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International safeguards: experience and prospects

Description: IAEA safeguards have been applied to over 95% of the nuclear material and facilities outside of the nuclear weapon states. The present system of nonproliferation agreements implemented by IAEA safeguards likely will not be changed in the foreseeable future. Instruments used for nondestructive analysis are described: portable multichannel analyzer, high-level neutron coincidence counter, active well coincidence counter, and neutron coincidence collar. 7 figs. (DLC)
Date: January 1, 1982
Creator: Keepin, G. R. & Menlove, H. O.
Partner: UNT Libraries Government Documents Department
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Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume II. Proliferation resistance

Description: The purpose of this volume is limited to an assessment of the relative effects that particular choices of nuclear-power systems, for whatever reasons, may have on the possible spread of nuclear-weapons capabilities. This volume addresses the concern that non-nuclear-weapons states may be able to initiate efforts to acquire or to improve nuclear-weapons capabilities through civilian nuclear-power programs; it also addresses the concern that subnational groups may obtain and abuse the nuclear mat… more
Date: June 1, 1980
Partner: UNT Libraries Government Documents Department
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Safeguards and security research and development: Program status report, February-July 1981

Description: This report, one of a series of biannual progress reports, describes the status of research and development in the Safeguards and Security Program at Los Alamos from February-July 1981. Most work covered here is sponsored by the Office of Safeguards and Security of the Department of Energy; however, project activities that are technically closely related to nuclear safeguards and security also are included where appropriate for conveying information useful to the nuclear community. The report c… more
Date: April 1, 1982
Creator: Henry, C.N. & Walton, R.B. (comps.)
Partner: UNT Libraries Government Documents Department
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Calculation of parameters for inspection planning and evaluation: mixed-oxide fuel fabrication facilities

Description: As part of Task C.35 (Calculation of Parameters for Inspection Planning and Evaluation) of the US Program of Technical Assistance to IAEA Safeguards, Pacific Northwest Laboratory has performed some quantitative analyses of IAEA inspection activities for mixed-oxide fuel fabrication facilities. There were four distinct efforts involved in this task. These were as follows: show the effect on a material balance verification of using two variables measurement methods in some strata; perform additio… more
Date: August 1, 1982
Creator: Reardon, P.T. & Mullen, M.F.
Partner: UNT Libraries Government Documents Department
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Leach test methodology for the Waste/Rock Interactions Technology Program

Description: Experimental leach studies in the WRIT Program have two primary functions. The first is to determine radionuclide release from waste forms in laboratory environments which attempt to simulate repository conditions. The second is to elucidate leach mechanisms which can ultimately be incorporated into nearfield transport models. The tests have been utilized to generate rates of removal of elements from various waste forms and to provide specimens for surface analysis. Correlation between constitu… more
Date: May 1, 1980
Creator: Bradley, D. J.; McVay, G. L. & Coles, D. G.
Partner: UNT Libraries Government Documents Department
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Process monitoring for reprocessing plant safeguards: a summary review

Description: Process monitoring is a term typically associated with a detailed look at plant operating data to determine plant status. Process monitoring has been generally associated with operational control of plant processes. Recently, process monitoring has been given new attention for a possible role in international safeguards. International Safeguards Project Office (ISPO) Task C.59 has the goal to identify specific roles for process monitoring in international safeguards. As the preliminary effort a… more
Date: October 1, 1986
Creator: Kerr, H. T.; Ehinger, M. H.; Wachter, J. W. & Hebble, T. L.
Partner: UNT Libraries Government Documents Department
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Nuclear safeguards research and development. Program status report, October 1980-January 1981

Description: This report presents the status of the Nuclear Safeguards Research and Development Program pursued by the Energy, Chemistry-Materials Science, and Operational Security/Safeguards Divisions of the Los Alamos National Laboratory. Topics include nondestructive assay technology development and applications, international safeguards systems. Also discussed are training courses, technology transfer, analytical chemistry methods for fissionable materials safeguards, the Department of Energy Computer S… more
Date: November 1, 1981
Creator: Henry, C.N. (comp.)
Partner: UNT Libraries Government Documents Department
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Optimal allocation of International Atomic Energy Agency inspection resources

Description: The Safeguards Department of the International Atomic Energy Agency (IAEA) conducts inspections to assure the peaceful use of a state's nuclear materials and facilities. Because of limited resources for conducting inspections, the careful disposition of inspection effort among these facilities is essential if the IAEA is to attain its safeguards goals. This report describes an optimization procedure for assigning an inspection effort to maximize attainment of IAEA goals. The procedure does not … more
Date: December 1, 1987
Creator: Markin, J.T.
Partner: UNT Libraries Government Documents Department
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Diversion analysis and safeguards measures for liquid metal fast breeder reactors

