Main Steam Line Break Calculations Using a Coupled RELAP5/PARCS Model for the Ringhals-3 Pressurized Water Reactor
- 著者名:
- 掲載資料名:
- 16th International Conference on Nuclear Engineering - Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition
- シリーズ名:
- ASME Symposia Volumes
- シリーズ巻号:
- ICONE 16(2)
- 発行年:
- 2008
- 巻:
- 2
- ペーパー番号:
- ICONE16-48702
- 開始ページ:
- 507
- 終了ページ:
- 514
- 総ページ数:
- 8
- 出版情報:
- New York: American Society of Mechanical Engineers
- ISBN:
- 9780791848159 [0791848159]
- 言語:
- 英語
- 請求記号:
- A11658/16
- 資料種別:
- 国際会議録
類似資料:
American Society of Mechanical Engineers |
American Society of Mechanical Engineers |
American Society of Mechanical Engineers |
American Society of Mechanical Engineers |
3
国際会議録
Application of RELAP5/MOD3.2 to the OECD/CSNI/NEA Main Steam Line Break Benchmark Related to TMI-1
American Society of Mechanical Engineers |
American Society of Mechanical Engineers |
American Society of Mechanical Engineers |
American Society of Mechanical Engineers |
American Society of Mechanical Engineers |
American Society of Mechanical Engineers |
6
国際会議録
FRED: Calculational Model of Fuel Rod Behavior Under Accident Conditions Coupled With RELAP5/MOD3
American Society of Mechanical Engineers |
American Society of Mechanical Engineers |