SCDAP/RELAP5 update and applications
Description
The integrated SCDAP/RELAP5 code is being developed by the Office of Nuclear Regulatory Research of the USNRC for the purpose of calculating the core damage and fission product transport within the RCS during LWR severe accidents events. Activities since October 1985 were concentrated in three areas. The first area, code and model development, resulted in the addition of a B4C control rod model and a two-dimensional (axial-radial) heat conduction analysis of fuel and control rods. The second area, developmental assessment, evaluated code models using the results of the OECD LOFT FP-2 test and the PBF and ACRR severe fuel damage tests. The third area, user and NRC technical support, resulted in application of the code to analyses of severe accidents in BWRs and PWRs. 8 refs
Availability note (English)
Available from NTIS, PC A02/MF A01; 1 as DE87012434.
Files
Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- EGG-M--22186
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19044850
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACPR REACTOR; BWR TYPE REACTORS; CORIUM; FISSION PRODUCTS; FUEL RODS; HEAT TRANSFER; HYDRAULICS; LOFT REACTOR; PBF REACTOR; PWR TYPE REACTORS; R CODES; RADIOACTIVE EFFLUENTS; RADIOACTIVITY TRANSPORT; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; S CODES; T CODES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; ISOTOPES; MATERIALS; MIXED SPECTRUM REACTORS; POWER REACTORS; PULSED REACTORS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.
- Secondary number(s)
- CONF-8610135--65.