Description: The general objective of the study is to perform a diversion analysis and an assessment of the available safeguards methods and systems for verifying inventory and flow of nuclear material in accessible and inaccessible areas of liquid-metal fast breeder reactor, LMFBR, systems. The study focuses primarily on the assembly-handling operations, assembly storage facilities, and reactor operations facilities relating to existing and/or near-term planned experimental, demonstration and prototypal re… more
Date: October 1, 1981
Creator: Persiani, P.J.
Partner: UNT Libraries Government Documents Department
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Status of safeguards instrumentation

Description: The International Atomic Energy Agency is performing safeguards at some nuclear power reactors, 50 bulk processing facilities, and 170 research facilities. Its verification activities require the use of instruments to measure nuclear materials and of surveillance instruments to maintain continuity of knowledge of the locations of nuclear materials. Instruments that are in use and under development to measure weight, volume, concentration, and isotopic composition of nuclear materials, and the m… more
Date: unknown
Creator: Higinbotham, W.A.
Partner: UNT Libraries Government Documents Department
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Nuclear energy at the turning point

Description: In deciding the future course of nuclear energy, it is necessary to re-examine man's long-term energy options, in particular solar energy and the breeder reactor. Both systems pose difficultiies: energy from the sun is likely to be expensive as well as limited, whereas a massive world-wide deployment of nuclear breeders will create problems of safety and of proliferation. Nuclear energy's long-term success depends on resolving both of these problems. Collocation of nuclear facilities with a sys… more
Date: July 1, 1977
Creator: Weinberg, A.M.
Partner: UNT Libraries Government Documents Department
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Measurement of actinide neutron cross sections

Description: The maintenance of strong scientific expertise is criticalto the U.S. nuclear attribution community. It is particularly importantto train students in actinide chemistry and physics. Neutroncross-section data are vital components to strategies for detectingexplosives and fissile materials, and these measurements requireexpertise in chemical separations, actinide target preparation, nuclearspectroscopy, and analytical chemistry. At the University of California,Berkeley and the Lawrence Berkeley N… more
Date: June 15, 2003
Creator: Firestone, Richard B.; Nitsche, Heino; Leung, Ka-Ngo; Perry, DaleL. & English, Gerald
Partner: UNT Libraries Government Documents Department
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Summary Report: First Research Coordination Meeting on ReferenceDatabase for Neutron Activation Analysis

Description: Potential problems associated with nuclear data for neutronactivation analysis were identified, the scope of the work to beundertaken was defined together with its priorities, and tasks wereassigned to participants. Data testing and measurements refer to gammaspectrumpeak evaluations, detector efficiency calibration, neutronspectrum characteristics and reference materials analysis.
Date: October 1, 2005
Creator: Firestone, Richard B. & Trkov, Andrej
Partner: UNT Libraries Government Documents Department
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Summary report on transportation of nuclear fuel materials in Japan : transportation infrastructure, threats identified in open literature, and physical protection regulations.

Description: 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 … more
Date: March 1, 2008
Creator: Cochran, John Russell; Ouchi, Yuichiro (Japan Atomic Energy Agency, Japan); Furaus, James Phillip & Marincel, Michelle K.
Partner: UNT Libraries Government Documents Department
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20th International Training Course (ITC-20) on the physical protection of nuclear facilities and materials evaluation report.

Description: The goal of this evaluation report is to provide the information necessary to improve the effectiveness of the ITC provided to the International Atomic Energy Agency Member States. This report examines ITC-20 training content, delivery methods, scheduling, and logistics. Ultimately, this report evaluates whether the course provides the knowledge and skills necessary to meet the participants needs in the protection of nuclear materials and facilities.
Date: September 1, 2008
Creator: Ramirez, Amanda Ann
Partner: UNT Libraries Government Documents Department
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Neutron Capture gamma ENDF libraries for modeling and identification of neutron sources

Description: There are a number of inaccuracies and data omissions with respect to gammas from neutron capture in the ENDF libraries used as field reference information and by modeling codes used in JTOT. As the use of Active Neutron interrogation methods is expanded, these shortfalls become more acute. A new, more accurate and complete evaluated experimental database of gamma rays (over 35,000 lines for 262 isotopes up to U so far) from thermal neutron capture has recently become available from the IAEA. T… more
Date: October 29, 2007
Creator: Sleaford, B
Partner: UNT Libraries Government Documents Department
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A Review of the IAEA Vulnerability Assessment Level Scheme: Applicabiliy to DTRA and DOE Programs in the FSU

Description: The International Atomic Energy Agency (IAEA) plans to use the Common Criteria, as the tool for developing graded and measurable evaluation criteria for information technology (IT) in safeguards systems in facilities subject to IAEA inspection. In their draft paper [ITSECSES] the IAEA defines a three-tiered Vulnerability Assessment Level (VAL) scheme. Each increased VAL level (1-3) defines additional and more stringent security and security-related requirements for the system developer, the sys… more
Date: December 6, 2001
Creator: Devaney, Mike M.; Hansen, Randy R.; Kouzes, Richard T. & Melton, Ronald B.
Partner: UNT Libraries Government Documents Department
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Evaluation of the DRAGON Code for VHTR Design Analysis.

