Published 2011 | Version v1
Miscellaneous

Study on self-initialization algorithm of SCDAP/RELAP5 code

  • 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)

Part of:
Proceedings of ICAPP 2011

Additional details

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/