clinically unaffected horses. The mean condyle mid-diaphysis ROI ratio was significantly (PThoroughbred racehorses. Nuclear scintigraphy is a useful diagnostic imaging modality in the detection of affected horses but is a poor indicator of prognosis for the condition. Better understanding of the clinical manifestations, diagnosis of and prognosis for subchondral bone injury will benefit the Thoroughbred industry in the UK.

  3. Decree of the State Office for Nuclear Safety No. 146/1997 of 18 June 1997 specifying activities which have an immediate impact on nuclear safety, and activities which are particularly important with respect to radiation protection, requirements for qualification and professional training, procedures for examining special professional competence and for granting certificates to selected personnel, and the scope and structure of documentation to be approved for permitting the training of selected personnel

    International Nuclear Information System (INIS)

    1997-01-01

    The Decree specifies requirements in the following fields: (a) activities which have an immediate impact on nuclear safety and activities which are particularly important with respect to radiation protection; (b) requirements for the qualification of selected personnel; (c) requirements for professional training of selected personnel of nuclear facilities and selected personnel handling ionizing radiation sources who are to gain special professional competence; (d) examination commission; (e) examination of special professional competence of selected personnel of nuclear facilities and selected personnel handling ionizing radiation sources; (f) granting permission to perform activities of selected personnel; and (g) scope and structure of documentation required to permit professional training of selected personnel of nuclear facilities and selected personnel handling ionizing radiation sources. (P.A.)

  4. Safety assessment and environmental impact assessment: Application to regulation of nuclear and radiation safety, with special consideration to Lepse related operations

    Energy Technology Data Exchange (ETDEWEB)

    Makarov, V.G. [Gosatomnadzor (Russian Federation); Smith, G.M.; Stone, D.M. [QuantiSci Ltd., Henley-on-Thames (United Kingdom)

    2000-11-01

    This report discusses the links between safety assessment and environmental impact assessment as applied to operations for unloading of spent nuclear fuel from the Lepse storage vessel. Regulatory responsibilities and regulatory requirements in these areas are under discussion and development in the Russian Federation and in other countries. The authors provide a briefing, based on inputs from Russian and western organisations, of their understanding of the situation at the time the work was done. They also make a variety of suggestions according to their perspectives. These suggestions should be relevant to the Lepse situation and to some other nuclear activities, bur do not represent the position of any particular organisation. Accordingly, this report is published by the SSI with the intention to promote discussion and interaction among relevant authorities.

  5. Safety assessment and environmental impact assessment: Application to regulation of nuclear and radiation safety, with special consideration to Lepse related operations

    International Nuclear Information System (INIS)

    Makarov, V.G.; Smith, G.M.; Stone, D.M.

    2000-11-01

    This report discusses the links between safety assessment and environmental impact assessment as applied to operations for unloading of spent nuclear fuel from the Lepse storage vessel. Regulatory responsibilities and regulatory requirements in these areas are under discussion and development in the Russian Federation and in other countries. The authors provide a briefing, based on inputs from Russian and western organisations, of their understanding of the situation at the time the work was done. They also make a variety of suggestions according to their perspectives. These suggestions should be relevant to the Lepse situation and to some other nuclear activities, bur do not represent the position of any particular organisation. Accordingly, this report is published by the SSI with the intention to promote discussion and interaction among relevant authorities

  6. Uses and examples of application of nuclear power in North Rhine-Westphalia with special regard to its contribution to a structural improvement

    International Nuclear Information System (INIS)

    Jehle, B.

    1978-01-01

    As examples of the implementation of nuclear energy, the alternative potentials for meeting electricity demand and for coal gasification in Nordrhein-Westfalen have been studied, with particular applications in the chemical and iron and steel industries of this state. The effects on competitiveness and choice of sites for these industries and on hard coal production have been quantified. The political significance of implementing nuclear energy for improving the economic structure depends not only on these individual economic effects but also on the contribution to growth and the effects which spread from these industries throughout the whole regional economy, which have also been quantified. The development of the chemical, iron and steel and coal industries can affect over 30% of the entire labour force of Nordrhein-Westfalen; thus for these industries energy-economic forces have appreciable structural effects. (orig.) [de

  7. Safety aspects of the modernization of I and C and process information in nuclear power plants with special regard to alarm annunciation

    Energy Technology Data Exchange (ETDEWEB)

    Seidel, F [Bundesamt fuer Strahlenschutz, Salzgitter (Germany)

    1997-09-01

    In particular for older German nuclear power plants there are projects to modernize I and C and process information systems. This modernization mainly aims at improvements in plant operation. For instance, using modern computing technology, the plant operation can be optimized, according to further details. Furthermore, the problem of spare-part keeping for out-dated components can be solved. For modernizing the I and C or the process computer system, safety-relevant aspects have to be taken into account. For instance, the compatibility of the system modification with the existing alarm annunciation concept shall be considered, and for each modernization step, the interfaces between the equipment of different safety significance shall be assessed and observed. The functions and the associated equipment have to be qualified in accordance to their safety significance. At present, the regulatory framework for computer-based instrumentation and control as well as for information systems is being elaborated in Germany and worldwide. Recently, the guidelines of the German Reactor Safety Commission have been extended with regard to the introduction and safety application of modern computer-based I and C in nuclear power plants. Furthermore, some of the essential requirements for design and qualification of modern I and C can be derived from the existing rules and standards. Particularly, concerning the alarm annunciation system, this report summarizes safety-relevant aspects of the modernization of the instrumentation and control system as well as the process information system in nuclear power plants. (author). 4 refs.

  8. Safety aspects of the modernization of I and C and process information in nuclear power plants with special regard to alarm annunciation

    International Nuclear Information System (INIS)

    Seidel, F.

