Published August 2012 | Version v1
Journal article

Self-sufficient nuclear fuel technology development and applications

Creators

  • 1. Dongguk University, College of Energy and Environment, 707 Seokjang-Dong, Gyeongju, Gyeongbuk 780-714 (Korea, Republic of)

Description

Highlights: ► Three kinds of nuclear fuel technology development procedures are provided. ► Detailed activities for nuclear fuel and cladding material developments are described. ► Main fuel failure causes for PWRs in Korea and countermeasures are provided. - Abstract: A cutting-edge nuclear fuel technology in Korea has been acquired through four stepwise nuclear fuel technology development phases starting from the 1970s that may include a fuel import phase, a turnkey fuel technology transfer phase, a fuel technology joint-development phase and a self-sufficient fuel technology development phase. The self-sufficient fuel technology development procedures have been applied for developing four kinds of advanced PWR fuels such as PLUS7, 16ACE7, 17ACE7 and HIPER, an advanced cladding material of HANA and various fuel performance analysis computer codes. The PLUS7, 16ACE7 and 17ACE7 fuels have already been implemented on a batch scale in the PWRs operating in Korea. Based on the forty years' operation experience of the PWRs in Korea and various fuel verification/validation test databases acquired from the advanced fuel developments, main fuel failure causes observed in the PWRs seem to be grid-to-rod fretting wear, debris-induced wear and accelerated Zry-4 cladding corrosion. Outstanding countermeasures against such main fuel failures are proposed to accomplish an ultimate goal of zero fuel defects for the aforementioned advanced fuels.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2012.04.023

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2012.04.023;
PII
S0029-5493(12)00227-0;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
249
Journal Page Range
p. 287-296
ISSN
0029-5493
CODEN
NEDEAU

Conference

Title
8. international topical meeting on nuclear thermal-hydraulics, operation and safety
Acronym
NUTHOS-8
Dates
10-14 Oct 2010
Place
Shanghai (China)

Optional Information

Copyright
Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.