Recent progress of and challenges for U.S. severe accident codes
Creators
- 1. School of Nuclear Engineering, Purdue Univ., West Lafayette, IN (United States)
Description
Severe accident code development has been an ongoing process for over three decades, and a variety of analysis tools are currently available to evaluate light water reactor behavior. These codes have been created by developers from a variety of backgrounds and with different goals. Based on knowledge obtained from experimental programs, considerable progress has been made in severe accident code development. However, many phenomena are not yet sufficiently modeled and the advent of new nuclear reactor designs introduces additional conditions and geometries that are currently not modeled. This paper discusses recent progress in U.S. severe accident code development, challenges that lie ahead and efforts to meet the demands placed on the codes. (author)
Additional details
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- NUTHOS-6: Proceedings of the 6th international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Imprint Pagination
- 3690 p.
- Journal Page Range
- 16 p.
Conference
- Title
- 6. international topical meeting on nuclear reactor thermal hydraulics, operations and safety
- Acronym
- NUTHOS-6
- Dates
- 4-8 Oct 2004
- Place
- Nara (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 36083925
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANALYTICAL SOLUTION; BWR TYPE REACTORS; COMPUTER CODES; HISTORICAL ASPECTS; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR ACCIDENTS; RISK ASSESSMENT; SAFETY ANALYSIS; USA; VALIDATION
- Descriptors DEC
- ACCIDENTS; DEVELOPED COUNTRIES; ENRICHED URANIUM REACTORS; MATHEMATICAL SOLUTIONS; NORTH AMERICA; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name KN, Paper ID KN-05.pdf; 34 refs., 5 figs.