    1997-01-01

    In particular for older German nuclear power plants there are projects to modernize I and C and process information systems. This modernization mainly aims at improvements in plant operation. For instance, using modern computing technology, the plant operation can be optimized, according to further details. Furthermore, the problem of spare-part keeping for out-dated components can be solved. For modernizing the I and C or the process computer system, safety-relevant aspects have to be taken into account. For instance, the compatibility of the system modification with the existing alarm annunciation concept shall be considered, and for each modernization step, the interfaces between the equipment of different safety significance shall be assessed and observed. The functions and the associated equipment have to be qualified in accordance to their safety significance. At present, the regulatory framework for computer-based instrumentation and control as well as for information systems is being elaborated in Germany and worldwide. Recently, the guidelines of the German Reactor Safety Commission have been extended with regard to the introduction and safety application of modern computer-based I and C in nuclear power plants. Furthermore, some of the essential requirements for design and qualification of modern I and C can be derived from the existing rules and standards. Particularly, concerning the alarm annunciation system, this report summarizes safety-relevant aspects of the modernization of the instrumentation and control system as well as the process information system in nuclear power plants. (author). 4 refs

  9. Nuclear power and nuclear safety 2006

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Kampmann, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2007-04-01

    The report is the fourth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2006 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power, and international relations and conflicts. (LN)

  10. Nuclear power and nuclear safety 2004

    International Nuclear Information System (INIS)

    2005-03-01

    The report is the second report in a new series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2004 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

  11. Nuclear power and nuclear safety 2005

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Kampman, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2006-03-01

    The report is the third report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe National Laboratory and the Danish Emergency Management Agency. The report for 2005 covers the following topics: status of nuclear power production, regional trends, reactor development and development of emergency management systems, safety related events of nuclear power and international relations and conflicts. (ln)

  12. Nuclear power and nuclear safety 2008

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Kampmann, D.

    2009-06-01

    The report is the fifth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2008 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events of nuclear power, and international relations and conflicts. (LN)

  13. Nuclear law: organization and responsibilities

    International Nuclear Information System (INIS)

    Ha Vinh Phuong.

    1986-01-01

    The paper emphasizes the importance of a special legislation insuring the governmental control of nuclear applications and other related activities. This legislation must establish the authority in charge for the development of peaceful applications of nuclear energy and the specialized body legally competent to insure an independent control of nuclear activities, it must define the principles and the conditions for licensing nuclear activities insuring the physical protection of nuclear materials and installations and must establish the specific rules for nuclear liability in the case of a nuclear accident. A list of IAEA publications related to the safety of nuclear power plants is included

  14. JENDL special purpose file

    International Nuclear Information System (INIS)

    Nakagawa, Tsuneo

    1995-01-01

    In JENDL-3,2, the data on all the reactions having significant cross section over the neutron energy from 0.01 meV to 20 MeV are given for 340 nuclides. The object range of application extends widely, such as the neutron engineering, shield and others of fast reactors, thermal neutron reactors and nuclear fusion reactors. This is a general purpose data file. On the contrary to this, the file in which only the data required for a specific application field are collected is called special purpose file. The file for dosimetry is a typical special purpose file. The Nuclear Data Center, Japan Atomic Energy Research Institute, is making ten kinds of JENDL special purpose files. The files, of which the working groups of Sigma Committee are in charge, are listed. As to the format of the files, ENDF format is used similarly to JENDL-3,2. Dosimetry file, activation cross section file, (α, n) reaction data file, fusion file, actinoid file, high energy data file, photonuclear data file, PKA/KERMA file, gas production cross section file and decay data file are described on their contents, the course of development and their verification. Dosimetry file and gas production cross section file have been completed already. As for the others, the expected time of completion is shown. When these files are completed, they are opened to the public. (K.I.)

  15. Review of the nuclear liability act

    International Nuclear Information System (INIS)

    1990-01-01

    There has always been concern that nuclear materials have the potential to cause injury and property damage. For this reason, nuclear operators have always been required by national regulatory authorities to exercise special precautions in the operation of their facilities. Federal legislation was drafted in Canada as the Nuclear Liability Act in 1970. The Act ensures that funds are available from all operators of nuclear facilities to provide financial compensation to third parties for injuries or damages suffered as a result of a nuclear incident; at the same time the Act provides protection to the operators by limiting their related liability. The Act also protects persons other than operators. The review of the Act has progressed in stages. The first stage was conducted by the staff of the Atomic Energy Control Board and catalogued previously identified difficulties with the Act. The second stage was a preliminary examination of the Act by an Interdepartmental Working Group. 2 figs

  16. Mutational analysis of the EMCV 2A protein identifies a nuclear localization signal and an eIF4E binding site

    International Nuclear Information System (INIS)

    Groppo, Rachel; Brown, Bradley A.; Palmenberg, Ann C.

    2011-01-01

    Cardioviruses have a unique 2A protein (143 aa). During genome translation, the encephalomyocarditis virus (EMCV) 2A is released through a ribosome skipping event mitigated through C-terminal 2A sequences and by subsequent N-terminal reaction with viral 3C pro . Although viral replication is cytoplasmic, mature 2A accumulates in nucleoli shortly after infection. Some protein also transiently associates with cytoplasmic 40S ribosomal subunits, an activity contributing to inhibition of cellular cap-dependent translation. Cardiovirus sequences predict an eIF4E binding site (aa 126-134) and a nuclear localization signal (NLS, aa 91-102), within 2A, both of which are functional during EMCV infection. Point mutations preventing eIF4E:2A interactions gave small-plaque phenotype viruses, but still inhibited cellular cap-dependent translation. Deletions within the NLS motif relocalized 2A to the cytoplasm and abrogated the inhibition of cap-dependent translation. A fusion protein linking the 2A NLS to eGFP was sufficient to redirect the reporter to the nucleus but not into nucleoli.

  17. Siting of nuclear power stations and the scope of preoperational investigations with special considerations of demographic aspects and the economic utilization of the neighbouring areas

    International Nuclear Information System (INIS)

    Bijak, J.

    1976-01-01

    The studies are presented on the location of atomic power stations in Poland made so far. The methods used in the studies are described which were done in two stages: preliminary location studies on the macroregional scale, and location studies on one or more of the chosen locations. Part one deals with general conditions which have to be met for location of atomic power stations and with preliminary assumptions accepted by GBS i PE ''Energoprojekt'' for location studies. Regulations and recommendations for establishing sites for atomic power stations are also given. Special location conditions are dealt with more extensively, the enviromental hazards and the need for their studies being particularly emphasized. Part two describes the scope of studies made prior to and after the time location investigations. Demographic studies and the economic utilization of the neighbouring areas are presented in more detail. (author)

  18. Siting of nuclear power stations and the scope of preoperational investigations with special considerations of demographic aspects and the economic utilization of the neighbouring areas. [Poland

    Energy Technology Data Exchange (ETDEWEB)

    Bijak, J [Biuro Studiow i Projektow ' Energoprojekt' , Warsaw (Poland)

    1976-01-01

    Studies are presented on the location of atomic power stations in Poland. The methods used in the studies are described which were done in two stages: preliminary location studies on the macroregional scale, and location studies on one or more of the chosen locations. Part one deals with general conditions which have to be met for location of atomic power stations and with preliminary assumptions accepted by GBS i PE ''Energoprojekt'' for location studies. Regulations and recommendations for establishing sites for atomic power stations are also given. Special location conditions are dealt with more extensively, the enviromental hazards and the need for their studies being particularly emphasized. Part two describes the scope of studies made prior to and after the time location investigations. Demographic studies and the economic utilization of the neighbouring areas are presented in more detail.