Description: This letter report summarizes three activities that were undertaken in FY 2005 to gather information on the DRAGON code and to perform limited evaluations of the code performance when used in the analysis of the Very High Temperature Reactor (VHTR) designs. These activities include: (1) Use of the code to model the fuel elements of the helium-cooled and liquid-salt-cooled VHTR designs. Results were compared to those from another deterministic lattice code (WIMS8) and a Monte Carlo code (MCNP). … more
Date: January 12, 2006
Creator: Taiwo, T. A. & Kim, T. K.
Partner: UNT Libraries Government Documents Department
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New neutron cross section and fission yield data for SNManalysis

Description: Neutron cross-section data are fundamental for the design ofnuclear interrogation systems, the maintenance of nuclear materials andwaste, and the understanding the consequences of nuclear catastrophe.Although a large body of nuclear data exists, it is often old,unreliable, or poorly determined. For several years we have collaborated,as part of an IAEA Coordinated Research Project, to precisely measure thepartial thermal neutron gamma ray cross sections for all elements fromhydrogen to uranium a… more
Date: May 28, 2003
Creator: Firestone, R. B.; Molnar, G. L.; Revay, Zs. & Belgya, T.
Partner: UNT Libraries Government Documents Department
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Monte Carlo Modeling and Analyses of Yalina- Booster Subcritical Assembly Part II : Pulsed Neutron Source.

Description: One of the most reliable experimental methods for measuring the kinetic parameters of a subcritical assembly is the Sjoestrand method applied to the reaction rate generated from a pulsed neutron source. This study developed a new analytical methodology for characterizing the kinetic parameters of a subcritical assembly using the Sjoestrand method, which allows comparing the analytical and experimental time dependent reaction rates and the reactivity measurements. In this methodology, the reacti… more
Date: October 22, 2008
Creator: Talamo, A.; Gohar, M. Y. A. & Rabiti, C.
Partner: UNT Libraries Government Documents Department
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DETERMINATION OF REPORTABLE RADIONUCLIDES FOR DWPF SLUDGE BATCH 4 MACROBATCH 5

Description: The Waste Acceptance Product Specifications (WAPS)1 1.2 require that 'The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115'. As part of the strategy to meet WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives great… more
Date: May 30, 2008
Creator: Bannochie, C; Ned Bibler, N & David Diprete, D
Partner: UNT Libraries Government Documents Department
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Uranyl Nitrate Flow Loop

Description: The objectives of the work discussed in this report were to: (1) develop a flow loop that would simulate the purified uranium-bearing aqueous stream exiting the solvent extraction process in a natural uranium conversion plant (NUCP); (2) develop a test plan that would simulate normal operation and disturbances that could be anticipated in an NUCP; (3) use the flow loop to test commercially available flowmeters for use as safeguards monitors; and (4) recommend a flowmeter for production-scale te… more
Date: October 1, 2008
Creator: Ladd-Lively, Jennifer L.
Partner: UNT Libraries Government Documents Department
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Technical Review Report for the Safety Analysis Report for Packaging Model 9977 S-SARP-G-00001 Revision 2

Description: This Technical Review Report (TRR) summarizes the review findings for the Safety Analysis Report for Packaging (SARP) for the Model 9977 B(M)F-96 shipping container. The content analyzed for this submittal is Content Envelope C.1, Heat Sources, in assemblies of Radioisotope Thermoelectric Generators or food-pack cans. The SARP under review, i.e., S-SARP-G-00001, Revision 2 (August 2007), was originally referred to as the General Purpose Fissile Material Package. The review presented in this TRR… more
Date: October 4, 2007
Creator: DiSabatino, A; Hafner, R & West, M
Partner: UNT Libraries Government Documents Department
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Monte Carlo Modeling and Analyses of Yalina-Booster Subcritical Assembly Part 1: Analytical Models and Main Neutronics Parameters.

Description: This study was carried out to model and analyze the YALINA-Booster facility, of the Joint Institute for Power and Nuclear Research of Belarus, with the long term objective of advancing the utilization of accelerator driven systems for the incineration of nuclear waste. The YALINA-Booster facility is a subcritical assembly, driven by an external neutron source, which has been constructed to study the neutron physics and to develop and refine methodologies to control the operation of accelerator … more
Date: September 11, 2008
Creator: Talamo, A. & Gohar, M. Y. A.
Partner: UNT Libraries Government Documents Department
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