Published January 2012 | Version v1
Report Open

Measurement and analysis of isotopic content for sensitive nuclear material

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 KAERI

Files

43127698.pdf

Files (5.2 MB)

Name Size Download all
md5:74c0a27caa3e6ff08ef24c7af91bb90d
5.2 MB Preview Download

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