Published October 2003 | Version v1
Report

Criticality analysis with burnup credit for APR1400 in the Republic of Korea

  • 1. Radiation Safety Analysis Group, Korea Power Engineering Company, Inc., Yusong-gu, Daejeon (Korea, Republic of)

Description

Criticality analysis for the spent fuel pool storage racks of APR1400, Advanced Power Reactor with 1400 MWe capacity for the next generation reactors in Korea, has been performed with the introductions of burnup credit and neutron-absorbing material to maximize spent fuel storage capacity in a given area. The main purpose of this analysis is to determine the minimum burnup necessary for a fuel assembly with a specific initial enrichment and minimum cooling time to be placed in the spent fuel storage rack. In this analysis, the SCALE 4.4 code system has been used. Also, the biases and uncertainties evaluated through validation calculations for both isotopic predictions and criticality calculation have been taken into account in the criticality evaluation. All of the key reactor operating parameters, such as moderator density, soluble boron level, fuel temperature, specific power, and operating history have been selected in a conservative way for the criticality analysis. The analysis results showed that the spent fuel storage rack of APR1400 is designed to achieve the high storage density by using burnup credit concept and poison material. (author)

Part of:
Practices and developments in spent fuel burnup credit applications. Proceedings of a technical committee meeting

Additional details

Publishing Information

ISBN
92-0-111203-3
Imprint Title
Practices and developments in spent fuel burnup credit applications. Proceedings of a technical committee meeting
Imprint Pagination
436 p.
Journal Page Range
p. 344-349
ISSN
1011-4289
Report number
IAEA-TECDOC--1378

Conference

Title
Technical committee meeting on practices and developments in spent fuel burnup credit applications
Dates
22-26 Apr 2002
Place
Madrid (Spain)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35007371
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; CALCULATION METHODS; COOLING TIME; CRITICALITY; FISSION POISONS; FUEL RACKS; FUEL STORAGE POOLS; POWER DENSITY; REACTIVITY WORTHS; S CODES; SAFETY ANALYSIS; TEMPERATURE DEPENDENCE
Descriptors DEC
COMPUTER CODES; MATERIALS; MECHANICAL STRUCTURES; NUCLEAR POISONS; REACTOR MATERIALS; SUPPORTS

Optional Information

Notes
12 refs, 2 figs, 2 tabs