Published May 2017 | Version v1
Miscellaneous

A Reactivity Evaluation of Hypothetical Misloadings for WEC 3-Loop Type Plant

  • 1. KEPCO Nuclear Fuel, Daejeon(Korea, Republic of)

Description

This study is designed to confirm the adverse effects caused by fuel misloading for a domestic WEC 3-loop type plant reflecting the recent operation condition. An evaluation of the core criticality for some severe cases of fuel misloading is involved in this study. With results of the evaluation, it can be estimated roughly how safety limits for refueling which are specified in plant Technical Specifications are effective even in any hypothetical severe misloading cases. This paper contains the quantitative study for loss of shutdown margin and inadvertent criticality caused by such a hypothetical multiple fuel misloading which would arise during refueling operation. The study was attained by core calculations for some misloaded configurations realized to make fresh fuel assemblies placed together in the center of the core. In the conclusion, this study can help understanding the consequences of hypothetical multiple misloading fuel and can be utilized as a reference case study.

Part of:
Proceedings of the KNS 2017 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2017 Spring Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[3 p.]

Conference

Title
2017 Spring Meeting of the KNS
Dates
17-19 May 2017
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
49050106
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; FUEL ASSEMBLIES; FUEL CYCLE; REACTIVITY; REACTOR OPERATION; SAFETY; SPECIFICATIONS; WESTINGHOUSE STANDARD REACTOR
Descriptors DEC
ENRICHED URANIUM REACTORS; OPERATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR LIFE CYCLE; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
1 ref, 2 figs, 1 tab