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Assessment of DUPIC fuel compatibility with CANDU-6

Abstract

The compatibility of DUPIC fuel with the existing CANDU reactor was assessed. The technical issues of DUPIC fuel compatibility were chosen based on the CANDU physics design requirements and inherent characteristics of DUPIC fuel. The compatibility was assessed for the reference DUPIC fuel composition which was determined to reduce the composition heterogeneity and improve the spent PWR fuel utilization. Preliminary studies on a CANDU core loaded with DUPIC fuel have shown that the nominal power distribution is flatter than that of a natural uranium core when a 2-bundle shift refueling scheme is used, which reduces the reactivity worths of devices in the core and, therefore, the performance of reactivity devices was assessed. The safety of the core was assessed by a LOCA simulation and it was found that the power pulse upon LOCA can be maintained below that in the natural uranium core when a poison material is used in the DUPIC fuel. For the feasibility of handling DUPIC fuel in the plant, it will be necessary to introduce new equipment to load the DUPIC fuel in the refueling magazine. The radiation effect of DUPIC fuel on both the reactor hardware and the environment will require a quantitative analysis later.  More>>
Authors:
Choi, H B; Roh, G H; Jeong, C J; Rhee, B W; Choi, J W [1] 
  1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Publication Date:
Jul 01, 1997
Product Type:
Conference
Report Number:
INIS-KR-006; CONF-9707151-
Reference Number:
SCA: 210400; 210200; 220300; PA: AIX-29:022058; EDB-98:048980; SN: 98001955954
Resource Relation:
Conference: DUPIC fuel workshop `97, Taejon (Korea, Republic of), 2 Jul 1997; Other Information: PBD: Jul 1997; Related Information: Is Part Of Proceedings of DUPIC fuel workshop 97; PB: 159 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 22 NUCLEAR REACTOR TECHNOLOGY; CANDU TYPE REACTORS; FUEL CYCLE; FUEL MANAGEMENT; NUCLEAR FUELS; PWR TYPE REACTORS; RADIATION PROTECTION; REACTIVITY; REACTOR PHYSICS; REACTOR SAFETY; REMOTE HANDLING
OSTI ID:
601087
Research Organizations:
Korea Atomic Energy Research Institute, Taejon (Korea, Republic of).
Country of Origin:
Korea, Republic of
Language:
English
Other Identifying Numbers:
Other: ON: DE98619558; TRN: KR9800072022058
Availability:
INIS; OSTI as DE98619558
Submitting Site:
KRN
Size:
pp. 53-61
Announcement Date:
Jun 08, 1998

Citation Formats

Choi, H B, Roh, G H, Jeong, C J, Rhee, B W, and Choi, J W. Assessment of DUPIC fuel compatibility with CANDU-6. Korea, Republic of: N. p., 1997. Web.
Choi, H B, Roh, G H, Jeong, C J, Rhee, B W, & Choi, J W. Assessment of DUPIC fuel compatibility with CANDU-6. Korea, Republic of.
Choi, H B, Roh, G H, Jeong, C J, Rhee, B W, and Choi, J W. 1997. "Assessment of DUPIC fuel compatibility with CANDU-6." Korea, Republic of.
@misc{etde_601087,
title = {Assessment of DUPIC fuel compatibility with CANDU-6}
author = {Choi, H B, Roh, G H, Jeong, C J, Rhee, B W, and Choi, J W}
abstractNote = {The compatibility of DUPIC fuel with the existing CANDU reactor was assessed. The technical issues of DUPIC fuel compatibility were chosen based on the CANDU physics design requirements and inherent characteristics of DUPIC fuel. The compatibility was assessed for the reference DUPIC fuel composition which was determined to reduce the composition heterogeneity and improve the spent PWR fuel utilization. Preliminary studies on a CANDU core loaded with DUPIC fuel have shown that the nominal power distribution is flatter than that of a natural uranium core when a 2-bundle shift refueling scheme is used, which reduces the reactivity worths of devices in the core and, therefore, the performance of reactivity devices was assessed. The safety of the core was assessed by a LOCA simulation and it was found that the power pulse upon LOCA can be maintained below that in the natural uranium core when a poison material is used in the DUPIC fuel. For the feasibility of handling DUPIC fuel in the plant, it will be necessary to introduce new equipment to load the DUPIC fuel in the refueling magazine. The radiation effect of DUPIC fuel on both the reactor hardware and the environment will require a quantitative analysis later. (author).}
place = {Korea, Republic of}
year = {1997}
month = {Jul}
}