DocumentCode
451492
Title
Development and test of spent fuel verification system using a scintillating glass fiber
Author
Park, Il-Jin ; Ahn, Gil Hoon ; Kim, Jong-Soo ; Kim, Jeong-Soo ; Ko, Kwang-Ok ; Min, Gyungsik
Author_Institution
Nat. Nucl. Manage. & Control Agency, Daejeon, South Korea
Volume
1
fYear
2005
fDate
23-29 Oct. 2005
Firstpage
515
Lastpage
518
Abstract
Spent fuel verification by non-destructive assay has been implemented for safeguards purpose using various radiation detectors such as a gas type detector, a semiconductor detector and so on. However, due to the severe circumstance of spent fuel storage such as high temperature, high radiation intensity and difficult to access area, the applicable radiation detectors and measurement techniques are restricted. A scintillating glass fiber has been known to have a good radiation hardness and physical properties for high temperature and humidity. In order to verify spent fuels stored in difficult to access area, we designed a spent fuel verification equipment using a scintillating glass fiber. Gamma and neutron sensitivity were tested to optimize the measurement system. The field test was performed at Wolsung NPP (nuclear power plant) pond storage area. The measurement result was compared to the simulation result using MCNP and ORIGEN-ARP codes. From the comparison result, it was known that a SGF verification system can be used as a spent fuel bundle identifier as well as in item counting.
Keywords
gamma-ray apparatus; gamma-ray detection; neutron detection; nuclear materials safeguards; radioactive waste storage; solid scintillation detectors; MCNP code; ORIGEN-ARP code; Wolsung nuclear power plant pond storage area; gamma sensitivity; neutron sensitivity; nuclear safeguards; radiation hardness; scintillating glass fiber; spent fuel bundle identifier; spent fuel storage; spent fuel verification system; Fuel storage; Glass; Humidity; Measurement techniques; Optical fiber devices; Optical fiber testing; Radiation detectors; Semiconductor radiation detectors; System testing; Temperature sensors;
fLanguage
English
Publisher
ieee
Conference_Titel
Nuclear Science Symposium Conference Record, 2005 IEEE
ISSN
1095-7863
Print_ISBN
0-7803-9221-3
Type
conf
DOI
10.1109/NSSMIC.2005.1596305
Filename
1596305
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