Radiological safety experience in the fabrication of alloy plate fuels bearing [sup 233]U/Pu
Journal Article
·
· Nuclear Technology; (United States)
OSTI ID:6159296
- Bhabha Atomic Research Centre, Bombay (India)
The first incidence of [sup 233]U-bearing fuel fabrication in India was the production of aluminum-clad Al-[sup 233]U alloy fuel for the Kamini research reactor. The reactor physics experiments for this fuel are now being carried out in the Purnima III critical assembly, where Al-Pu alloy plate fuels will also be used. Both types of fuels were fabricated in the radiometallurgy laboratories of Bhabha Atomic Research Centre. The hazard potential of each step, evaluated from the site-specific radiological field data, is summarized. The parameters analyzed for this purpose include external and internal radiation hazards, contamination hazards, age of fuel material (i.e., time after separation), and experimental thermoluminescent detector exposure data. Gamma spectrometric data of the finished fuel plates were also analyzed for their utility in checking the material inventory. The collective dose equivalent from the fabrication operations for 12 subassemblies (9 bearing [sup 233]U and 3 bearing plutonium) was 67 mSv, arising from external exposures only. The internal exposure was nil. Fabrication of fuel plates constituted [gt]60% of the total exposure. Fabrication of fuel subassemblies and quality control inspection at all the stages accounted for the remaining radiation exposure. Handling of [sup 233]U/Pu-bearing fuels is likely to increase in the years ahead in India. In this context, analysis of radiological field data has yielded useful guidelines for future work.
- OSTI ID:
- 6159296
- Journal Information:
- Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 103:2; ISSN 0029-5450; ISSN NUTYBB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
050700* -- Nuclear Fuels-- Fuels Production & Properties
054000 -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
560101 -- Biomedical Sciences
Applied Studies-- Radiation Effects-- Dosimetry & Monitoring-- (1992-)
61 RADIATION PROTECTION AND DOSIMETRY
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALLOY NUCLEAR FUELS
ALPHA DECAY RADIOISOTOPES
ASIA
CONTAMINATION
DEVELOPING COUNTRIES
DOSE EQUIVALENTS
DOSES
ELEMENTS
ENERGY SOURCES
EVEN-ODD NUCLEI
FABRICATION
FUEL FABRICATION PLANTS
FUELS
GAMMA SPECTROMETERS
HAZARDS
HEALTH HAZARDS
HEAVY ION DECAY RADIOISOTOPES
HEAVY NUCLEI
INDIA
ISOTOPES
MATERIALS
MEASURING INSTRUMENTS
METALS
NEON 24 DECAY RADIOISOTOPES
NUCLEAR FACILITIES
NUCLEAR FUELS
NUCLEI
PLUTONIUM
RADIATION DOSES
RADIATION HAZARDS
RADIATION PROTECTION
RADIOISOTOPES
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SOLID FUELS
SPECTROMETERS
SPONTANEOUS FISSION RADIOISOTOPES
TRANSURANIUM ELEMENTS
URANIUM 233
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
054000 -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
560101 -- Biomedical Sciences
Applied Studies-- Radiation Effects-- Dosimetry & Monitoring-- (1992-)
61 RADIATION PROTECTION AND DOSIMETRY
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALLOY NUCLEAR FUELS
ALPHA DECAY RADIOISOTOPES
ASIA
CONTAMINATION
DEVELOPING COUNTRIES
DOSE EQUIVALENTS
DOSES
ELEMENTS
ENERGY SOURCES
EVEN-ODD NUCLEI
FABRICATION
FUEL FABRICATION PLANTS
FUELS
GAMMA SPECTROMETERS
HAZARDS
HEALTH HAZARDS
HEAVY ION DECAY RADIOISOTOPES
HEAVY NUCLEI
INDIA
ISOTOPES
MATERIALS
MEASURING INSTRUMENTS
METALS
NEON 24 DECAY RADIOISOTOPES
NUCLEAR FACILITIES
NUCLEAR FUELS
NUCLEI
PLUTONIUM
RADIATION DOSES
RADIATION HAZARDS
RADIATION PROTECTION
RADIOISOTOPES
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SOLID FUELS
SPECTROMETERS
SPONTANEOUS FISSION RADIOISOTOPES
TRANSURANIUM ELEMENTS
URANIUM 233
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES