Abstract
Studsvik's approach to spent nuclear fuel analyses combines isotopic concentrations and cross-sections, calculated by the lattice physics codes, with core irradiation history data from reactor core simulator and tabulated isotopic decay data. These data sources are used and processed by the code Spent Nuclear Fuel (SNF) to predict spent nuclear fuel characteristics. The procedure for verification and validation of SNF is outlined in this paper which includes verification of the decay data as well as the numerical methods where they are applied into. The paper presents the applicability of SNF to analyses of spent nuclear fuel in comparisons to well established and recognized code in the spent fuel analyses field, ORIGEN, SCALE v6.2.2.
Kurzfassung
Studsviks Ansatz für die Analyse abgebrannter Kernbrennstoffe kombiniert Isotopenkonzentrationen und -querschnitte, die durch die Gitter-Codes berechnet werden, mit Daten zur Geschichte der Kernbestrahlung aus dem Reaktorkernsimulator und tabellarischen Isotopenzerfallsdaten. Diese Datenquellen werden vom Code SNF verwendet und verarbeitet, um die Eigenschaften abgebrannter Kernbrennstoffe vorherzusagen. Das Verfahren zur Verifikation und Validierung des SNF Codes wird in diesem Beitrag skizziert, der sowohl die Verifikation der Zerfallsdaten als auch die numerischen Methoden, in denen sie angewendet werden, umfasst. Dieser Beitrag stellt die Anwendbarkeit des SNF auf Analysen von abgebrannten Kernbrennstoffen im Vergleich zu gut etablierten und anerkannten Codes im Bereich der Analysen von abgebrannten Brennelementen dar wie ORIGEN, SCALE v6.2.2.
References
1 SNF Update v1.07.00 Release notes, SSP-18/409 Rev 0 (March 2018)Search in Google Scholar
2 Simeonov, T.; WempleC.: Development in Studsvik's system for spent fuel analyses. 26th AER symposium, Helsinki, Finland, 10–14 October (2016)Search in Google Scholar
3 Simeonov, T.; WempleC.: Application of STUDSVIK's Spent Nuclear Fuel System for VVER reactors. 27th AER symposium, Munich, Germany, 17–20 October (2017)Search in Google Scholar
4 ReardenB.; Jessee, M.; Eds.: SCALE Code System. ORNL/TM-2005/39, Version 6.2.2, OakRidge National Laboratory, Oak Ridge, Tennessee (2017) 10.2172/1408010Search in Google Scholar
5 WieselquistW.; et al.: ORIGEN: Neutron Activation, Actinide Transmutation, Fission Product Generation, and Radiation Source Terms Calculation. Section 5.1, ORNL/TM-2005/39, SCALE Code System Version 6.2.2, February (2017)Search in Google Scholar
6 Gauld, I. C.; Wiarda, D.; Pigni, M.; Wieselquist, W.: 5.2 ORIGEN data resources, ORNL/TM-2005/39, Version 6.2.2, OakRidge National Laboratory, Oak Ridge, Tennessee (2017)Search in Google Scholar
7 Simeonov, T.; WempleC.: Update and evaluation of decay data for spent nuclear fuel analyses. Nuclear Data 2016, Bruges, Belgium, September (2016). 10.1051/epjconf/201714609011Search in Google Scholar
8 Chadwick, M.; et al.: ENDF/B-VII.1 nuclear data for science and technology: Cross sections, covariances, fission product yields and decay data. Nuclear Data Sheets112 (2011)Search in Google Scholar
9 Tuli, J. K.: Evaluated Nuclear Structure Data File. BNL-NCS-51655-01/02-Rev, BNL (2001)Search in Google Scholar
10 Koning, A. J.; Rochman, D.: Modern nuclear data evaluation with the TALYS code system. Nuclear Data Sheets113 (2012) 284110.1016/j.nds.2012.11.002Search in Google Scholar
11 Berger, M. J.; et al.: ESTAR, PSTAR and ASTAR. NIST (2015). Online at http://physics.nist.gov/StarSearch in Google Scholar
12 Shores, E. F.: Data update for the SOURCES-4A computer code. LA-UR-00–5016 (2000)Search in Google Scholar
13 Watt, B. E.: Energy spectrum of neutrons from thermal fission of U-235. Phys Rev87 (1952) 610.1103/PhysRev.87.1037Search in Google Scholar
14 Kahler, A. C. (ed.): The NJOY nuclear data processing system, Version 2012. LA-UR-12-27079, Los Alamos National Laboratory, December 2012 (updated for NJOY2012.40, October 2014)Search in Google Scholar
15 Dillman, L. T.: EDISTR – A computer program to obtain a nuclear decay data base for radiation dosimetry. ORNL/TM6689 (1980) 10.2172/5726596Search in Google Scholar
16 Perry, R. T.; Wilson, W. B.: Neutron production from (α,n) reactions and spontaneous Fission in ThO2, UO2, and (U,Pu)O2 Fuels. LA-8869-MS, LANL (1981) 10.2172/6188934Search in Google Scholar
17 Peele, R. W.; Maienschein, F. C.: The absolute spectrum of photons emitted in coincidence with thermal-neutron fission of Uranium-235. ORNL-4457(1970) 10.2172/4149909Search in Google Scholar
18 Stamm'ler, R. J. J.; Abbate, M. J.: Methods of steady-state reactor physics in nuclear design. Academic Press (1983) 384Search in Google Scholar
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