FRAS3 analysis of transient fission-gas behavior in PNL-10 fuel
Description
The purpose of this work is to demonstrate the capability of the updated FRAS3 code to accurately predict the detailed transient behavior of fission gas in irradiated oxide fuel. The FRAS3 code has been modified in several ways since an earlier evaluation was performed. The most significant modification, in terms of the calculated results, is in the inclusion of the vacancy-depletion effect in the analysis of the growth rate of overpressured intragranular fission-gas bubbles. The code has been applied to analysis of a series of FGR capsule-heating tests of irradiated PNL-10 fuel. This same series of tests was treated in the earlier evaluation exercise, providing a direct comparison between the observations, the original calculated results, and the latest results
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE84005430.Files
15073046.pdf
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Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Imprint Pagination
- 5 p.
- Report number
- CONF-840614--4
Conference
- Title
- Annual meeting of the American Nuclear Society.
- Dates
- 3-8 Jun 1984.
- Place
- New Orleans, LA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 15073046
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CALCULATIONS; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL PINS; GRAIN BOUNDARIES; LMFBR TYPE REACTORS; REACTOR SAFETY; SWELLING; TRANSIENTS
- Descriptors DEC
- BREEDER REACTORS; CRYSTAL STRUCTURE; DEFORMATION; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; ISOTOPES; LIQUID METAL COOLED REACTORS; MATERIALS; MICROSTRUCTURE; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; SAFETY