Published January 2007
| Version v1
Journal article
Developing MNCIT to include all MNSR components
Creators
- 1. Atomic Energy Commission, Damascus (Syrian Arab Republic), Dept. of Nuclear Engineering
Description
This report describe the development of MNCIT program, which treated initially the fuel rods only. MNCIT is developed and extended to treat all reactor components in the context of automating flux and power distributions for any cylindrical shaped reactor once the Input File for MNCIT was compiled correctly. (author)
Additional details
Publishing Information
- Journal Title
- Aalam Al-Zarra
- Journal Issue
- 107
- Journal Page Range
- p. 66
- ISSN
- 1607-985X
INIS
- Country of Publication
- Syrian Arab Republic
- Country of Input or Organization
- Syrian Arab Republic
- INIS RN
- 38019860
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- C CODES; FUEL RODS; M CODES; MNSR TYPE REACTORS; REACTOR COMPONENTS; W CODES
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Abstract of Scientific Research