  19. Multiple nuclear and mitochondrial genotyping identifies emperors and large-eye breams (Teleostei : Lethrinidae) from New Caledonia and reveals new large-eye bream species

    OpenAIRE

    Borsa, Philippe; Collet, Adeline; Carassou, Laure; Ponton, Dominique; Chen, W. J.

    2010-01-01

    International audience; Species identification is fundamental to address questions about community ecology, biodiversity, conservation and resource management, at any life history stage. Current studies on fish larval ecology of tropical species are hampered by the lack of reliable and effective tools for identifying larvae at the species level. Emperors and large-eye breams comprise fish species from the perciform fish family Lethrinidae. They inhabit coastal and coral-reef habitats of the t...

  20. Visualizing the characteristics of a work process being observed from the main control room of nuclear power plants - identifying underlying requirements

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jinkyun; Jung, Wondea [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    One of the disseminated approaches is to identify and manage vulnerable tasks (i.e., error-prone tasks) by applying many kinds of human reliability assessment (HRA) techniques. That is, if HRA practitioners are able to identify plausible error forcing factors (e.g., performance shaping factors; PSFs) under a given task context, effective countermeasures that are helpful for reducing the possibility of human error can be drawn by deducing how to eliminate the associated PSFs. In order to reduce the variability of HRA results, the development of an objective criterion for determining the level of each PSF could be the most plausible countermeasure. In order to address this issue, this paper applied a process mining technique to the analysis of communication logs gathered from main control room (MCR) crews in NPPs, which could be useful for visualizing their characteristics in terms of the Work process. In this study, before providing additional information that is helpful for HRA practitioners in determining the quality of the Work process, three kinds of underlying requirements are identified. They are: (1) an ability to describe the flow of a work, (2) an ability to incorporate time and spatial information into the flow of a work, and (3) an ability to identify the flow of symptoms and/or knowledge being employed by an MCR crew. In order to satisfy these requirements, a couple of techniques can be used. This might allow partial pooling of log information according to how the information can be clustered.' In other words, the process mining technique is very useful for discovering the flow of a work being involved in a given situation, it is strongly expected that the analysis of communication logs that allow us to understand what and how they did in order to cope with a situation at hand. If so, it is possible to visualize necessary information that is essential for minimizing the variability of HRA practitioners who have to determine the quality of the Work

  1. Visualizing the characteristics of a work process being observed from the main control room of nuclear power plants - identifying underlying requirements

    International Nuclear Information System (INIS)

    Park, Jinkyun; Jung, Wondea

    2015-01-01

    One of the disseminated approaches is to identify and manage vulnerable tasks (i.e., error-prone tasks) by applying many kinds of human reliability assessment (HRA) techniques. That is, if HRA practitioners are able to identify plausible error forcing factors (e.g., performance shaping factors; PSFs) under a given task context, effective countermeasures that are helpful for reducing the possibility of human error can be drawn by deducing how to eliminate the associated PSFs. In order to reduce the variability of HRA results, the development of an objective criterion for determining the level of each PSF could be the most plausible countermeasure. In order to address this issue, this paper applied a process mining technique to the analysis of communication logs gathered from main control room (MCR) crews in NPPs, which could be useful for visualizing their characteristics in terms of the Work process. In this study, before providing additional information that is helpful for HRA practitioners in determining the quality of the Work process, three kinds of underlying requirements are identified. They are: (1) an ability to describe the flow of a work, (2) an ability to incorporate time and spatial information into the flow of a work, and (3) an ability to identify the flow of symptoms and/or knowledge being employed by an MCR crew. In order to satisfy these requirements, a couple of techniques can be used. This might allow partial pooling of log information according to how the information can be clustered.' In other words, the process mining technique is very useful for discovering the flow of a work being involved in a given situation, it is strongly expected that the analysis of communication logs that allow us to understand what and how they did in order to cope with a situation at hand. If so, it is possible to visualize necessary information that is essential for minimizing the variability of HRA practitioners who have to determine the quality of the Work

  2. 2008 GRS specialized forum

    International Nuclear Information System (INIS)

    Butz, H.P.

    2008-01-01

    After the successful trial run in 2007, the 2008 GRS Specialized Forum held at the Cologne Wolkenburg on April 7 and 8, 2008 was a full success. GRS, Gesellschaft fuer Anlagen- und Reaktorsicherheit, plans to resume in this way its GRS specialized lectures series with a tradition of many years. Approximately 180 participants from public authorities, licensees, the nuclear industry, research and engineering establishments as well as universities showed their interest in current GRS activities. On 2 days, only GRS experts presented fundamental and GRS-specific approaches in scientific analysis, new research findings, and possibilities of advancing scientific methods under the four headings of Reactor Safety Research and Evaluation, Topical Subjects of Reactor Safety, Radiation Protection Activities, and Repository Safety and Environmental Research. The discussions held after each presentation offered a number of critical, but valuable and welcome, contributions from the different perspectives of the discussants. (orig.)

  3. Results of special security inspection on improvement of security management setup in Head Office and Tsuruga Nuclear Power Station of the Japan Atomic Power Company and improvement of facilities in Tsuruga Nuclear Power Station

    International Nuclear Information System (INIS)

    1982-01-01

    In connection with the series of accidents in the Tsuruga Nuclear Power Station, the Agency of Natural Resources and Energy had instructed JAPC to make comprehensive inspection on the security management setup and to take improvement measures in the nuclear power station. The results of the subsequent inspection by ANRE confirmed that the improvements made by JAPC are adequate, and the following items are described: improvement of security management setup - communication and reporting in emergency, the management of inspection and maintenance records, work control and supervision in repair, improvement, etc., functional authority and responsibility in maintenance management, operation management, radiation control, personnel education; improvement of facilities - feed water heaters, laundry waste-water filter room, radioactive waste treatment facility, general drainage, concentrated waste liquid storage tanks in newly-built waste treatment building, etc. (J.P.N.)

  4. A very special relationship

    International Nuclear Information System (INIS)

    Arnold, L.M.

