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Laszlo, G.; Ridder, P. de; Goldman, A.; Cappis, J.; Bievre, P. de
Safeguards and nuclear material management1991
Safeguards and nuclear material management1991
AbstractAbstract
[en] The Isotope Dilution Mass Spectrometry (IDMS) measurement technique provides a means for determining the unknown amount of various isotopes of an element in a sample solution of known mass. The sample solution is mixed with an auxiliary solution, or tracer, containing a known amount of the same element having the same isotopes but of different relative abundances or isotopic composition and the induced change in the isotopic composition measured by isotope mass spectrometry. The technique involves the measurement of the abundance ratio of each isotope to a (same) reference isotope in the sample solution, in the tracer solution and in the blend of the sample and tracer solution. These isotope ratio measurements, the known element amount in the tracer and the known mass of sample solution are used to calculate the unknown amount of one isotope in the sample solution. Subsequently the unknown amount of element is determined. The purpose of this paper is to examine the optimization of the ratio of the estimated unknown amount of element in the sample solution to the known amount of element in the tracer solution in order to minimize the relative uncertainty in the determination of the unknown amount of element
Secondary Subject
Source
Stanchi, L. (Commission of the European Communities, Ispra (Italy). Joint Research Centre); Commission of the European Communities, Luxembourg (Luxembourg); 745 p; 1991; p. 219-223; 13. Annual Symposium on Safeguards and Nuclear Material Management; Avignon (France); 14-16 May 1991
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Baecklin, A.; Hakansson, A.; Bjoerkholm, P.; Dyring, A.
Safeguards and nuclear material management1991
Safeguards and nuclear material management1991
AbstractAbstract
[en] A high-speed gamma-ray spectroscopy system for verification of nuclear fuel of the BWR type has been constructed. It uses a gamma-ray collimator, commercial high-speed NIM electronics, a fast PC and especially designed software and PC interface. It allows accurate determination of e.g. 154Eu in presence of strong activities of 134Cs and 137Cs. With this technique isotopic correlations may be used for independent determination of fuel parameters
Primary Subject
Source
Stanchi, L. (Commission of the European Communities, Ispra (Italy). Joint Research Centre); Commission of the European Communities, Luxembourg (Luxembourg); 745 p; 1991; p. 349-351; 13. Annual Symposium on Safeguards and Nuclear Material Management; Avignon (France); 14-16 May 1991
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BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CESIUM ISOTOPES, DEVELOPED COUNTRIES, ELECTRON CAPTURE RADIOISOTOPES, ENRICHED URANIUM REACTORS, EUROPE, EUROPIUM ISOTOPES, GE SEMICONDUCTOR DETECTORS, HOURS LIVING RADIOISOTOPES, INTERMEDIATE MASS NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, MEASURING INSTRUMENTS, MINUTES LIVING RADIOISOTOPES, NUCLEI, ODD-EVEN NUCLEI, ODD-ODD NUCLEI, POWER REACTORS, RADIATION DETECTORS, RADIOISOTOPES, RARE EARTH NUCLEI, REACTORS, SCANDINAVIA, SEMICONDUCTOR DETECTORS, SPECTROSCOPY, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, YEARS LIVING RADIOISOTOPES
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Krick, M.S.; Cowder, L.; Lagattu, A.; Lopatin, Y.; Czock, K.; Maltsev, V.; Chernikov, A.; Mokeenko, P.; D'Yadkov, K.; Ivanov, V.
Safeguards and nuclear material management1991
Safeguards and nuclear material management1991
AbstractAbstract
[en] Enriched uranium fuel assemblies were measured with an Active Well Coincidence Counter (AWCC) at the Beloyarskaya Nuclear Power Plant. Special AWCC inserts, electronics, and software were used. Stationary and scanning measurements were performed to establish calibrations and performance specifications for the assay of 235U and 235U/cm for BN600 fuel
Primary Subject
Source
Stanchi, L. (Commission of the European Communities, Ispra (Italy). Joint Research Centre); Commission of the European Communities, Luxembourg (Luxembourg); 745 p; 1991; p. 413-418; 13. Annual Symposium on Safeguards and Nuclear Material Management; Avignon (France); 14-16 May 1991
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ACTINIDE NUCLEI, ACTINIDES, ALPHA DECAY RADIOISOTOPES, BARYON REACTIONS, BREEDER REACTORS, DIAGNOSTIC TECHNIQUES, ELEMENTS, ENRICHED URANIUM, EPITHERMAL REACTORS, EVEN-ODD NUCLEI, FAST REACTORS, FBR TYPE REACTORS, HADRON REACTIONS, HEAVY NUCLEI, ISOMERIC TRANSITION ISOTOPES, ISOTOPE ENRICHED MATERIALS, ISOTOPES, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MATERIALS, METALS, MINUTES LIVING RADIOISOTOPES, NUCLEAR REACTIONS, NUCLEI, NUCLEON REACTIONS, PARTICLE SOURCES, POWER REACTORS, RADIATION SOURCES, RADIOISOTOPES, REACTORS, SODIUM COOLED REACTORS, URANIUM, URANIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
