Published 1979
| Version v1
Book
Comparison of fission-gas effects in a transient overpower test (HUT 5-7A) to FRAS3 code predictions
Description
Fission gas has an important bearing on fuel dynamics during reactor transients. In this paper, fission-gas bubble sizes and densities, both within grains and on grain boundaries, are characterized as functions of radial location across the axial midplane of the HUT 5-7A (PNL 9-25) TOP (50 /cent/sub s/) TREAT tested fuel pin. The FRAS3 code, being developed to model fission-gas effects in reactor transients, is applied to analyze the results of this experiment. Comparisons between measured data and calculated results for the HUT 5-7A test are presented to illustrate the observed phenomena and to demonstrate the validity of the modeling approach. 13 refs
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL
- Imprint Title
- International meeting on fast reactor safety technology
- Journal Page Range
- p. 2050-2059.
Conference
- Title
- International meeting on fast reactor safety technology.
- Dates
- 19 - 23 Aug 1979.
- Place
- Seattle, WA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12618872
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; F CODES; FISSION PRODUCTS; LMFBR TYPE REACTORS; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; ISOTOPES; LIQUID METAL COOLED REACTORS; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTORS