지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2011.1
- 수록면
- 45 - 62 (18page)
이용수
초록· 키워드
오류제보하기
The Korean nuclear industry is developing a thermal-hydraulic analysis code for safety analysis of pressurized waterreactors (PWRs). The new code is called the Safety and Performance Analysis Codefor Nuclear Power Plants (SPACE). TheSPACE code adopts advanced physical modeling of two-phase flows, mainly two-fluid three-field models which comprisegas, continuous liquid, and droplet fields and has the capability to simulate 3D effects by the use of structured and/or non-structured meshes. The programming language for the SPACE code is C++ for object-oriented code architecture. The SPACEcode will replace outdated vendor supplied codes and will be used for the safety analysis of operating PWRs and the design ofadvanced reactors. This paper describes the overall features of the SPACE code and shows the code assessment results forseveral conceptual and separate effect test problems.
목차
등록된 정보가 없습니다.
참고문헌 (29)
참고문헌 신청
/ 1981 / BWR (boiling Water Reactor) Refill-Reflood program Task 4.8 - Model Qualification Task plan
/ 1986 / Analysis of FLECHT SEASET 163-Rod Blocked Bundle Data Using COBRA-TF
/ 2000 / TRAC-M/FORTRAN90 (VERSION 3.0) Theory Manual
/ 2001 / RELAP5/MOD3.3 Code Manual, Volume I: Code Structure, System Models and Solution Methods
/ 2006 / MARS code manual, volume 1: code structure, system models, and solution methods
/ 1986 / Analysis of FLECHT SEASET 163-Rod Blocked Bundle Data Using COBRA-TF
/ 2000 / TRAC-M/FORTRAN90 (VERSION 3.0) Theory Manual
/ 2001 / RELAP5/MOD3.3 Code Manual, Volume I: Code Structure, System Models and Solution Methods
/ 2006 / MARS code manual, volume 1: code structure, system models, and solution methods
이 논문의 저자 정보
최근 본 자료
댓글(0)
0