Absolute burn-up determination of U3Si2-Al irradiated fuel plate with loading 2.96 gU/cm3
Creators
- 1. Pusat Teknologi Bahan Bakar Nuklir - BATAN, Kawasan Puspiptek Serpong, Tangerang Selatan 15314 (Indonesia)
Description
Absolute burn up measurement of U3Si2-Al irradiated fuel element with loading of 2.96 gU/cm3 with RI-SIE 2 code has been done. The burn up calculation of U3Si2-Al irradiated fuel element is based on the content of 137Cs, 235U and 239Pu isotopes which is obtained by radiochemical analysis after an appropriate separation. The purpose of the separation a monitoring of the fission product (137Cs isotope) and the heavy elements (uranium and plutonium) is to get the amount of 235U isotope accurately. Separation and analysis of 137Cs isotope had been done by cation exchange using zeolite Lampung and spectrometer-γ. While the separation both of isotop 235U and 239Pu had been done by anion exchange column using Dowex 1 x 8 resin. The effluent of U in the column anion exchanger was eluted by using HNO3 8N and the effluent of Pu was eluted by HCl 0.1N + HF 0.036N. Both of isotopes were analyzed by using a spectrometer-α. The analysis result showed that the content of 137Cs isotope in U3Si2-Al irradiated fuel element was 0.000716 g/g sample, while the content of 235U, 239Pu and 238Pu were 0.032824 g/g sample, 0.000011 g/g sample and 0.000005 g/g sample respectively. The result of measurement 235U isotope compared with initially content of isotop 235U (fabrication data) for being used in the absolute burn up measurement. The result of absolute burn up calculation of U3Si2-Al irradiated fuel U3Si2-Al with loading of 2.96 gU/cm3 with RI-SIE 2 code was 51.69 %. (author)
Additional details
Additional titles
- Original title (Indonesian)
- Penentuan burn up mutlak pelat elmen bakar U3Si2-Al tingkat muat uranium 2,96 gU/cm3 pasca iradiasi
Publishing Information
- Journal Title
- Jurnal Teknologi Bahan Nuklir
- Journal Volume
- 11
- Journal Issue
- 2
- Journal Page Range
- p. 83-98
- ISSN
- 1907-2635
INIS
- Country of Publication
- Indonesia
- Country of Input or Organization
- Indonesia
- INIS RN
- 51102253
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ANIONS; BURNUP; CATIONS; CESIUM 137; FISSION PRODUCTS; FUEL ELEMENTS; HOT CELLS; PLUTONIUM 239; RADIOCHEMICAL ANALYSIS; SPENT FUEL ELEMENTS; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CESIUM ISOTOPES; CHARGED PARTICLES; CHEMICAL ANALYSIS; EQUIPMENT; EVEN-ODD NUCLEI; FUEL ELEMENTS; HEAVY NUCLEI; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTOPES; IONS; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; LABORATORY EQUIPMENT; MATERIALS; MINUTES LIVING RADIOISOTOPES; NUCLEI; ODD-EVEN NUCLEI; PLUTONIUM ISOTOPES; QUANTITATIVE CHEMICAL ANALYSIS; RADIOACTIVE MATERIALS; RADIOISOTOPES; REACTOR COMPONENTS; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 17 refs.; 8 tabs.; 3 figs.