Published October 2002
| Version v1
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Neutronic design of the RSG-GAS compact core without CIP
Creators
- 1. Center for Development of Research Reactor Technology, National Atomic Energy Agency, Serpong (Indonesia)
Description
Improvement of the efficiency of reactor operation can be chivvied by some ways, such as, the uranium density of the fuel, loading pattern and configuration of core elements. The paper deals with determination of optimal configuration of the compact core with out CIP. Calculations were carried out by means of SRAC-PIJ module for cross section generation and SRAC-ASMBURN for core calculations. The optimal compact core obtained, showed that no-CIP compact core increase highest reactivity value about 0,84 % Δk/k and longest time operation about 1,19 time in the safety criteria that is power peaking factor less then 1,4 and margin control element worth less then volume in the first design that -2,2% Δk/k
Files
37092522.pdf
Files
(2.3 MB)
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Additional details
Additional titles
- Original title (Indonesian)
- Desain neutronik teras kompak RSG-GAS tanpa CIP
Publishing Information
- Publisher
- Centre for Development of Advanced Reactor System, National Atomic Energy Agency and Univetsity of Trisakti
- Imprint Place
- Serpong (Indonesia)
- Imprint Title
- Proceedings of the 8. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities
- Imprint Pagination
- 415 p.
- Journal Page Range
- p. 173-184
- ISSN
- 0854-2910
- Report number
- INIS-ID--032
Conference
- Title
- 8. National Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities
- Original Conference Title
- Seminar Nasional ke-8 Teknologi dan Keselamatan PLTN Serta Fasilitas Nuklir
- Dates
- 15 Oct 2002
- Place
- Jakarta (Indonesia)
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 37092522
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALCULATION METHODS; COMPACTS; COMPUTER CODES; CONTROL ELEMENTS; CROSS SECTIONS; FUEL ELEMENTS; NEUTRON TRANSPORT; NUCLEAR CORES; REACTOR OPERATION; URANIUM 235; URANIUM SILICIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; EVEN-ODD NUCLEI; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MINUTES LIVING RADIOISOTOPES; NEUTRAL-PARTICLE TRANSPORT; NUCLEI; OPERATION; RADIATION TRANSPORT; RADIOISOTOPES; REACTOR COMPONENTS; SILICIDES; SILICON COMPOUNDS; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM COMPOUNDS; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 5 refs; 1 tabs; 3 figs Imprint:Prosiding Seminar Nasional ke-8 Teknologi dan Keselamatan PLTN Serta Fasilitas Nuklir