Development of core fuel management code system for WWER-type reactors

Development of core fuel management code system for WWER-type reactors 1 3 corresp first-author E-mail: xiabangyang@163.com E-mail: xiabangyang@163.com xiabangyang@163.com 2 3 National Key Laboratory for Reactor System Design Technology, Chengdu 610041, China; National Key Laboratory for Reactor System Design Technology, Chengdu 610041, China; Shanghai Jiaotong University, Shanghai 200030, China; Shanghai Jiaotong University, Shanghai 200030, China; Xi'an Jiaotong University, Xi'an 710049, China Xi'an Jiaotong University, Xi'an 710049, China In this article, a core fuel management program for hexagonal pressurized water type WWER reactors (CFMHEX) has been developed, which is based on advanced three-dimensional nodal method and integrated with thermal hydraulic code to realize the coupling of neutronics and thermal-hydraulics. In CFMHEX, all these feedback effects such as burnup, power distribution, moderator density, and control rod insertion are considered. The verification and validation of the code system have been examined through the IAEA WWER-1000-type Kalinin NPP benchmark problem. The numerical results are in good agreement with measurements and are close to those of other international institutes. Fuel management WWER Nodal method References Xia Bangyang , Xie Zhongsheng . Journal of Xi’an Jiaotong University (in Chinese) , 2005 , 39 ( 7 ): 762 - 765 Journal of Xi’an Jiaotong University (in Chinese) Xia Bangyang , Xie Zhongsheng . Nuclear Power Engineering (in Chinese) , 2005 , 26 ( 5 ): 425 - 430 Nuclear Power Engineering (in Chinese) Smith K.S . Simulate-3 methodology. Studsvik /S02A-92/02-REV , 1992 Simulate-3 methodology. Studsvik /S02A-92/02-REV Zhang Yin , Xie Zhongsheng . Proceeding of the Int Conf PHYSOR , Seoul, South Korea , 2002 IAEA-TECDOC . In-core fuel management code package validation for WWER . Vienna : IAEA , 1995 : 1011 - 4289 In-core fuel management code package validation for WWER 10.1016/S1001-8042(06)60058-4 T329.2 2005-10-27 2006-10-20 2021-01-19 2006 Nuclear Science and Techniques 05 17