Summary of ICAP assessment results for RELAP5/MOD2
Description
The International Code Assessment and Applications Program (ICAP) encompasses bilateral agreements between the US Nuclear Regulatory Commission and fourteen nations and/or multinational organizations. One purpose of the ICAP is to provide assessments of the RELAP5 computer code with the intent to identifying code deficiencies and drafting user guidelines. To date, twenty assessment studies have been provided by ICAP assessing the RELAP5/MOD2 code. Of these, ten have been reviewed and evaluated. Based on these ten studies, three code deficiencies were identified and four user guidelines drafted. The code deficiencies are listed and the user guidelines stated. A summary of the information considered and the procedure used in the identification of the code deficiencies and the formulation of user guidelines is given
Additional details
Publishing Information
- Imprint Title
- Sixteenth water reactor safety information meeting. Proceedings: Volume 4, Code uncertainty for ECCS rule; international code assessment program; thermal hydraulics; 2D/3D data applications
- Imprint Pagination
- 606 p.
- Journal Page Range
- p. 161-172.
- Report number
- NUREG/CP--0097-Vol.4
Conference
- Title
- 16. water reactor safety information meeting.
- Dates
- 24-27 Oct 1988.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20084606
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRITICAL FLOW; CRITICAL HEAT FLUX; CRITICAL MASS; DRAG; EVALUATION; INTERNATIONAL ORGANIZATIONS; INTERNATIONAL REGULATIONS; MATHEMATICAL MODELS; PWR TYPE REACTORS; QUALITY CONTROL; R CODES; REACTOR ACCIDENTS; REACTOR SAFETY; T CODES; US NRC
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTROL; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT FLUX; LAW; NATIONAL ORGANIZATIONS; POWER REACTORS; REACTORS; REGULATIONS; SAFETY; SIMULATION; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8810155--Vol.4.