Measurement and analysis of isotopic content for sensitive nuclear material
Creators
- 1. KAERI, Daejeon (Korea, Republic of)
Description
The system design of SDTS was performed for sensitive isotopic fissile content assay in spent fuel and recycled fuel Distribution of neutron in fuel was examined. The position of neutron source and fuel assay area was determined and the neutron spectrum by slowing down was analyzed. Detection property was done by neutron measurement sensitivity. Detector position sensitivity was evaluated. Neutron resolution was analyzed. Moreover, neutron spectrum and resolution analysis will play an important role in isotopic fissile assay. Design of target must produce high neutron yield and cooling capability must be considered. Proper coolant is introduced and the effect on neutron production was evaluated. The design results will be used for LSDS system development as a basic information. SDTS system development will play an important role in improvement of safety and economics of future nuclear reactor development and spent fuel management. Moreover, the advanced fissile assay technology will increase international transparence and credibility and the technology development will contribute to related technology export
Availability note (English)
Also available from KAERIFiles
43127698.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 169 p.
- Report number
- KAERI/RR--3340/2011
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 43127698
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- COOLANTS; DESIGN; NEUTRON SOURCES; RESOLUTION; SAFETY; SENSITIVITY; SPENT FUELS
- Descriptors DEC
- ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; PARTICLE SOURCES; RADIATION SOURCES; REACTOR MATERIALS
Optional Information
- Notes
- 14 refs, 110 figs, 53 tabs