Published 1999
| Version v1
Book
Verification of IVA5 computer code for melt-water interaction analysis: Part 1
Creators
Description
In order to qualify IVA5 for applications in the field of the melt-water interactions in nuclear reactor safety, the author analyzed the achievable accuracy by predicting phenomena that are within this class. Comparison with a variety of experiments ranging from simple material relocation phenomena to highly violent explosions qualified IVA5 as a code representing the state-of-the-art in the field of the multiphase flows. The code is capable of predicting multiphase flow behavior in complicated geometries and industrial networks. The code is able to predict melt-water interaction in well quantified uncertainty region. Reducing the uncertainty band needs future sophistication in the directions specified in this work
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers
- Imprint Place
- New York, NY (United States)
- Imprint Title
- Proceedings of the 33rd national heat transfer conference NHTC'99
- Imprint Pagination
- [1150 p.]
- Journal Page Range
- p. 8, PaperNHTC, 9936
Conference
- Title
- 33. National Heat Transfer Conference NHTC'99
- Dates
- 15-17 Aug 1999
- Place
- Albuquerque, NM (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 31014061
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FORTRAN; I CODES; MOLTEN METAL-WATER REACTIONS; MULTIPHASE FLOW; REACTOR ACCIDENTS; REACTOR SAFETY; VERIFICATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; FLUID FLOW; PROGRAMMING LANGUAGES; SAFETY
Optional Information
- Secondary number(s)
- CONF-990805--