Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD

다국어 초록 (Multilingual Abstract)

For an efficient Monte Carlo (MC) burnup analysis, an accurate high-order depletion scheme to considerthe nonlinear flux variation in a coarse burnup-step interval is crucial accompanied with an accuratedepletion equation solver. In a Seoul National University MC code, McCARD, the high-order depletionschemes of the quadratic depletion method (QDM) and the linear extrapolation/quadratic interpolation(LEQI) method and a depletion equation solver by the Chebyshev rational approximation method (CRAM)have been newly implemented in addition to the existing constant extrapolation/backward extrapolation(CEBE) method using the matrix exponential method (MEM) solver with substeps. In this paper, thequadratic extrapolation/quadratic interpolation (QEQI) method is proposed as a new high-order depletionscheme. In order to examine the effectiveness of the newly-implemented depletion modules inMcCARD, four problems in the VERA depletion benchmarks are solved by CEBE/MEM, CEBE/CRAM, LEQI/MEM, QEQI/MEM, and QDM for gadolinium isotopes. From the comparisons, it is shown that the QEQI/MEM predicts kinf's most accurately among the test cases. In addition, statistical uncertainty propagationanalyses for a VERA pin cell problem are conducted by the sensitivity and uncertainty and the stochasticsampling methods.

참고문헌 (Reference)

1 K. Okumura, "Validation of a continuousenergy Monte Carlo burn-up code MVP-BURN and its application to analysis of post irradiation experiment" 37 (37): 128-, 2000

2 D.I. Poston, "Users Manual, Version 1.00 for MONTEBURNS, Version 3.01" Los Alamos National Laboratory 1998

3 H.J. Park, "Uncertainty propagation in Monte Carlo depletion analysis" 167 : 196-, 2011

4 K.S. Kim, "Specifications for the VERA Depletion Benchmark Suite" Oak Ridge National Laboratory 2015

5 J. Leppanen, "Serpentea Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code" VTT Technical Research Centre of Finland 2013

6 D. Lee, "Quadratic depletion method for gadolinium isotopes in CASMO-5" 174 : 79-, 2013

7 A.G. Croff, "ORIGEN2: a versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials" 62 : 335-, 1983

8 H.J. Shim, "Monte Carlo depletion analysis of a PWR with the MCNAP" M&C 99 : 1999

9 D.B. Pelowitz, "MCNP6TM User's Manual Version 1.0, Rev. 0" Los Alamos National Laboratory 2013

10 심형진, "MCCARD: MONTE CARLO CODE FOR ADVANCED REACTOR DESIGN AND ANALYSIS" 한국원자력학회 44 (44): 161-176, 2012

11 "Jordan Research & Training Reactor Final Safety Analysis Report" Jordan Atomic Energy Commission 2014

12 Y. Nagaya, "Impact of perturbed fission source on the effective multiplication factor in Monte Carlo perturbation calculations" 42 (42): 428-, 2005

13 A. Isotalo, "Higher order methods for burnup calculations with bateman solutions" 38 : 1987-, 2011

14 R.J. Stamm’ler, "HELIOS Methods" Studsvik Scandpower 1998

15 H. Rief, "Generalized Monte Carlo perturbation algorithms for correlated sampling and a second-order taylor series approach" 11 : 455-, 1984

16 J.Y. Cho, "Development of Gadolinium Quadratic Depletion Module for DeCART" Korea Atomic Energy Research Institute 2012

17 K.H. Lee, "Depletion and decay analyses of a KJRR fission moly target" 2013

18 M. Pusa, "Computing the matrix exponential in burnup calculations" 164 : 140-, 2010

19 A. Isotalo, "Comparison of neutronics-depletion coupling schemes for burnup calculations" 179 : 434-, 2015

20 R. Reyes-Ramírez, "Comparison of MCNPX-C90 and TRIPOLI-4-d for fuel depletion calculations of a gas-cooled fast reactor" 37 (37): 1101-, 2010