    1987-01-01

    The book shows why Britain adopted postwar defence policies that entailed nuclear weapon tests, why more than half of these tests were in Australia, where and how they took place, how the two nations cooperated and what was achieved at what cost. The radiation safety standards of the time and of the present day are compared and the safety aspects of the trials are looked at from the contemporary and present day viewpoint. The book covers the five series of trials in Australia and discusses the very special relationship that existed between the United Kingdom and Australia that made them possible. (author)

  5. Concerning major items in government ordinance requiring modification of part of enforcement regulation for law relating to control of nuclear material, nuclear fuel and nuclear reactor

    International Nuclear Information System (INIS)

    1989-01-01

    The report describes major items planned to be incorporated into the enforcement regulations for laws relating to control of nuclear material, nuclear fuel and nuclear reactor. The modifications have become necessary for the nation to conclude a nuclear material protection treaty with other countries. The modification include the definitions of 'special nuclear fuel substances' and 'special nuclear fuel substances' and 'special nuclear fuel substances subject to protection'. The modifications require that protective measures be taken when handling and transporting special nuclear fuel substances subject to protection. Transport of special nuclear fuel substances requires approval from the Prime Minister or Transport Minister. Transport of special nuclear fuel substances subject to protection should be conducted after notifying the prefectural Public Safety Commission. Transport of special nuclear fuel substances subject to protection requires the conclusion of arrangements among responsible persons and approval of them from the Prime Minister. (N.K.)

  6. International Specialization

    DEFF Research Database (Denmark)

    Kleindienst, Ingo; Geisler Asmussen, Christian; Hutzschenreuter, Thomas

    2012-01-01

    Whether and how international diversification and cross-border arbitrage affects firm performance remains one of the major unresolved research questions in the strategy and international business literatures. We propose that knowing how much a firm has internationally diversified tells us very...... little about performance implications, if we do not know, and do not ask, how the firm has diversified. Therefore, building on the two broad arguments of operating flexibility and location-specific commitment, we develop a theoretical framework that focuses on the extent to which a firm's international...... arbitrage strategy is characterized by specialization versus replication and argue that these different strategies may have differential impact on profitability and risk reduction. Developing a sophisticated measure of international specialization and using a unique panel data set of 92 German MNEs to test...

  7. INTERNET and information about nuclear sciences. The world wide web virtual library: nuclear sciences

    International Nuclear Information System (INIS)

    Kuruc, J.

    1999-01-01

    In this work author proposes to constitute new virtual library which should centralize the information from nuclear disciplines on the INTERNET, in order to them to give first and foremost the connection on the most important links in set nuclear sciences. The author has entitled this new virtual library The World Wide Web Library: Nuclear Sciences. By constitution of this virtual library next basic principles were chosen: home pages of international organizations important from point of view of nuclear disciplines; home pages of the National Nuclear Commissions and governments; home pages of nuclear scientific societies; web-pages specialized on nuclear problematic, in general; periodical tables of elements and isotopes; web-pages aimed on Chernobyl crash and consequences; web-pages with antinuclear aim. Now continue the links grouped on web-pages according to single nuclear areas: nuclear arsenals; nuclear astrophysics; nuclear aspects of biology (radiobiology); nuclear chemistry; nuclear company; nuclear data centres; nuclear energy; nuclear energy, environmental aspects of (radioecology); nuclear energy info centres; nuclear engineering; nuclear industries; nuclear magnetic resonance; nuclear material monitoring; nuclear medicine and radiology; nuclear physics; nuclear power (plants); nuclear reactors; nuclear risk; nuclear technologies and defence; nuclear testing; nuclear tourism; nuclear wastes; nuclear wastes. In these single groups web-links will be concentrated into following groups: virtual libraries and specialized servers; science; nuclear societies; nuclear departments of the academic institutes; nuclear research institutes and laboratories; centres, info links

  8. Special offer

    CERN Multimedia

    Staff Association

    2010-01-01

    Special offer for members of the Staff Association and their families 10% reduction on all products in the SEPHORA shop (sells perfume, beauty products etc.) in Val Thoiry ALL YEAR ROUND. Plus 20% reduction during their “vente privée”* three or four times a year. Simply present your Staff Association membership card when you make your purchase. * next “vente privée” from 24th to 29th May 2010  

  9. Special lecture

    International Nuclear Information System (INIS)

    Yoshikawa, H.

    1998-01-01

    In his special lecture, given at the Artsimovich-Kadomtsev Memorial Session of the 17th IAEA Fusion Energy Conference in Yokohama, October 1998, Prof. H. Yoshikawa stated that the fusion program had come to a crossroads. He was wondering whether the future would lead to cooperation between nations, striving to overcome the difficulties the world is confronted with, or if it would lead to despair

  10. Special offer

    CERN Multimedia

    Staff Association

    2011-01-01

    SPECIAL OFFER FOR OUR MEMBERS Tarif unique Adulte/Enfant Entrée Zone terrestre 19 euros instead of 23 euros Entrée “Zone terrestre + aquatique” 24 euros instead of 31 euros Free for children under 3, with limited access to the attractions. Walibi Rhône-Alpes is open daily from 22 June to 31 August, and every week end from 3 September until 31 October. Closing of the “zone aquatique” 11 September.

  11. Special effects.

    Science.gov (United States)

    Davis, Carol

    The nursing team on the day case ward at Alder Hey Hospital has introduced changes to the environment to help children with special needs, who often attend the ward repeatedly. Small changes, such as keeping colours on the ward neutral, can help children relax. Nurses contact parents a week before admission to find out about their child's likes and dislikes. Parents are encouraged to bring a child's favourite items with them. Operating sessions are scheduled to meet these children's needs.

