Published 1989
| Version v1
Book
Simulation of the Maanshan Unit 2 full load rejection transient using RELAP5/MOD2 code
Creators
- 1. National Tsing Hua Univ., Hsinchu (Taiwan). Dept. of Nuclear Engineering
- 2. Taiwan Power Co., Taipei
Description
The calculated results and their corresponding test data, especially for the time varying histories of 12 measured parameters are compared in order to assess the global simulation capability of the RELAP5/MOD2 code on net load rejection transients. The results indicate that RELAP5/MOD2 can successfully and accurately predict the time varying histories of the major system parameters during the period of net load rejection event. (orig./DG)
Additional details
Publishing Information
- Publisher
- Braun.
- Imprint Place
- Karlsruhe (Germany, F.R.)
- ISBN
- 3-7650-1116-9
- Imprint Title
- Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 2
- Imprint Pagination
- 696 p.
- Journal Page Range
- p. 1383-1388.
Conference
- Title
- 4. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4).
- Dates
- 10-13 Oct 1989.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 22038390
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AC LOSSES; CHINA; COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; FLOW RATE; HYDRAULICS; OUTAGES; POWER LOSSES; PWR TYPE REACTORS; REACTOR SAFETY; TRANSIENTS
- Descriptors DEC
- ASIA; ENERGY LOSSES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS