Study on self-initialization algorithm of SCDAP/RELAP5 code
Creators
- 1. Institute of Nuclear Energy Research - INER, 1000, Wunhua Rd., Jiaan Village,Longtan Towship, Taoyuan County 32546,Taiwan (China)
Description
Full text of publication follows. The SCDAP/RELAP5 (SR5) code, which is composed of the RELAP5 code and the SCDAP model, is a severe accident analysis code for nuclear power plants. In order to simulate a consistent accident scenario with SR5, a correct initial steady-state condition must be generated. RELAP5 provides useful controller components for the self-initialization purpose. However, many users still use the trial-and-error approach to generate the initial conditions. This paper demonstrates the application of the self-initialization algorithm of the RELAP5 and SR5 codes. Kuosheng nuclear power plant (NPP), a GE BWR-6 with MARK III containment, and Maanshan NPP, a Westinghouse pressurized water reactor plant, are cited as a reference plants. First, the standard controller components provided in the RELAP5 model are described. Then, a set of controllers that mimic an actual plant control system is applied to establish the steady-state conditions for Kuosheng and Maanshan NPPs with the SR5 code. The problems associated with the self-initialization are discussed and solved. The initialization work of partial-power conditions of the Maanshan NPP is also demonstrated. These initial conditions are successfully generated with the RELAP5 controller components. By using this feature, it not only improves the accuracy of the simulation, but also eliminates the tedious trial-and-error initialization process. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- Proceedings of ICAPP 2011
- Imprint Pagination
- 2851 p.
- Journal Page Range
- p. 1457
- Report number
- INIS-FR--13-0283
Conference
- Title
- The Power of Innovation
- Acronym
- ICAPP 2011 - Performance and Flexibility
- Dates
- 2-5 May 2011
- Place
- Nice (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 44092950
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; OPTIMIZATION; PWR TYPE REACTORS; R CODES; REACTOR ACCIDENT SIMULATION; S CODES; STEADY-STATE CONDITIONS; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available in abstract form only, full text entered in this record; Available from the INIS Liaison Officer for France, see the 'INIS contacts' section of the INIS website for current contact and E-mail addresses: http://www.iaea.org/INIS/contacts/