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Title: SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data

Abstract

SFCOMPO-2.0 is the new release of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) database of experimental assay measurements. These measurements are isotopic concentrations from destructive radiochemical analyses of spent nuclear fuel (SNF) samples. We supplement the measurements with design information for the fuel assembly and fuel rod from which each sample was taken, as well as with relevant information on operating conditions and characteristics of the host reactors. These data are necessary for modeling and simulation of the isotopic evolution of the fuel during irradiation. SFCOMPO-2.0 has been developed and is maintained by the OECD NEA under the guidance of the Expert Group on Assay Data of Spent Nuclear Fuel (EGADSNF), which is part of the NEA Working Party on Nuclear Criticality Safety (WPNCS). Significant efforts aimed at establishing a thorough, reliable, publicly available resource for code validation and safety applications have led to the capture and standardization of experimental data from 750 SNF samples from more than 40 reactors. These efforts have resulted in the creation of the SFCOMPO-2.0 database, which is publicly available from the NEA Data Bank. Our paper describes the new database, and applications of SFCOMPO-2.0 for computer code validation, integralmore » nuclear data benchmarking, and uncertainty analysis in nuclear waste package analysis are briefly illustrated.« less

Authors:
 [1];  [2];  [2];  [3];  [1];  [4];  [1];  [5];  [6];  [7];  [8];  [9];  [9];  [10];  [8];  [11];  [12]; ORCiD logo [2];  [10];  [13] more »;  [14];  [15];  [2];  [16];  [17];  [18];  [19];  [1];  [10];  [20];  [21];  [15];  [22];  [23];  [24];  [25];  [25] « less
  1. Organisation for Economic Co-operation and Development (OECD), Boulogne-Billancourt (France)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. Nuclear Safety Council, Madrid (Spain)
  4. National Organization for Radioactive Waste and Enriched Fissile Fuel (NIRAS/ONDRAF), Bussels (Belgium)
  5. Vuje, Inc., Trnava (Slovak Republic)
  6. ENUSA Industries, Madrid (Spain)
  7. Julich Research Centre (Germany)
  8. Nuclear Research Inst., Rez (Czech Republic)
  9. Belgian Nuclear Research Center (SCK-CEN), Mol (Belgium)
  10. Society for Plant and Reactor Safety (GRS), Munich (Germany)
  11. AREVA GmbH, Erlangen (Germany)
  12. Centre for Energy Research Hungarian Academy of Sciences, Budapest (Hungary)
  13. UK National Nuclear Lab., Cumbria (United Kingdom)
  14. UK National Nuclear Lab., Sellafield (United Kingdom)
  15. Engineering and Analysis of Shields (SEA), Madrid (Spain)
  16. US Nuclear Regulatory Commission (NRC), Rockville, MD (United States)
  17. Industrial Power Corporation (TVO), Helsinki (Finland)
  18. Radiation and Nuclear Safety Authority (STUK), Helsinki (Finland)
  19. Federal Office for Radiation Protection (BFS), Salzgitter (Germany)
  20. Japan Atomic Energy Agency (JAEA), Ibaraki (Japan)
  21. Scientific Engineering Consultants GmbH (WTI), Julich (Germany)
  22. Joint Research Centre Karlsruhe, Eggenstein-Leopoldshafen (Germany)
  23. Paul Scherrer Inst. (PSI), Villigen (Switzerland)
  24. Japan Atomic Energy Agency (JAEA), Tokai (Japan)
  25. Nuclear Regulation Authority, Tokyo (Japan)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1376611
Grant/Contract Number:
AC05-00OR22725
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Annals of Nuclear Energy (Oxford)
Additional Journal Information:
Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 110; Journal Issue: C; Journal ID: ISSN 0306-4549
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 97 MATHEMATICS AND COMPUTING; SFCOMPO; Spent nuclear fuel database; Radiochemical assay data; Experimental isotopic compositions; Nuclear fuel depletion; Nuclear fuel evolution; Code validation; Integral benchmarks

Citation Formats

Michel-Sendis, F., Gauld, I., Martinez, J. S., Alejano, C., Bossant, M., Boulanger, D., Cabellos, O., Chrapciak, V., Conde, J., Fast, I., Gren, M., Govers, K., Gysemans, M., Hannstein, V., Havlůj, F., Hennebach, M., Hordosy, G., Ilas, G., Kilger, R., Mills, R., Mountford, D., Ortego, P., Radulescu, G., Rahimi, M., Ranta-Aho, A., Rantamäki, K., Ruprecht, B., Soppera, N., Stuke, M., Suyama, K., Tittelbach, S., Tore, C., Winckel, S. Van, Vasiliev, A., Watanabe, T., Yamamoto, Toru, and Yamamoto, Toshihisa. SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data. United States: N. p., 2017. Web. doi:10.1016/j.anucene.2017.07.022.
Michel-Sendis, F., Gauld, I., Martinez, J. S., Alejano, C., Bossant, M., Boulanger, D., Cabellos, O., Chrapciak, V., Conde, J., Fast, I., Gren, M., Govers, K., Gysemans, M., Hannstein, V., Havlůj, F., Hennebach, M., Hordosy, G., Ilas, G., Kilger, R., Mills, R., Mountford, D., Ortego, P., Radulescu, G., Rahimi, M., Ranta-Aho, A., Rantamäki, K., Ruprecht, B., Soppera, N., Stuke, M., Suyama, K., Tittelbach, S., Tore, C., Winckel, S. Van, Vasiliev, A., Watanabe, T., Yamamoto, Toru, & Yamamoto, Toshihisa. SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data. United States. doi:10.1016/j.anucene.2017.07.022.
Michel-Sendis, F., Gauld, I., Martinez, J. S., Alejano, C., Bossant, M., Boulanger, D., Cabellos, O., Chrapciak, V., Conde, J., Fast, I., Gren, M., Govers, K., Gysemans, M., Hannstein, V., Havlůj, F., Hennebach, M., Hordosy, G., Ilas, G., Kilger, R., Mills, R., Mountford, D., Ortego, P., Radulescu, G., Rahimi, M., Ranta-Aho, A., Rantamäki, K., Ruprecht, B., Soppera, N., Stuke, M., Suyama, K., Tittelbach, S., Tore, C., Winckel, S. Van, Vasiliev, A., Watanabe, T., Yamamoto, Toru, and Yamamoto, Toshihisa. 2017. "SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data". United States. doi:10.1016/j.anucene.2017.07.022.
@article{osti_1376611,
title = {SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data},
author = {Michel-Sendis, F. and Gauld, I. and Martinez, J. S. and Alejano, C. and Bossant, M. and Boulanger, D. and Cabellos, O. and Chrapciak, V. and Conde, J. and Fast, I. and Gren, M. and Govers, K. and Gysemans, M. and Hannstein, V. and Havlůj, F. and Hennebach, M. and Hordosy, G. and Ilas, G. and Kilger, R. and Mills, R. and Mountford, D. and Ortego, P. and Radulescu, G. and Rahimi, M. and Ranta-Aho, A. and Rantamäki, K. and Ruprecht, B. and Soppera, N. and Stuke, M. and Suyama, K. and Tittelbach, S. and Tore, C. and Winckel, S. Van and Vasiliev, A. and Watanabe, T. and Yamamoto, Toru and Yamamoto, Toshihisa},
abstractNote = {SFCOMPO-2.0 is the new release of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) database of experimental assay measurements. These measurements are isotopic concentrations from destructive radiochemical analyses of spent nuclear fuel (SNF) samples. We supplement the measurements with design information for the fuel assembly and fuel rod from which each sample was taken, as well as with relevant information on operating conditions and characteristics of the host reactors. These data are necessary for modeling and simulation of the isotopic evolution of the fuel during irradiation. SFCOMPO-2.0 has been developed and is maintained by the OECD NEA under the guidance of the Expert Group on Assay Data of Spent Nuclear Fuel (EGADSNF), which is part of the NEA Working Party on Nuclear Criticality Safety (WPNCS). Significant efforts aimed at establishing a thorough, reliable, publicly available resource for code validation and safety applications have led to the capture and standardization of experimental data from 750 SNF samples from more than 40 reactors. These efforts have resulted in the creation of the SFCOMPO-2.0 database, which is publicly available from the NEA Data Bank. Our paper describes the new database, and applications of SFCOMPO-2.0 for computer code validation, integral nuclear data benchmarking, and uncertainty analysis in nuclear waste package analysis are briefly illustrated.},
doi = {10.1016/j.anucene.2017.07.022},
journal = {Annals of Nuclear Energy (Oxford)},
number = C,
volume = 110,
place = {United States},
year = 2017,
month = 8
}

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  • Experimental data on the isotopic concentrations in irradiated nuclear fuel represent one of the primary methods for validating computational methods and nuclear data used for reactor and spent fuel depletion simulations that support nuclear fuel cycle safety and safeguards programs. Measurement data have previously not been available to users in a centralized or searchable format, and the majority of accessible information has been, for the most part, limited to light-water-reactor designs. This paper describes a recent initiative to compile spent fuel benchmark data for additional reactor designs used throughout the world that can be used to validate computer model simulationsmore » that support nuclear energy and nuclear safeguards missions. Experimental benchmark data have been expanded to include VVER-440, VVER-1000, RBMK, graphite moderated MAGNOX, gas cooled AGR, and several heavy-water moderated CANDU reactor designs. Additional experimental data for pressurized light water and boiling water reactor fuels has also been compiled for modern assembly designs and more extensive isotopic measurements. These data are being compiled and uploaded to a recently revised structured and searchable database, SFCOMPO, to provide the nuclear analysis community with a centrally-accessible resource of spent fuel compositions that can be used to benchmark computer codes, models, and nuclear data. The current version of SFCOMPO contains data for eight reactor designs, 20 fuel assembly designs, more than 550 spent fuel samples, and measured isotopic data for about 80 nuclides.« less
  • An essential component of computational modeling and simulation is the availability of well-qualified experimental benchmark data against which calculation systems can be validated and the bias and uncertainty associated with the codes and data can be evaluated. The validation process is extremely important for safety and licensing to demonstrate that adequate margins for uncertainty have been included in the calculations. For safety evaluations involving spent nuclear fuel, the isotopic compositions and resulting activities calculated using depletion and decay codes must be validated against experimental determinations of the spent fuel content. In this process the isotopic concentrations predicted by the codesmore » should be compared with corresponding measurements of spent fuel made by destructive analysis as a fundamental part of any code performance evaluation. In recent years there has been growing international interest in acquiring high-quality assay data that can be used to validate code calculations, particularly for modern fuel designs and high burnup fuels and for a wider range of nuclides important to nuclear criticality safety, radiological safety assessments, and decay heat. Assay data are required to validate a broad range of reactor and fuel-cycle applications, including reactor core simulation, postulated severe accident analysis, spent fuel handling, spent fuel transportation and interim storage, reprocessing, nuclear safeguards, and final fuel repository evaluations. In some cases researchers working on depletion code development have noted a general lack of available assay measurements that can be used to benchmark and validate their code calculations for spent fuel compositions. This perception is due in part to the fact that data have been reported in diverse publications over many years, many experimental reports are difficult to access, and there has not been a concerted and funded effort to compile and consolidate available measurements that can be easily accessed by code developers and analysts for validation. In response to the increased interest in fuel isotopic measurements and needs for consolidation and documentation of available data, an Expert Group on Assay Data for Spent Nuclear Fuel (EGADSNF) was formed in 2007 as a working group of the Organisation for Economic Cooperation and Development (OECD)/Nuclear Energy Agency (NEA) Working Party on Nuclear Criticality Safety (WPNCS). Although the group was formed by the Expert Group on Burnup Credit to coordinate isotopic assay data activities and facilitate collaboration between countries developing or implementing burnup credit in their nuclear criticality safety methodologies, the group recognized the need and value of assay data for a broad range of spent fuel applications, and the EGADSNF includes members representing not only the WPNCS, but also members from the standing technical Committee on the Safety of Nuclear Installations and the Integration Group for the Safety Case of the Radioactive Waste Management Committee. Member countries currently active in the EGADSNF include Belgium, the Czech Republic, France, Germany, Japan, Slovakia, Spain, Sweden, the United Kingdom, and the United States. The experimental database of spent fuel measurements maintained by the OECD/NEA is web-accessible. SFCOMPO (database of Spent Fuel Compositions) contains measured isotopic data, mostly for light water reactor (LWR) fuels, for about 250 fuel samples. This paper summarizes the status of SFCOMPO and current activities to expand and improve the database.« less
  • A comprehensive sensitivity and uncertainty analysis was performed on a 1200-MW(thermal) minor actinide burner designed for a low burnup reactivity swing, negative Doppler constant, and low sodium void worth. Sensitivities of the performance parameters were generated using depletion perturbation methods for the constrained closed fuel cycle of the reactor. The uncertainty analysis was performed using the sensitivity and covariance data taken from ENDF/B-V and other published sources. The uncertainty analysis of a liquid-metal reactor for burning minor actinides has shown that uncertainties in the nuclear data of several key minor actinide isotopes can introduce large uncertainties in the predicted performancemore » of the core. The relative uncertainties in the burnup swing, Doppler constant, and void worth were conservatively estimated to be 220, 120, and 59%, respectively. An analysis was performed to prioritize the minor actinide reactions for reducing the uncertainties.« less
  • Here, fuel assemblies in the spent fuel pool are stored by suspending them in two vertically stacked layers at the Atucha Unit 1 nuclear power plant (Atucha-I). This introduces the unique problem of verifying the presence of fuel in either layer without physically moving the fuel assemblies. Given that the facility uses both natural uranium and slightly enriched uranium at 0.85 wt% 235U and has been in operation since 1974, a wide range of burnups and cooling times can exist in any given pool. A gross defect detection tool, the spent fuel neutron counter (SFNC), has been used at themore » site to verify the presence of fuel up to burnups of 8000 MWd/t. At higher discharge burnups, the existing signal processing software of the tool was found to fail due to nonlinearity of the source term with burnup.« less