[en] The improvement of accuracy of nuclear physics data of transactinium nuclides, namely half-lives determination, is of vital importance for the development of nuclear physics assay and monitoring methods and ensuring their reliability. The half-life of 240Pu due to α radiation has been determined to be 6563+7 years. The value of 240Pu half-life due to spontaneous fission has not been precisely determined until recently. It varied from 1.15x1011 to 1.47x1011 years. The value of 240Pu spontaneous fission half-life was obtained using results of precision neutron flux measurements from two spherical metal plutonium samples with 240Pu content of about 90% and impurities less than 0.3%. The effect of self-multiplication specific neutron fluxes of (α,n) reactions and spontaneous fission of 238 Pu and 242Pu were taken into account. The obtained value of 240Pu spontaneous fission half-life consists of (1.15+0.02)x1011 years
Primary Subject
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Source
Stanchi, L. (Commission of the European Communities, Ispra (Italy). Joint Research Centre); Commission of the European Communities, Luxembourg (Luxembourg); 745 p; 1991; p. 497-501; 13. Annual Symposium on Safeguards and Nuclear Material Management; Avignon (France); 14-16 May 1991
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AbstractAbstract
[en] The application of new video surveillance electronics to safeguards has introduced an urgent need to formulate and adopt video standards that will ensure the highest possible video quality and the orderly introduction of data insertion. Standards will provide guidance in the application of image processing and digital techniques. Realistic and practical standards are a benefit to the IAEA, Member States, Support Programme equipment developers and facility operators, as they assist in the efficient utilisation of available resources. Moreover, standards shall provide a clear path for orderly introduction of newer technologies, whilst ensuring authentication and verification of the original image through the video process. Standards emerging from IAEA are an outcome of experience based on current knowledge, both within the safeguards arena and the video parent industry which comprises commercial and professional television. This paper provides a brief synopsis of recent developments which have highlighted the need for a surveillance based video standard together with a brief outline of these standards
Primary Subject
Source
Stanchi, L. (Commission of the European Communities, Ispra (Italy). Joint Research Centre); Commission of the European Communities, Luxembourg (Luxembourg); 745 p; 1991; p. 539-542; 13. Annual Symposium on Safeguards and Nuclear Material Management; Avignon (France); 14-16 May 1991
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AbstractAbstract
[en] As one of the most important industrial electronuclear states in the world, with a comprehensive national fuel cycle (from mines to reprocessing plants) on the one hand, and as a nuclear supplier as well as a nuclear weapon state on the other hand, France deemed it necessary to establish its own domestic safeguards system, in order to struggle against hazards of malevolence at the national level and to contribute efficiently to nuclear non-proliferation at the international level. The French legal regulations are based on the main following principles: (1) Licensing of activities related to import-export, to the possession or to the transportation of nuclear material; (2) Control performed by the operator, including NMCA, C/S an physical protection; (3) Inspection by the domestic Safeguards Authority; (4) Penalties. Specificities of domestic and international Safeguards (Euratom, IAEA) concerning objectives and scopes, information required, accounting, inspection types, R and D are illustrated and possible interactions are considered
Original Title
Le controle des matieres nucleaires en France
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Source
Stanchi, L. (Commission of the European Communities, Ispra (Italy). Joint Research Centre); Commission of the European Communities, Luxembourg (Luxembourg); 745 p; 1991; p. 3-12; 13. Annual Symposium on Safeguards and Nuclear Material Management; Avignon (France); 14-16 May 1991
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Vocino, V.; Binda, F.; Caravati, G.; D'Adamo, D.; Farese, N.; Maucq, T.; Remorini, B.
Safeguards and nuclear material management1991
Safeguards and nuclear material management1991
AbstractAbstract
[en] The isotopic composition of Plutonium 242 can not be measured by gamma spectroscopy. For this reason the gamma and passive neutron assay technique has been historically combined with the isotopic correlation to obtain the Plutonium 242 weight percentage. In this report experimental data from high resolution gamma spectroscopy, passive neutron assay and calorimetry were used to determine the weight of Plutonium, the respective weight percentages and the Americium 241 content without resorting to correlations. Data are presented for the plutonium oxide PERLA standards in the weight range of 100 g-2500 g. The data were collected in the JRC-PERLA facility and the results are compared to nominal values. The accuracy is always better than 0.5% on the total Plutonium mass for the 14 samples in this evaluation
Primary Subject
Secondary Subject
Source
Stanchi, L. (Commission of the European Communities, Ispra (Italy). Joint Research Centre); Commission of the European Communities, Luxembourg (Luxembourg); 745 p; 1991; p. 397-401; 13. Annual Symposium on Safeguards and Nuclear Material Management; Avignon (France); 14-16 May 1991
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ACTINIDE COMPOUNDS, ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, AMERICIUM ISOTOPES, CHALCOGENIDES, EVEN-EVEN NUCLEI, HEAVY NUCLEI, ISOTOPES, NUCLEI, ODD-EVEN NUCLEI, OXIDES, OXYGEN COMPOUNDS, PLUTONIUM COMPOUNDS, PLUTONIUM ISOTOPES, PLUTONIUM OXIDES, RADIOISOTOPES, SPECTROSCOPY, TRANSURANIUM COMPOUNDS, YEARS LIVING RADIOISOTOPES
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AbstractAbstract
[en] A number of reasons are given why more isotope-specific or isotope-related thinking should occur in measurements for Safeguards and Nuclear Material Management. It is isotopes which are fissile. Isotope-specific methods are available for direct quantitative determination of isotopes without a detour via elemental content with its problems in sample stoichiometry. Fissile isotopes in input solutions of reprocessing plants are already assayed by an isotope-specific method (IDMS*) and enable direct isotope-accountancy. Within the same amount of element, fissile isotopes (e.g. 235U) can be substituted for non-fissile isotopes (e.g. 238U) using isotope separation techniques of the near future leaving the total amount of element the same but changing the Safeguards character of the material drastically. Isotope-specific ratio of ratio measurement approaches, applied to IDMS have the potential of breaking through the 0.1% uncertainty barrier, at the same time making measurements easier. Large dynamic ratio measurement capability would enable the determination of the total amount of fissile isotope within a nuclear material batch (e.g. an input tank) directly against a small (ppm) but known added amount of a spike isotope (e.g. 233U) without the necessity of separate calibration of the tank for mass or volume of solution
Primary Subject
Source
Stanchi, L. (Commission of the European Communities, Ispra (Italy). Joint Research Centre); Commission of the European Communities, Luxembourg (Luxembourg); 745 p; 1991; p. 187-193; 13. Annual Symposium on Safeguards and Nuclear Material Management; Avignon (France); 14-16 May 1991
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Mayer, K.; Alonso, A.; Bievre, P. de; Lycke, W.; Bolle, W. de; Gallet, M.; Hendrickx, F.
Safeguards and nuclear material management1991
Safeguards and nuclear material management1991
AbstractAbstract
[en] The interest in the safeguards of fissile material focuses on a limited number of compounds which play key roles in the nuclear fuel cycle. Amongst these materials Uranium Dioxide pellets are of considerable importance as they enter the reactors in order to generate energy. In LWR's pellets with an initial 235U content of about 3 mass % are used, whereas natural or depleted material is applied for the breeding zone in FBR's. The 89/90 round o REIMEP covered Uranium materials with 235U abundances in the range of natural or depleted material. UO2 pellets were distributed to 21 laboratories for analysis. The participating laboratories were asked to determine the Uranium content and the isotopic composition of the material. The results reported by the participants are presented as graphs thus giving a picture of the state-of-the-practice
Primary Subject
Source
Stanchi, L. (Commission of the European Communities, Ispra (Italy). Joint Research Centre); Commission of the European Communities, Luxembourg (Luxembourg); 745 p; 1991; p. 207-209; 13. Annual Symposium on Safeguards and Nuclear Material Management; Avignon (France); 14-16 May 1991
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Verbruggen, A.; Gallet, M.; Hendrickx, F.; Bievre, P. de
Safeguards and nuclear material management1991
Safeguards and nuclear material management1991
AbstractAbstract
[en] An highly enriched 244Pu isotopic reference material (CBNM IRM-042a) has been prepared and certified for 244Pu isotope concentration. The certified value of (2.257 7 ± 0.004 4).1018 atoms 242Pu.kg-1 of solution has been established by isotope dilution mass spectrometry. The plutonium isotopic composition has been determined by thermal ionization mass spectrometry and calibration of these measurements by means of synthetic 242Pu/239Pu mixtures. The isotopic reference material is supplied in a sealed glass ampoule containing approximately 10 g of a 5M nitric acid solution at an approximate concentration of 1 μg Pu per g solution. This isotopic reference material is part of a systematic CBNM programme to supply spike isotopic reference materials of various isotopes at different concentrations
Primary Subject
Source
Stanchi, L. (Commission of the European Communities, Ispra (Italy). Joint Research Centre); Commission of the European Communities, Luxembourg (Luxembourg); 745 p; 1991; p. 241-244; 13. Annual Symposium on Safeguards and Nuclear Material Management; Avignon (France); 14-16 May 1991
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ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, DISPERSIONS, EVEN-EVEN NUCLEI, HEAVY NUCLEI, HOMOGENEOUS MIXTURES, HYDROGEN COMPOUNDS, INORGANIC ACIDS, INORGANIC COMPOUNDS, ISOTOPE APPLICATIONS, ISOTOPES, MIXTURES, NITROGEN COMPOUNDS, NUCLEI, OXYGEN COMPOUNDS, PLUTONIUM ISOTOPES, RADIATION SOURCES, RADIOISOTOPES, SPECTROSCOPY, STANDARDS, TRACER TECHNIQUES, YEARS LIVING RADIOISOTOPES
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