Published November 1994
| Version v1
Miscellaneous
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2-Dimensional fuel burnup calculation of TRR-1/M1
Creators
Description
The program package for 2-dimensional bumpup calculation for TRIGA reactor has been being developed. To verify this package, 2-group macroscopic cross sections at 1 MW for major components of the reactor core were generated. The calculations of excess reactivity and bumpup for core loading no. 1-9 were performed by using this package. Comparing the calculated excess reactivities to the measured values obtained from the log book, the result indicates that the calculations are in good agreement with the measurements
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Additional details
Publishing Information
- ISBN
- 974-7400-06-5
- Imprint Title
- Proceedings of the 5th nuclear science and technology conference
- Imprint Pagination
- 514 p.
- Journal Page Range
- p. B125-B134.
- Report number
- INIS-mf--14876
Conference
- Title
- 5. conference on nuclear science and technology.
- Dates
- 21-23 Nov 1994.
- Place
- Bangkok (Thailand).
INIS
- Country of Publication
- Thailand
- Country of Input or Organization
- Thailand
- INIS RN
- 27071337
- Subject category
- S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTER CALCULATIONS; EXPERIMENTAL DATA; MATHEMATICAL MODELS; NUCLEAR FUELS
- Descriptors DEC
- DATA; ENERGY SOURCES; FUELS; INFORMATION; MATERIALS; NUMERICAL DATA; REACTOR MATERIALS