Published November 1994 | Version v1
Miscellaneous Open

2-Dimensional fuel burnup calculation of TRR-1/M1

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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Part of:
Proceedings of the 5th nuclear science and technology conference

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

Optional Information