Development of ORIGEN libraries for mixed oxide (MOX) fuel assembly designs

被引:7
作者
Mertyurek, Ugur [1 ]
Gauld, Ian C. [1 ]
机构
[1] Oak Ridge Natl Lab, POB 2008, Oak Ridge, TN 37831 USA
关键词
ANALYSIS CAPABILITIES; NUCLEAR-DATA; VALIDATION; DEPLETION; SCIENCE;
D O I
10.1016/j.nucengdes.2015.11.027
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
ORIGEN cross section libraries for reactor-grade mixed oxide (MOX) fuel assembly designs have been developed to provide fast and accurate depletion calculations to predict nuclide inventories, radiation sources and thermal decay heat information needed in safety evaluations and safeguards verification measurements of spent nuclear fuel. These ORIGEN libraries are generated using two-dimensional lattice physics assembly models that include enrichment zoning and cross section data based on ENDF/B-VII.O evaluations. Using the SCALE depletion sequence, burnup-dependent cross sections are created for selected commercial reactor assembly designs and a representative range of reactor operating conditions, fuel enrichments, and fuel burnup. The burnup dependent cross sections are then interpolated to provide problem-dependent cross sections for ORIGEN, avoiding the need for time-consuming lattice physics calculations. The ORIGEN libraries for MOX assembly designs are validated against destructive radiochemical assay measurements of MOX fuel from the MALIBU international experimental program. This program included measurements of MOX fuel from a 15 x 15 pressurized water reactor assembly and a 9 x 9 boiling water reactor assembly. The ORIGEN MOX libraries are also compared against detailed assembly calculations from the Phase IV-B numerical MOX fuel burnup credit benchmark coordinated by the Nuclear Energy Agency within the Organization for Economic Cooperation and Development. The nuclide compositions calculated by ORIGEN using the MOX libraries are shown to be in good agreement with other physics codes and with experimental data. Published by Elsevier B.V.
引用
收藏
页码:220 / 230
页数:11
相关论文
共 27 条
[1]  
[Anonymous], NUCL SCI
[2]  
[Anonymous], 2011, ORNLTM200539
[3]  
Boulanger D., 2004, DC P 2004 INT M LWR
[4]   SCALE 6: COMPREHENSIVE NUCLEAR SAFETY ANALYSIS CODE SYSTEM [J].
Bowman, S. M. .
NUCLEAR TECHNOLOGY, 2011, 174 (02) :126-148
[5]   ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology [J].
Chadwick, M. B. ;
Oblozinsky, P. ;
Herman, M. ;
Greene, N. M. ;
McKnight, R. D. ;
Smith, D. L. ;
Young, P. G. ;
MacFarlane, R. E. ;
Hale, G. M. ;
Frankle, S. C. ;
Kahler, A. C. ;
Kawano, T. ;
Little, R. C. ;
Madland, D. G. ;
Moller, P. ;
Mosteller, R. D. ;
Page, P. R. ;
Talou, P. ;
Trellue, H. ;
White, M. C. ;
Wilson, W. B. ;
Arcilla, R. ;
Dunford, C. L. ;
Mughabghab, S. F. ;
Pritychenko, B. ;
Rochman, D. ;
Sonzogni, A. A. ;
Lubitz, C. R. ;
Trumbull, T. H. ;
Weinman, J. P. ;
Brown, D. A. ;
Cullen, D. E. ;
Heinrichs, D. P. ;
McNabb, D. P. ;
Derrien, H. ;
Dunn, M. E. ;
Larson, N. M. ;
Leal, L. C. ;
Carlson, A. D. ;
Block, R. C. ;
Briggs, J. B. ;
Cheng, E. T. ;
Huria, H. C. ;
Zerkle, M. L. ;
Kozier, K. S. ;
Courcelle, A. ;
Pronyaev, V. ;
van der Marck, S. C. .
NUCLEAR DATA SHEETS, 2006, 107 (12) :2931-3059
[6]   ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data [J].
Chadwick, M. B. ;
Herman, M. ;
Oblozinsky, P. ;
Dunn, M. E. ;
Danon, Y. ;
Kahler, A. C. ;
Smith, D. L. ;
Pritychenko, B. ;
Arbanas, G. ;
Arcilla, R. ;
Brewer, R. ;
Brown, D. A. ;
Capote, R. ;
Carlson, A. D. ;
Cho, Y. S. ;
Derrien, H. ;
Guber, K. ;
Hale, G. M. ;
Hoblit, S. ;
Holloway, S. ;
Johnson, T. D. ;
Kawano, T. ;
Kiedrowski, B. C. ;
Kim, H. ;
Kunieda, S. ;
Larson, N. M. ;
Leal, L. ;
Lestone, J. P. ;
Little, R. C. ;
McCutchan, E. A. ;
MacFarlane, R. E. ;
MacInnes, M. ;
Mattoon, C. M. ;
McKnight, R. D. ;
Mughabghab, S. F. ;
Nobre, G. P. A. ;
Palmiotti, G. ;
Palumbo, A. ;
Pigni, M. T. ;
Pronyaev, V. G. ;
Sayer, R. O. ;
Sonzogni, A. A. ;
Summers, N. C. ;
Talou, P. ;
Thompson, I. J. ;
Trkov, A. ;
Vogt, R. L. ;
van der Marck, S. C. ;
Wallner, A. ;
White, M. C. .
NUCLEAR DATA SHEETS, 2011, 112 (12) :2887-2996
[7]   REACTOR PHYSICS METHODS AND ANALYSIS CAPABILITIES IN SCALE [J].
DeHart, Mark D. ;
Bowman, Stephen M. .
NUCLEAR TECHNOLOGY, 2011, 174 (02) :196-213
[8]  
Gauld I.C., 2015, ESARDA S 2015 MANCH
[9]  
Gauld I.C., 2003, ORNLTM20032
[10]   ISOTOPIC DEPLETION AND DECAY METHODS AND ANALYSIS CAPABILITIES IN SCALE [J].
Gauld, Ian C. ;
Radulescu, Georgeta ;
Ilas, Germina ;
Murphy, Brian D. ;
Williams, Mark L. ;
Wiarda, Dorothea .
NUCLEAR TECHNOLOGY, 2011, 174 (02) :169-195