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Verification tests for CANDU advanced fuel -Development of the advanced CANDU technology-

Technical Report:

Abstract

This project is underway in cooperation with AECL to develop the CANDU advanced fuel bundle (so-called, CANFLEX) which can enhance reactor safety and fuel economy in comparison with the current CANDU fuel and which can be used with natural uranium, slightly enriched uranium and other advanced fuel cycle. As the final schedule, the advanced fuel will be verified by carrying out a large scale demonstration of the bundle irradiation in a commercial CANDU reactor, and consequently will be used in the existing and future CANDU reactors in Korea. The research activities during this year Out-of-pile hydraulic tests for the prototype of CANFLEX bundle was conducted in the CANDU-hot test loop at KAERI. Thermalhydraulic analysis with the assumption of CANFLEX-NU fuel loaded in Wolsong-1 was performed by using thermalhydraulic code, and the thermal margin and T/H compatibility of CANFLEX bundle with existing fuel for CANDU-6 reactor have been evaluated. (Author).
Authors:
Chung, Jang Hwan; Suk, Ho Cheon; Jeong, Moon Ki; Park, Joo Hwan; Jeong, Heung Joon; Jeon, Ji Soo; Kim, Bok Deuk [1] 
  1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Publication Date:
Jul 01, 1994
Product Type:
Technical Report
Report Number:
KAERI/RR-1326/93
Reference Number:
SCA: 210400; 220300; PA: AIX-26:011444; EDB-95:028279; SN: 95001324178
Resource Relation:
Other Information: PBD: Jul 1994
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 22 GENERAL STUDIES OF NUCLEAR REACTORS; CANDU TYPE REACTORS; FUEL ELEMENT CLUSTERS; COOLANT LOOPS; HYDRAULICS; NUCLEAR FUELS; PRESSURE DROP; REACTOR FUELING; THERMODYNAMICS; VERIFICATION; 210400; 220300; POWER REACTORS, NONBREEDING, OTHERWISE MODERATED OR UNMODERATED; FUEL ELEMENTS
OSTI ID:
10111606
Research Organizations:
Korea Cancer Center Hospital, Seoul (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE95612925; TRN: KR9400164011444
Availability:
OSTI; NTIS; INIS
Submitting Site:
KRN
Size:
171 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Chung, Jang Hwan, Suk, Ho Cheon, Jeong, Moon Ki, Park, Joo Hwan, Jeong, Heung Joon, Jeon, Ji Soo, and Kim, Bok Deuk. Verification tests for CANDU advanced fuel -Development of the advanced CANDU technology-. Korea, Republic of: N. p., 1994. Web.
Chung, Jang Hwan, Suk, Ho Cheon, Jeong, Moon Ki, Park, Joo Hwan, Jeong, Heung Joon, Jeon, Ji Soo, & Kim, Bok Deuk. Verification tests for CANDU advanced fuel -Development of the advanced CANDU technology-. Korea, Republic of.
Chung, Jang Hwan, Suk, Ho Cheon, Jeong, Moon Ki, Park, Joo Hwan, Jeong, Heung Joon, Jeon, Ji Soo, and Kim, Bok Deuk. 1994. "Verification tests for CANDU advanced fuel -Development of the advanced CANDU technology-." Korea, Republic of.
@misc{etde_10111606,
title = {Verification tests for CANDU advanced fuel -Development of the advanced CANDU technology-}
author = {Chung, Jang Hwan, Suk, Ho Cheon, Jeong, Moon Ki, Park, Joo Hwan, Jeong, Heung Joon, Jeon, Ji Soo, and Kim, Bok Deuk}
abstractNote = {This project is underway in cooperation with AECL to develop the CANDU advanced fuel bundle (so-called, CANFLEX) which can enhance reactor safety and fuel economy in comparison with the current CANDU fuel and which can be used with natural uranium, slightly enriched uranium and other advanced fuel cycle. As the final schedule, the advanced fuel will be verified by carrying out a large scale demonstration of the bundle irradiation in a commercial CANDU reactor, and consequently will be used in the existing and future CANDU reactors in Korea. The research activities during this year Out-of-pile hydraulic tests for the prototype of CANFLEX bundle was conducted in the CANDU-hot test loop at KAERI. Thermalhydraulic analysis with the assumption of CANFLEX-NU fuel loaded in Wolsong-1 was performed by using thermalhydraulic code, and the thermal margin and T/H compatibility of CANFLEX bundle with existing fuel for CANDU-6 reactor have been evaluated. (Author).}
place = {Korea, Republic of}
year = {1994}
month = {Jul}
}