  12. Nuclear medicine

    International Nuclear Information System (INIS)

    Kand, Purushottam

    2012-01-01

    Nuclear medicine is a specialized area of radiology that uses very small amounts of radioactive materials to examine organ function and structure. Nuclear medicine is older than CT, ultrasound and MRI. It was first used in patients over 60-70 years ago. Today it is an established medical specialty and offers procedures that are essential in many medical specialities like nephrology, pediatrics, cardiology, psychiatry, endocrinology and oncology. Nuclear medicine refers to medicine (a pharmaceutical) that is attached to a small quantity of radioactive material (a radioisotope). This combination is called a radiopharmaceutical. There are many radiopharmaceuticals like DTPA, DMSA, HIDA, MIBI and MDP available to study different parts of the body like kidneys, heart and bones etc. Nuclear medicine uses radiation coming from inside a patient's body where as conventional radiology exposes patients to radiation from outside the body. Thus nuclear imaging study is a physiological imaging, whereas diagnostic radiology is anatomical imaging. It combines many different disciplines like chemistry, physics mathematics, computer technology, and medicine. It helps in diagnosis and to treat abnormalities very early in the progression of a disease. The information provides a quick and accurate diagnosis of wide range of conditions and diseases in a person of any age. These tests are painless and most scans expose patients to only minimal and safe amounts of radiation. The amount of radiation received from a nuclear medicine procedure is comparable to, or often many times less than, that of a diagnostic X-ray. Nuclear medicine provides an effective means of examining whether some tissues/organs are functioning properly. Therapy using nuclear medicine in an effective, safe and relatively inexpensive way of controlling and in some cases eliminating, conditions such as overactive thyroid, thyroid cancer and arthritis. Nuclear medicine imaging is unique because it provides doctors with

  13. Historical aspects of the nuclear right development

    International Nuclear Information System (INIS)

    Puig, Diva E.

    1999-01-01

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

  14. Nuclear magnetic resonance and liquid chromatography-mass spectrometry combined with an incompleted separation strategy for identifying the natural products in crude extract

    Energy Technology Data Exchange (ETDEWEB)

    Dai Dongmei; He Jiuming [Key Laboratory of Bioactive Substances and Resource Utilization of Chinese Herbal Medicine, Ministry of Education, Institute of Materia Medica, Chinese Academy of Medical Sciences and Peking Union Medical College, 1 Xian Nong Tan Street, Beijing 100050 (China); Sun Ruixiang [Institute of Computing Technology, Chinese Academy of Sciences, Beijing 100080 (China); Zhang Ruiping [Key Laboratory of Bioactive Substances and Resource Utilization of Chinese Herbal Medicine, Ministry of Education, Institute of Materia Medica, Chinese Academy of Medical Sciences and Peking Union Medical College, 1 Xian Nong Tan Street, Beijing 100050 (China); Aisa, Haji Akber [Xinjiang Technological Institute of Physics and Chemistry, Chinese Academy of Sciences, Urumqi 830011 (China); Abliz, Zeper [Key Laboratory of Bioactive Substances and Resource Utilization of Chinese Herbal Medicine, Ministry of Education, Institute of Materia Medica, Chinese Academy of Medical Sciences and Peking Union Medical College, 1 Xian Nong Tan Street, Beijing 100050 (China)], E-mail: zeper@imm.ac.cn

    2009-01-26

    NMR and LC-MS combined with an incompleted separation strategy were proposed to the simultaneous structure identification of natural products in crude extracts, and a novel method termed as NMR/LC-MS parallel dynamic spectroscopy (NMR/LC-MS PDS) was developed to discover the intrinsic correlation between retention time (Rt), mass/charge (m/z) and chemical shift ({delta}) data of the same constituent from mixture spectra by the co-analysis of parallelly visualized multispectroscopic datasets from LC-MS and {sup 1}H NMR. The extracted ion chromatogram (XIC) and {sup 1}H NMR signals deriving from the same individual constituent were correlated through fraction ranges and intensity changing profiles in NMR/LC-MS PDS spectrum due to the signal amplitude co-variation resulted from the concentration variation of constituents in a series of incompletely separated fractions. NMR/LC-MS PDS was applied to identify 12 constituents in an active herbal extract including flavonol glycosides, which was separated into a series of fractions by flash column chromatography. The complementary spectral information of the same individual constituent in the crude extract was discovered simultaneously from mixture spectra. Especially, two groups of co-eluted isomers were identified successfully. The results demonstrated that NMR/LC-MS PDS combined with the incompleted separation strategy achieved the similar function of on-line LC-NMR-MS analysis in off-line mode and had the potential for simplifying and accelerating the analytical routes for structure identification of constituents in herbs or their active extracts.

  15. Nuclear magnetic resonance and liquid chromatography-mass spectrometry combined with an incompleted separation strategy for identifying the natural products in crude extract

    International Nuclear Information System (INIS)

    Dai Dongmei; He Jiuming; Sun Ruixiang; Zhang Ruiping; Aisa, Haji Akber; Abliz, Zeper

    2009-01-01

    NMR and LC-MS combined with an incompleted separation strategy were proposed to the simultaneous structure identification of natural products in crude extracts, and a novel method termed as NMR/LC-MS parallel dynamic spectroscopy (NMR/LC-MS PDS) was developed to discover the intrinsic correlation between retention time (Rt), mass/charge (m/z) and chemical shift (δ) data of the same constituent from mixture spectra by the co-analysis of parallelly visualized multispectroscopic datasets from LC-MS and 1 H NMR. The extracted ion chromatogram (XIC) and 1 H NMR signals deriving from the same individual constituent were correlated through fraction ranges and intensity changing profiles in NMR/LC-MS PDS spectrum due to the signal amplitude co-variation resulted from the concentration variation of constituents in a series of incompletely separated fractions. NMR/LC-MS PDS was applied to identify 12 constituents in an active herbal extract including flavonol glycosides, which was separated into a series of fractions by flash column chromatography. The complementary spectral information of the same individual constituent in the crude extract was discovered simultaneously from mixture spectra. Especially, two groups of co-eluted isomers were identified successfully. The results demonstrated that NMR/LC-MS PDS combined with the incompleted separation strategy achieved the similar function of on-line LC-NMR-MS analysis in off-line mode and had the potential for simplifying and accelerating the analytical routes for structure identification of constituents in herbs or their active extracts

  16. Selected topics in nuclear structure

    International Nuclear Information System (INIS)

    1994-01-01

    The collection of abstracts on selected topics in nuclear structure are given. Special attention pays to collective excitations and high-spin states of nuclei, giant resonance structure, nuclear reaction mechanisms and so on

  17. Nuclear Safety Regulations

    International Nuclear Information System (INIS)

    Novosel, N.; Prah, M.

