KOREAN DEVELOPMENT OF ADVANCED THERMAL-HYDRAULIC CODES FOR WATER REACTORS AND HTGRs: SPACE AND GAMMA

作     者：No, Hee Cheon Ha, Sang Jun Kim, Kyung Doo Lim, Hong Sik Lee, Eo Hwak Jin, Hyung Gon 

作者机构：Korea Adv Inst Sci & Technol Dept Nucl & Quantum Engn Taejon 305701 South Korea Khalifa Univ Sci Technol & Res KUSTAR Dept Nucl Engn Abu Dhabi U Arab Emirates KHNP Cent Res Inst Safety Technol Off Taejon 305343 South Korea Korea Atom Energy Res Inst Taejon 305353 South Korea 

出 版 物：《NUCLEAR TECHNOLOGY》 

年 卷 期：2013年第181卷第1期

页      面：24-43页

核心收录：

学科分类：08[工学] 0827[工学-核科学与技术] 

主　　题：SPACE GAMMA safety analysis code 

摘      要：The Korea nuclear industry has been developing the thermal-hydraulic system analysis Safety and Performance Analysis CodE (SPACE) and the GAs Multicomponent Mixture Analysis (GAMMA) code for safety analysis of pressurized water reactors (PWRs) and high-temperature gas-cooled reactors (HTGRs), respectively. SPACE will replace outdated vendor-supplied codes and will be used for the safety analysis of operating PWRs and for the design of an advanced PWR. SPACE consists of up-to-date physical models of two-phase flow dealing with multidimensional two-fluid, three-fieldflow GAMMA consists of multidimensional governing equations consisting of the basic equations for continuity, momentum conservation, energy conservation of the gas mixture, and mass conservation of n species. GAMMA is based on a porous media model so that thermofluid and chemical reaction behaviors in a multicomponent mixture system and heat transfer within solid components, free and forced convection between a solid and a fluid, and radiative heat transfer between solid surfaces can be dealt with. GAMMA has a two-dimensional helium turbine model based on the throughflow calculation and a coupled neutronics thermal-hydraulic model. Extensive code assessment has been performed for the verification and validation of SPACE and GAMMA.