Moderation Factor Of Some Fuel Plate Type Models
Creators
- 1. Multipupose Reactor Centre, National Atomic Energy Agency, Serpong, Indonesia (Indonesia)
Description
Fuel plate type is one of the fuel types which is used in the research reactors and also in the isotop production reactors. The claddings area of this fuel plate type is bigger than another fuel type, so using of this fuel plate type is more interesting because the heat, which is produced by the fission process and also g heating, will be better transferred into the coolant. It means it is possible to get an high order of neutron flux. Based an this reason some factors, i.e. the enrichment Of 235U, Uranium density, mixing material in the meat region and also in the cladding, moderation ratio, must be calculated. The moderation factor has important meanings, i.e. the prismatic block fuel method would be lthe optimal using of the fuel element. The negative reactivity coefficient is required to fulfill the safety aspect. The moderation factor depends on the water volume between the fuel plates. In this paper will be discussed the moderation factor/ratio of the fuel plate type which has 15, 17, 19, 21, 23, 25, 27, 29, and 31 fuel plates with the some dimension except the cooling gap. The MIMS-D4 code was used for the calculation. The calculation showed that the fuel plate types, which is build until 23 fuel plates, area still over moderated condition. The reactivity cefatin of the above plate type is still negative
Files
32025955.pdf
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Additional details
Additional titles
- Original title (Indonesian)
- Faktor Moderasi Pada Berbagai Model Elemen Bakar Plat
Publishing Information
- Publisher
- Nuclear Fuel Elements Development Centre, National Atomic Energy Agency, Serpong, Indonesia
- Imprint Place
- Jakarta (Indonesia)
- Imprint Title
- Proceeding of the Scientific Presentation on Nuclear Fuel Cycle
- Imprint Pagination
- 389 p.
- Journal Page Range
- p. 257-265
- ISSN
- 1410-1998
- Report number
- INIS-ID--009
Conference
- Title
- Scientific Presentation on Nuclear Fuel Cycle
- Original Conference Title
- Presentasi Ilmiah Daur Bahan Bakar Nuklir
- Dates
- 18-19 Mar 1996
- Place
- Jakarta, Indonesia (Indonesia)
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 32025955
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CLADDING; ISOTOPE PRODUCTION REACTORS; NEUTRON FLUX; NUCLEAR FUELS; RESEARCH REACTORS; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; DEPOSITION; ENERGY SOURCES; EVEN-ODD NUCLEI; FUELS; HEAVY NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IRRADIATION REACTORS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MATERIALS; MINUTES LIVING RADIOISOTOPES; NUCLEI; RADIATION FLUX; RADIOISOTOPES; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SPONTANEOUS FISSION RADIOISOTOPES; SURFACE COATING; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- authors; 5 figs.; 3 tabs.; 4 refs. Imprint:Prosiding Presentasi Ilmiah Daur Bahan Bakar Nuklir