    2008-01-01

    Beside new Ordinance on the control of nuclear material and special equipment ('Official Gazette' No. 15/08), from 2006 State Office for Nuclear Safety (SONS) adopted Ordinance on performing nuclear activities ('Official Gazette' No. 74/06) and Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety ('Official Gazette' No. 74/06), based on Nuclear Safety Act ('Official Gazette' No. 173/03). The Ordinance on performing nuclear activities regulates the procedure of notification of the intent to perform nuclear activities, submitting the application for the issue of a licence to perform nuclear activities, and the procedure for issuing decisions on granting a licence to perform a nuclear activity. The Ordinance also regulates the content of the forms for notification of the intent to perform nuclear activities, as well as of the application for the issue of a licence to perform the nuclear activity and the method of keeping the register of nuclear activities. According to the Nuclear Safety Act, nuclear activities are the production, processing, use, storage, disposal, transport, import, export, possession or other handling of nuclear material or specified equipment. The Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety regulates these mentioned conditions, whereas compliance is established by a decision passed by the SONS. Special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety are organizational, technical, technological conditions and established system of quality assurance. In 2007, State Office for Nuclear Safety finalized the text of new Ordinance on conditions for nuclear safety and protection with regard to the siting, design, construction, use and decommissioning of a facility in which a nuclear activity is

  18. Special energies and special frequencies

    International Nuclear Information System (INIS)

    Endrullis, M.; Englisch, H.

    1987-01-01

    ''Special frequencies'' have been asserted to be zeros of the density of frequencies corresponding to a random chain of coupled oscillators. Our investigation includes both this model and the random one-dimensional Schroedinger operator describing an alloy or its discrete analogue. Using the phase method we exactly determine a bilateral Lifsic asymptotic of the integrated density of states k(E) at special energies G s , which is not only of the classical type exp(-c/vertical strokeE-E s vertical stroke 1/2 ) but also exp(-c'/vertical strokeE-E s vertical stroke) is a typical behaviour. In addition, other asymptotics occur, e.g. vertical strokeE-E c vertical stroke c '', which show that k(E) need not be C ∞ . (orig.)

  19. A portable system for nuclear, chemical agent, and explosives identification

    International Nuclear Information System (INIS)

    Parker, W.E.; Buckley, W.M.; Kreek, S.A.; Mauger, G.J.; Lavietes, A.D.; Dougan, A.D.; Caffrey, A.J.

    2001-01-01

    The FRIS/PINS hybrid integrates the LLNL-developed Field Radionuclide Identification System (FRIS) with the INEEL-developed Portable Isotopic Neutron Spectroscopy (PINS) chemical assay system to yield a combined general radioisotope, special nuclear material, and chemical weapons/explosives detection and identification system. The PINS system uses a neutron source and a high-purity germanium γ-ray detector. The FRIS system uses an electromechanically cooled germanium detector and its own analysis software to detect and identify special nuclear material and other radioisotopes. The FRIS/PINS combined system also uses the electromechanically-cooled germanium detector. There is no other currently available integrated technology that can combine a prompt-gamma neutron-activation analysis capability for CWE with a passive radioisotope measurement and identification capability for special nuclear material

  20. A Portable System for Nuclear, Chemical Agent and Explosives Identification

    International Nuclear Information System (INIS)

    Parker, W.E.; Buckley, W.M.; Kreek, S.A.; Caffrey, A.J.; Mauger, G.J.; Lavietes, A.D.; Dougan, A.D.

    2000-01-01

    The FRIS/PINS hybrid integrates the LLNL-developed Field Radionuclide Identification System (FRIS) with the INEEL-developed Portable Isotopic Neutron Spectroscopy (PINS) chemical assay system to yield a combined general radioisotope, special nuclear material, and chemical weapons/explosives detection and identification system. The PINS system uses a neutron source and a high-purity germanium γ-ray detector. The FRIS system uses an electrochemically cooled germanium detector and its own analysis software to detect and identify special nuclear material and other radioisotopes. The FRIS/PINS combined system also uses the electromechanically-cooled germanium detector. There is no other currently available integrated technology that can combine an active neutron interrogation and analysis capability for CWE with a passive radioisotope measurement and identification capability for special nuclear material

  1. Development of database for spent fuel and special waste from the Spanish nuclear power plants; Desarrollo de la base de datos para el combustible gastado y residuos especiales de las centrales nucleares espanolas

    Energy Technology Data Exchange (ETDEWEB)

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

    2013-07-01

    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)

  2. An alternative host matrix based on iron phosphate glasses for the vitrification of specialized nuclear waste forms. Annual progress report, September 15, 1996 - September 14, 1997

    International Nuclear Information System (INIS)

    Day, D.E.; Marasinghe, K.; Ray, C.S.

    1997-01-01

    'Objectives of this project are to: (1) investigate the glass composition and processing conditions that yield optimum properties for iron phosphate glasses for vitrifying radioactive waste, (2) determine the atomic structure of iron phosphate glasses and the structure-property relationships, (3) determine how the physical and structural properties of iron phosphate glasses are affected by the addition of simulated high level nuclear waste components, and (4) investigate the process and products of devitrification of iron phosphate waste forms. The glass forming ability of about 125 iron phosphate melts has been investigated in different oxidizing to reducing atmospheres using various iron oxide raw materials such as Fe 2 O 3 , FeO, Fe 3 O 4 , and FeC 2 O 4 2H 2 O. The chemical durability, redox equilibria between Fe(II) and Fe(III), crystallization behavior and structural features for these glasses and their crystalline forms have been investigated using a variety of techniques including Mossbauer spectroscopy, X-ray absorption spectroscopy (XAS), X-ray photoelectron spectroscopy (XPS), Extended x-ray absorption fine structure (EXAFS) and X-ray absorption near edge structure (XANES) analysis, differential thermal and thermogravimetric analysis (DTA/TGA), and X-ray and neutron diffraction.'

  3. Development and application of anti-washout special material for long distance. Remediation work of contaminated water at Fukushima Daiichi Nuclear Power Plant underground structure

    International Nuclear Information System (INIS)

    Otsu, Hitoshi; Nishikori, Kazumasa; Sato, Keita; Hibi, Yasuki; Yanai, Shuji; Deguchi, Amane

    2017-01-01

    The seawater piping trench of Fukushima Daiichi Nuclear Power Station connects the screen pump room and turbine building. High concentration contaminated water stagnated in the trench due to the 2011 off the Pacific coast of Tohoku Earthquake, which caused a leakage accident. In order to solve the future leakage risk, a replacement work the liquid with cement was performed to remove contaminated water inside the trench. This paper explains the development of cement filler applied to the trench and the outline of its application work. Long-distance underwater fluid filler that can flow in the water throughout the longest 85 m long shafts was developed and its fluidity was confirmed in a laboratory and mockup device. In the field application, a cement manufacturing plant was set up in the power plant premises, and it took about a year to pour the cement into the trenches of No 2, 3, and 4 Units. To prevent the leakage of contaminated water in the trench, the cement pouring was performed while controlling the water level. Due to the high concentration of contaminated water, workers' radiation exposure management was conducted on a daily and monthly basis, and cumulative radiation exposure was strictly controlled. For radiation shielding, laying crushed stone and iron plate, installation of concrete protection wall and lead wool mat, and use of tungsten vest during work were practiced. Thanks to these measures, it was possible to reduce the exposure dose to about 27% of the originally predicted level. (A.O.)

