FORMOSA-B: A boiling water reactor in-core fuel management optimization package II

被引:20
|
作者
Karve, AA [1 ]
Turinsky, PJ [1 ]
机构
[1] N Carolina State Univ, Dept Nucl Engn, Elect Power Res Ctr, Raleigh, NC 27695 USA
关键词
D O I
10.13182/NT00-A3104
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
As part of the continuing development of the boiling water reactor in-core fuel management optimization code FORMOSA-B, the fidelity of the core simulator has been improved and a control rod pattern (CRP) sampling capability has been added The robustness of the core simulator is first demonstrated by benchmarking against core load-follow, depletion predictions of both SIMULATE-3 and MICROBURN-B2 codes. The CRP sampling capability based on heuristic rules, is next successfully tested on a fixed fuel loading pattern (LP) to field a feasible CRP that removes the thermal margin and critical flow constraint violations. Its performance in facilitating a spectral shift flow operation is also demonstrated, and then its significant influence on the cost of thermal margin is presented. Finally: rite heuristic CRP sampling capability is coupled with the stochastic LP optimization capability in FORMOSA-B-based on simulated annealing (SA)-to solve the combined CRP-LP optimization problem. Effectiveness of the sampling in improving the efficiency of the SA adaptive algorithm is shown by comparing the results to those obtained with the sampling turned off (i.e., only LP optimization is carried out for the fixed reference CRP). The results preserved clearly indicate the successful implementation of the CRP sampling algorithm and demonstrate FORMOSA-B's enhanced optimization features, which facilitate the code's usage for broader optimization studies.
引用
收藏
页码:48 / 68
页数:21
相关论文
共 50 条
  • [21] In-core fuel management with biased multiobjective function optimization
    Shatilla, YA
    Little, DC
    Penkrot, JA
    Holland, RA
    NUCLEAR TECHNOLOGY, 2000, 130 (03) : 282 - 295
  • [22] In-core power sharing and fuel requirement study for a decommissioning Boiling Water Reactor using the linear reactivity model
    Chen, Chung-Yuan
    Tung, Wu-Hsiung
    Yaur, Shung-Jung
    Kuo, Weng-Sheng
    NUCLEAR ENGINEERING AND DESIGN, 2014, 275 : 264 - 271
  • [23] Preliminary analysis on in-core fuel management optimization of molten salt pebble-bed reactor
    Xia, Bing
    Lv, Ying-Zhong
    Jing, Xing-Qing
    Xu, Xiao-Lin
    Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2013, 47 (SUPPL1): : 150 - 155
  • [24] OPTIMAL IN-CORE FUEL MANAGEMENT FOR PRESSURIZED WATER REACTORS
    CHITKARA, K
    WEISMAN, J
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1972, 15 (02): : 655 - +
  • [25] ALUN - A MODULAR SYSTEM FOR REACTOR AND IN-CORE FUEL-MANAGEMENT CALCULATIONS
    ABUSHADY, Y
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1981, 38 (JUN): : 185 - 187
  • [26] AN ADVANCED MODULAR SCHEME FOR REACTOR AND IN-CORE FUEL-MANAGEMENT CALCULATIONS
    ABUSHADY, Y
    ATOMKERNENERGIE-KERNTECHNIK, 1983, 42 (01): : 50 - 54
  • [27] Management and calculation of in-core fuel for high flux engineering test reactor
    Liao, Chengkui
    Xie, Zhongsheng
    Yin, Banghua
    Sun, Shouhua
    Peng, Feng
    Tang, Xueren
    Hedongli Gongcheng/Nuclear Power Engineering, 2000, 21 (05): : 389 - 392
  • [28] CONSIDERATIONS ON IN-CORE FUEL MANAGEMENT DURING STARTUP OF A FAST BREEDER REACTOR
    BILLAUX, M
    GOLDSCHM.P
    VANDENBE.C
    SPENKE, H
    WEHMANN, U
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1970, 13 (02): : 469 - &
  • [29] In-core fuel management strategy for the basket-fuel-assembly molten salt reactor
    Chun Xue
    Zhi-Yong Zhu
    Hai-Qing Zhang
    Jun Lin
    NuclearScienceandTechniques, 2017, 28 (09) : 86 - 98
  • [30] ADVANCED MODULAR SCHEME FOR REACTOR AND IN-CORE FUEL MANAGEMENT CALCULATIONS.
    Abushady, Yousry
    Atomkernenergie, Kerntechnik, 1983, 42 (01): : 50 - 54