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--