  4. Special equipment support the fuel storage

    International Nuclear Information System (INIS)

    Vega, M. E.

    2014-01-01

    In the current juncture one of the keys to any company that works in a market that is as demanding as the nuclear, is its ability to developed new technological products that they can adapt to the different special situations/needs of nuclear Power Plants during their operating life. As an example, below are some of the specialized equipment that ENSA has been developing for more than thirty years that has been doing work in the area of fuel storage. (Author)

  5. Nuclear ships and their safety

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1961-04-15

    Several aspects of nuclear ship propulsion, with special reference to nuclear safety, were discussed at an international symposium at Taormina, Italy, from 14-18 November 1960. Discussions on specific topics are conducted, grouped under the following headings: Economics and National Activities in Nuclear Ship Propulsion; International Problems and General Aspects of Safety for Nuclear Ships; Nuclear Ship Projects from the Angle of Safety; Ship Reactor Problems; Sea Motion and Hull Problems; Maintenance and Refuelling Problems; and Safety Aspects of Nuclear Ship Operation.

  6. The System for Controlling Source and Special Nuclear Material at the Eurochemic Reprocessing Plant; Systeme de Controle des Matieres Nucleaires Brutes et Speciales a l'Usine de Traitement D'Eurochemic; Sistema kontrolya nad iskhodnym i spetsial'nym yadernym materialom na zavode evrokhimicheskoj kompanii po regeneratsii yadernogo topliva; Control de Materiales Nucleares Basicos y de Materiales Fisionables Especiales en la Planta de Regeneracion de la Eurochemic

    Energy Technology Data Exchange (ETDEWEB)

    Frenzel, W.; Schueller, W. [EUROCHEMIC, MOL (Belgium)

    1966-02-15

    Eurochemic is constructing a reprocessing plant near Mol (Belgium). The main characteristics of the plant and the different process steps are summarized. To maintain proper control of source and special nuclear material, the facilities of the company are divided into material balance areas. All transfers into and out of these areas are determined. Depending on their significance for the overall material balance, different precision requirements have been established according to a scale of significance which is briefly discussed. To adjust the book balance, physical inventories are periodically performed. The corresponding inventory procedures are outlined. The books used for nuclear materials accounting and the principles of the accounting system are summarized. (author) [French] La societe Eurochemic fait actuellement construire une usine de traitement chimique pres de Mol (Belgique). L'auteur indique succinctement les principales caracteristiques de l'usine et les differentes etapes du traitement. Pour assurer un controle correct des matieres nucleaires brutes et speciales, les installations d'Eurochemic sont divisees en secteurs de mesures. Tous les transferts entre ces secteurs de mesure sont determines quantitativement. Les mesures sont faites avec des degres de precision differents qui ont ete fixes en fonction de leur importance pour le bilan matieres general; les auteurs examinent brievement les criteres appliques a cette fin. Pour verifier le bilan, on procede periodiquement a des inventaires materiels. La facon dont sont menes ces inventaires est exposee dans ses grandes lignes. Les auteurs indiquent les livres utilises pour la comptabilite des matieres nucleaires et resument les principes du systeme comptable. (author) [Spanish] La compania Eurochemic esta construyendo una planta de regeneracion en Mol (Belgica). Los autores resumen las principales caracteristicas de la instalacion, y las distintas fases del proceso industrial. Para mantener un control

  7. Special offers

    CERN Multimedia

    Staff Association

    2011-01-01

    Are you a member of the Staff Association? Did you know that as a member you can benefit from the following special offers: BCGE (Banque Cantonale de Genève): personalized banking solutions with preferential conditions. TPG: reduced rates on annual transport passes for active and retired staff. Aquaparc: reduced ticket prices for children and adults at this Swiss waterpark in Le Bouveret. FNAC: 5% reduction on FNAC vouchers. For more information about all these offers, please consult our web site: http://association.web.cern.ch/association/en/OtherActivities/Offers.html

  8. Special Offers

    CERN Multimedia

    Association du personnel

    2011-01-01

    Are you a member of the Staff Association? Did you know that as a member you can benefit from the following special offers: BCGE (Banque Cantonale de Genève): personalized banking solutions with preferential conditions. TPG: reduced rates on annual transport passes for active and retired staff. Aquaparc: reduced ticket prices for children and adults at this Swiss waterpark in Le Bouveret. Walibi: reduced prices for children and adults at this French attraction park in Les Avenières. FNAC: 5% reduction on FNAC vouchers. For more information about all these offers, please consult our web site: http://association.web.cern.ch/association/en/OtherActivities/Offers.html

  9. Special offer

    CERN Multimedia

    Staff Association

    2011-01-01

    OFFRE SPECIALE POUR NOS MEMBRES Les vendredis 29 juillet, 5 et 12 août, Aquaparc fermera ses portes exceptionnellement à 22h00. Pour ces évènements, des tarifs défiant toute concurrence vous sont proposés. Au programme : Clown spécialiste de la sculpture de ballons de 16h00 à 21h00 Ambiance Salsa avec danseurs professionnel : Démonstration et Cours de Salsa. Les tarifs : Pour une entrée à partir de 15h00 : Enfant : CHF 22.- Adulte : CHF 26.-  

  10. Nuclear power: how and why

    International Nuclear Information System (INIS)

    1982-10-01

    The subject is discussed, with special reference to the United Kingdom, under the headings: the need for nuclear power; Britain's experience (nuclear reactors); the nuclear process; how fuel is made; recycling fuel; wastes and their treatment; decommissioning; fast reactors; nuclear fusion; safety and radiation. (U.K.)

  11. The abuse of nuclear power

    International Nuclear Information System (INIS)

    Hill, J.

    1977-01-01

    Different aspects of possible abuse of nuclear power by countries or individuals are discussed. Special attention is paid to the advantage of nuclear power, despite the risk of weapon proliferation or terrorism. The concepts of some nuclear power critics, concerning health risks in the nuclear sector are rejected as untrue and abusive

  12. Rock disposal problems identified

    Energy Technology Data Exchange (ETDEWEB)

    Knox, R

    1978-06-01

    Mathematical models are the only way of examining the return of radioactivity from nuclear waste to the environment over long periods of time. Work in Britain has helped identify areas where more basic data is required, but initial results look very promising for final disposal of high level waste in hard rock repositories. A report by the National Radiological Protection Board of a recent study, is examined.

