The impact of fuel depletion scheme within SCALE code on the criticality of spent fuel pool with RBMK fuel assemblies

被引:0
作者
Slavickas, Andrius [1 ]
Kaliatka, Tadas [1 ]
Pabarcius, Raimondas [1 ]
Rimkevicius, Sigitas [1 ]
机构
[1] Lithuanian Energy Inst, Lab Nucl Installat Safety, Breslaujos Str 3, LT-44403 Kaunas, Lithuania
关键词
Depletion scheme; Dancoff factor; Spent fuel pool; RBMK; SCALE; VALIDATION; CAPABILITIES;
D O I
10.1016/j.net.2022.08.001
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
RBMK fuel assemblies differ from other LWR FA due to a specific arrangement of the fuel rods, the low enrichment, and the used burnable absorber -erbium. Therefore, there is a challenge to adapt modeling tools, developed for other LWR types, to solve RBMK problems. A set of 10 different depletion simulation schemes were tested to estimate the impact on reactivity and spent fuel composition of possible SCALE code options for the neutron transport modelling and the use of different nuclear data libraries. The simulations were performed using cross-section libraries based on both, VII.0 and VII.1, versions of ENDF/ B nuclear data, and assuming continuous energy and multigroup simulation modes, standard and user -defined Dancoff factor values, and employing deterministic and Monte Carlo methods. The criticality analysis with burn-up credit was performed for the SFP loaded with RBMK-1500 FA. Spent fuel com-positions were taken from each of 10 performed depletion simulations. The criticality of SFP is found to be overestimated by up to 0.08% in simulation cases using user-defined Dancoff factors comparing the results obtained using the continuous energy library (VII.1 version of ENDF/B nuclear data). It was shown that such discrepancy is determined by the higher U-235 and Pu-239 isotopes concentrations calculated.(c) 2022 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
引用
收藏
页码:4731 / 4742
页数:12
相关论文
共 22 条
  • [1] Agrenius L., 2010, 1193244 SKB
  • [2] Almenas K., 1998, IGNALINA RBMK 1500 S
  • [3] [Anonymous], 1999, TR016780V1R2 EPRI
  • [4] [Anonymous], 2011, SPENT NUCL FUEL ASS, V5
  • [5] [Anonymous], 2010, ACC AN SAF AN REP DE
  • [6] [Anonymous], 2011, ORNLTM200539
  • [7] [Anonymous], 2007, REG GUID 1 13 SPENT
  • [8] Cardoni J., 2016, SAND2016-9065R
  • [9] Validation of nuclide depletion capabilities in Monte Carlo code MCS
    Ebiwonjumi, Bamidele
    Lee, Hyunsuk
    Kim, Wonkyeong
    Lee, Deokjung
    [J]. NUCLEAR ENGINEERING AND TECHNOLOGY, 2020, 52 (09) : 1907 - 1916
  • [10] Validation of BWR spent nuclear fuel isotopic predictions with applications to burnup credit
    Gauld, I. C.
    Mertyurek, U.
    [J]. NUCLEAR ENGINEERING AND DESIGN, 2019, 345 : 110 - 124