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Development of post-irradiation examination and evaluation techniques for nuclear reactor fuel

Technical Report:

Abstract

Fuels discharged from the KORI-1 nuclear power plant have been subjected to hot-cell examination at the post-irradiation examination facility of the Korea Atomic Energy Research Institute. The main objectives were to increase the technical depth of the post-irradiation examination (PIE) and evaluation, and to prepare systemic data base of the irradiation behavior for pressurized water reactor fuels. The examination items include a visual inspection, a dimensional measurement, and a gamma-scanning for the fuel assembly in pool. The hot-cell examination items for the fuel rod are a visual inspection, a profilometry, an axial gamma-scanning, an eddy current testing, a X-ray radiography, a fission gas collection, and its chemical composition analysis, a metallography, a ceramography, a micro gamma-scanning, a densimetry, and a burnup measurement by the chemical analysis method. The in-core fuel behavior parameters, such as a fuel rod/stack length change, a rod internal pressure change, a fission gas release rate, a cladding corrosion, fuel rod creep and growth, and a burnup, have been determined experimentally and compared with the predicted values by means of computer codes. It is appeared that the predicted values are well agreeable with the experimental results, except that for the fuel rod growth. (Author).
Authors:
Ro, Seong Gy; Kim, Eun Ka; Min, Duck Kee [1] 
  1. Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of); and others
Publication Date:
Dec 01, 1990
Product Type:
Technical Report
Report Number:
KAERI/RR-942/90
Reference Number:
SCA: 220300; 210200; 420203; PA: AIX-23:014938; SN: 92000646926
Resource Relation:
Other Information: PBD: Dec 1990
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 42 ENGINEERING; NUCLEAR FUELS; POST-IRRADIATION EXAMINATION; BURNUP; FUEL RODS; HOT CELLS; KORI-1 REACTOR; NONDESTRUCTIVE TESTING; REACTOR CORES; SPENT FUELS; 220300; 210200; 420203; FUEL ELEMENTS; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; HANDLING EQUIPMENT AND PROCEDURES
OSTI ID:
10113683
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE92615093; TRN: KR9100101014938
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
242 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Ro, Seong Gy, Kim, Eun Ka, and Min, Duck Kee. Development of post-irradiation examination and evaluation techniques for nuclear reactor fuel. Korea, Republic of: N. p., 1990. Web.
Ro, Seong Gy, Kim, Eun Ka, & Min, Duck Kee. Development of post-irradiation examination and evaluation techniques for nuclear reactor fuel. Korea, Republic of.
Ro, Seong Gy, Kim, Eun Ka, and Min, Duck Kee. 1990. "Development of post-irradiation examination and evaluation techniques for nuclear reactor fuel." Korea, Republic of.
@misc{etde_10113683,
title = {Development of post-irradiation examination and evaluation techniques for nuclear reactor fuel}
author = {Ro, Seong Gy, Kim, Eun Ka, and Min, Duck Kee}
abstractNote = {Fuels discharged from the KORI-1 nuclear power plant have been subjected to hot-cell examination at the post-irradiation examination facility of the Korea Atomic Energy Research Institute. The main objectives were to increase the technical depth of the post-irradiation examination (PIE) and evaluation, and to prepare systemic data base of the irradiation behavior for pressurized water reactor fuels. The examination items include a visual inspection, a dimensional measurement, and a gamma-scanning for the fuel assembly in pool. The hot-cell examination items for the fuel rod are a visual inspection, a profilometry, an axial gamma-scanning, an eddy current testing, a X-ray radiography, a fission gas collection, and its chemical composition analysis, a metallography, a ceramography, a micro gamma-scanning, a densimetry, and a burnup measurement by the chemical analysis method. The in-core fuel behavior parameters, such as a fuel rod/stack length change, a rod internal pressure change, a fission gas release rate, a cladding corrosion, fuel rod creep and growth, and a burnup, have been determined experimentally and compared with the predicted values by means of computer codes. It is appeared that the predicted values are well agreeable with the experimental results, except that for the fuel rod growth. (Author).}
place = {Korea, Republic of}
year = {1990}
month = {Dec}
}