  13. Special Memories at INIS

    International Nuclear Information System (INIS)

    Pistillo, Domenico

    2015-01-01

    INIS: a worldwide hub where nuclear information is preserved, validated, and made universally available. Within this special edition of the Newsletter, celebrating the 45th birthday of INIS, you will probably read this definition, and many more, of the International Nuclear Information System. However, INIS has some special aspects, not immediately visible to those who interact with the System and the INIS Secretariat, which make it unique in the scientific environment. In this article, I will try to share my experience with INIS and the memories that have stayed with me, even after my departure. I joined INIS in 2006 as an IT Systems Engineer. I must say that I found a very complex IT infrastructure with over 20 servers and several software applications which, given the small size of the INIS Unit, clearly reflected the multitude of activities INIS was (and still is) involved in. From the start, I felt that INIS was perceived in a different way by other people involved with Information Technology. In fact, since its birth in 1970, INIS has proven to be extremely innovative and open to embracing new technologies, compared with other parts of the Agency. For example, Livelink was proposed and installed for the first time by the INIS Unit before becoming the IAEA standard tool for enterprise document management, and presently, is uniquely and sharply customized to fulfill INIS’ critical weekly task of processing thousands of bibliographic and full text records

  14. Factors That Drive Youth Specialization.

    Science.gov (United States)

    Padaki, Ajay S; Popkin, Charles A; Hodgins, Justin L; Kovacevic, David; Lynch, Thomas Sean; Ahmad, Christopher S

    Specialization in young athletes has been linked to overuse injuries, burnout, and decreased satisfaction. Despite continued opposition from the medical community, epidemiological studies suggest the frequency is increasing. Extrinsic pressures in addition to individual aspirations drive this national trend in sports specialization. Descriptive epidemiology study. Level 3. A novel instrument assessing the driving factors behind youth specialization was generated by an interdisciplinary team of medical professionals. Surveys were administered to patients and athletes in the department's sports medicine clinic. The survey was completed by 235 athletes between 7 and 18 years of age, with a mean age of 13.8 ± 3.0 years. Athletes specialized at a mean age of 8.1 years, and 31% of athletes played a single sport while 58% played multiple sports but had a preferred sport. More than 70% of athletes had collegiate or professional ambitions, and 60% played their primary sport for 9 or more months per year, with players who had an injury history more likely to play year-round ( P specialized athletes reporting this significantly more often ( P = 0.04). Half of the athletes reported that sports interfered with their academic performance, with older players stating this more frequently ( P specializing in a single sport before starting high school. While intrinsic drive may identify healthy aspirations, extrinsic influences are prevalent in specialized athletes. Extrinsic factors contributing to youth specialization were identified and compounded the deleterious sequelae of youth athlete specialization.

  15. Radiation protection in nuclear energy. V.1

    International Nuclear Information System (INIS)

    1988-01-01

    The conference was convened to provide a forum for the exchange of international views on the principles of radiation protection for regulators and practitioners, to highlight issues of current importance, to examine the problems encountered in applying the principles of radiation protection, and, where possible, to identify generic solutions. A special session entitled ''The dose-response relationship: implications for nuclear energy'', and a panel on ''Radiation protection education and training'' were included in the conference programme. Refs, figs and tabs

  16. Sports Specialization in Young Athletes

    Science.gov (United States)

    Jayanthi, Neeru; Pinkham, Courtney; Dugas, Lara; Patrick, Brittany; LaBella, Cynthia

    2013-01-01

    Context: Sports specialization is intense training in 1 sport while excluding others. Sports specialization in early to middle childhood has become increasingly common. While most experts agree that some degree of sports specialization is necessary to achieve elite levels, there is some debate as to whether such intense practice time must begin during early childhood and to the exclusion of other sports to maximize potential for success. There is a concern that sports specialization before adolescence may be deleterious to a young athlete. Evidence Acquisition: PubMed and OVID were searched for English-language articles from 1990 to 2011 discussing sports specialization, expert athletes, or elite versus novice athletes, including original research articles, consensus opinions, and position statements. Results: For most sports, there is no evidence that intense training and specialization before puberty are necessary to achieve elite status. Risks of early sports specialization include higher rates of injury, increased psychological stress, and quitting sports at a young age. Sports specialization occurs along a continuum. Survey tools are being developed to identify where athletes fall along the spectrum of specialization. Conclusion: Some degree of sports specialization is necessary to develop elite-level skill development. However, for most sports, such intense training in a single sport to the exclusion of others should be delayed until late adolescence to optimize success while minimizing injury, psychological stress, and burnout. PMID:24427397

  17. Nuclear power and nuclear safety 2011

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Aage, H.K.; Kampmann, D.; Nystrup, P.E.; Thomsen, J.

    2012-07-01

    The report is the ninth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2011 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations and conflicts, and the Fukushima accident. (LN)

  18. Nuclear power and nuclear safety 2009

    International Nuclear Information System (INIS)

    Lauritzen, B.; Oelgaard, P.L.; Kampmann, D.; Nystrup, P.E.; Thorlaksen, B.

    2010-05-01

    The report is the seventh report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2009 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, conflicts and the European safety directive. (LN)

  19. Nuclear power and nuclear safety 2012

    International Nuclear Information System (INIS)

    Lauritzen, B.; Nonboel, E.; Israelson, C.; Kampmann, D.; Nystrup, P.E.; Thomsen, J.

    2013-11-01

    The report is the tenth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is prepared in collaboration between DTU Nutech and the Danish Emergency Management Agency. The report for 2012 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations and conflicts, and the results of the EU stress test. (LN)

  20. Special Offers

    CERN Multimedia

    Association du personnel

    2011-01-01

    Are you a member of the Staff Association? Did you know that as a member you can benefit from the following special offers: BCGE (Banque Cantonale de Genève): personalized banking solutions with preferential conditions.     TPG: reduced rates on annual transport passes for active and retired staff.     Aquaparc: reduced ticket prices for children and adults at this Swiss waterpark in Le Bouveret.     Walibi: reduced prices for children and adults at this French attraction park in Les Avenières.       FNAC: 5% reduction on FNAC vouchers.       For more information about all these offers, please consult our web site: http://association.web.cern.ch/association/en/OtherActivities/Offers.html