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Development of the nuclear fuel materials for research reactor -Development of the advanced nuclear materials-

Technical Report:

Abstract

This project was carried out in order to localize the fuel production and to develop the atomized uranium silicide fuels. In the fabrication part, the fuel meat was successfully cladded with good contact between meat and clad through extrusion die modification and properly controlling of extrusion parameters. The electron beam welding parameters were established properly so that the strength of welding zone showed to be same as the clad strength. The fabricating and assembling technologies of the fuel assembly have been developed and applied to the fabrication of dummy fuels. The development of coating technology on the surface of graphite crucible reduced the carbon contamination in atomized powder. In fuel performance testing part, the thermal reaction swelling tests were carried out. The results showed that the atomized fuel meat swells 30 - 40 % lower than pulverized fuel meat. The corrosion test revealed that the thickness of oxide layer ranges within the criteria of fuel safe requirement. In the fuel design part, the design criteria have been established with evaluating KMRR fuel material characteristics with respect to KMRR operation. In the hydraulic testing part, the modification of test facility and the development of the measuring instrument and data aquisition system  More>>
Publication Date:
Jul 01, 1994
Product Type:
Technical Report
Report Number:
KAERI/RR-1354/93
Reference Number:
SCA: 220600; 220300; PA: AIX-26:011536; EDB-95:028497; SN: 95001324198
Resource Relation:
Other Information: PBD: Jul 1994
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; KMR REACTOR; NUCLEAR FUELS; ATOMIZATION; CLADDING; CORROSION; EXTRUSION; HYDRAULICS; SWELLING; URANIUM SILICIDES; 220600; 220300; RESEARCH, TEST, TRAINING, PRODUCTION, IRRADIATION, MATERIALS TESTING REACTORS; FUEL ELEMENTS
OSTI ID:
10111637
Research Organizations:
Korea Cancer Center Hospital, Seoul (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE95612944; TRN: KR9400187011536
Availability:
OSTI; NTIS; INIS
Submitting Site:
KRN
Size:
332 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Kim, Chang Kyu, Lee, Jong Tak, Park, Hee Dae, Kim, Ki Hwan, Hwang, Wan, Kim, Bong Koo, Ku, Yang Hyeon, Lim, In Cheol, Lee, Jae Kyeong, Kang, Yeong Hwan, Park, Jong Man, Jung, Heung Joon, Lee, Don Bae, Jang, Shee Jeong, Jo, Hae Dong, Ko, Yeong Mo, Lim, Kyeong Soo, Kim, Jeong Do, An, Hyeon Soo, Park, Shee Jin, and Kim, Bok Deuk. Development of the nuclear fuel materials for research reactor -Development of the advanced nuclear materials-. Korea, Republic of: N. p., 1994. Web.
Kim, Chang Kyu, Lee, Jong Tak, Park, Hee Dae, Kim, Ki Hwan, Hwang, Wan, Kim, Bong Koo, Ku, Yang Hyeon, Lim, In Cheol, Lee, Jae Kyeong, Kang, Yeong Hwan, Park, Jong Man, Jung, Heung Joon, Lee, Don Bae, Jang, Shee Jeong, Jo, Hae Dong, Ko, Yeong Mo, Lim, Kyeong Soo, Kim, Jeong Do, An, Hyeon Soo, Park, Shee Jin, & Kim, Bok Deuk. Development of the nuclear fuel materials for research reactor -Development of the advanced nuclear materials-. Korea, Republic of.
Kim, Chang Kyu, Lee, Jong Tak, Park, Hee Dae, Kim, Ki Hwan, Hwang, Wan, Kim, Bong Koo, Ku, Yang Hyeon, Lim, In Cheol, Lee, Jae Kyeong, Kang, Yeong Hwan, Park, Jong Man, Jung, Heung Joon, Lee, Don Bae, Jang, Shee Jeong, Jo, Hae Dong, Ko, Yeong Mo, Lim, Kyeong Soo, Kim, Jeong Do, An, Hyeon Soo, Park, Shee Jin, and Kim, Bok Deuk. 1994. "Development of the nuclear fuel materials for research reactor -Development of the advanced nuclear materials-." Korea, Republic of.
@misc{etde_10111637,
title = {Development of the nuclear fuel materials for research reactor -Development of the advanced nuclear materials-}
author = {Kim, Chang Kyu, Lee, Jong Tak, Park, Hee Dae, Kim, Ki Hwan, Hwang, Wan, Kim, Bong Koo, Ku, Yang Hyeon, Lim, In Cheol, Lee, Jae Kyeong, Kang, Yeong Hwan, Park, Jong Man, Jung, Heung Joon, Lee, Don Bae, Jang, Shee Jeong, Jo, Hae Dong, Ko, Yeong Mo, Lim, Kyeong Soo, Kim, Jeong Do, An, Hyeon Soo, Park, Shee Jin, and Kim, Bok Deuk}
abstractNote = {This project was carried out in order to localize the fuel production and to develop the atomized uranium silicide fuels. In the fabrication part, the fuel meat was successfully cladded with good contact between meat and clad through extrusion die modification and properly controlling of extrusion parameters. The electron beam welding parameters were established properly so that the strength of welding zone showed to be same as the clad strength. The fabricating and assembling technologies of the fuel assembly have been developed and applied to the fabrication of dummy fuels. The development of coating technology on the surface of graphite crucible reduced the carbon contamination in atomized powder. In fuel performance testing part, the thermal reaction swelling tests were carried out. The results showed that the atomized fuel meat swells 30 - 40 % lower than pulverized fuel meat. The corrosion test revealed that the thickness of oxide layer ranges within the criteria of fuel safe requirement. In the fuel design part, the design criteria have been established with evaluating KMRR fuel material characteristics with respect to KMRR operation. In the hydraulic testing part, the modification of test facility and the development of the measuring instrument and data aquisition system were performed. The preliminary testing results with dummy fuels fabricated by our research team showed that the developed system works normally and the results is almost same as AECL results. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Jul}
}