DEVELOPMENT OF AN AUTOMATIC-GENERATION SYSTEM FOR BWR RE-STARTUP PLANS

被引:0
作者
KINOSHITA, M
FUKUZAKI, T
MARUYAMA, H
SANO, H
FUKASAWA, Y
MATSUKI, T
机构
[1] Power & Ind. Systems R & D Div., Hitachi, Ltd.
[2] Hitachi Works, Hitachi, Ltd.
[3] Omika Works, Hitachi, Ltd.
[4] Hitachi Ibaraki Tech. College, Hitachi, Ltd.
来源
JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN | 1995年 / 37卷 / 09期
关键词
BWR TYPE REACTORS; NUCLEAR POWER PLANTS; PLANNING; REACTOR RE-STARTUP; REACTOR OPERATION; KNOWLEDGE BASE; COMPUTER AIDED SYSTEMS; SIMULATION PROGRAM; NEURAL NETWORK; REACTOR START-UP; CONTROL ROD WITHDRAWAL SEQUENCE; EXPERT SYSTEMS;
D O I
10.3327/jaesj.37.844
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
A system to automatically generate re-startup plans for BWR plants has been developed. By including consideration oi high speed re-startup after reactor shutdown, where xenon concentration is still transient, the system generates the plan whose re-startup time is as short as possible according to the time interval between the reactor shutdown and startup and the current reactor conditions. For this purpose, not only BWR core managing expertise in a knowledge base, but also core simulation programs are used. To realize both higher accuracy and shorter computing time of core characteristics predictions by the simulation programs, the error tendency between the simulation results and actual plant data is learned using an artificial neural network. To make the plan for re-startup operation, first, allowable xenon concentrations and corresponding control. rod patterns that satisfy thermal constraints at the rated power are estimated. Secondly, based on the estimation results, control rod withdrawal sequence, reactor power, control rod pattern and core flow rate for each time are determined. A prototype system was developed to evaluate its performance. The system was capable of generating a plan automatically within 30 min.
引用
收藏
页码:844 / 853
页数:10
相关论文
共 5 条
  • [1] Fukuzaki T., Et al., Operational experience with simulator-type core performance calculation system for boiling water reactors, Specialists' Meeting on Operational Experience with Control and Instrumentation Systems in Nuctear Power Plants, (1987)
  • [2] Iwamoto T., Et al., Proc. Int. Topical Meeting on Advances in Reactor Physics, (1987)
  • [3] Ida T., Et al., ANS 1988 Winter Meeting/ANS, Trans., 57, (1988)
  • [4] Kinoshita M., Et al., ANS 1990 Winter Meeting/ANS Trans., 62, (1990)
  • [5] Kinoshita M., Et al., Nucl. Technol., 96, (1991)