Published July 1999 | Version v1
Journal article

Overview on VVER fuel in Russian federation

  • 1. Nuclear Development Corp., Tokai, Ibaraki (Japan)

Description

An outline of VVER (Atomic Power Station with Water-cooled and Water-moderated Reactor) which has been developed and commercialized in U.S.S.R since the mid-1950s is briefly presented from a historical and conceptual view point. The major specifications of nuclear fuels used especially in VVER-1000 are compared with those used in PWR, together with some description of the structure of the pressure vessel with its dimensions, cooling system, and the core components including the fuel assembly, fuel cladding materials (Zr-1%Nb) and control rods. Some data on in-core corrosion behavior of the several cladding materials used, on irradiation-induced growth as a function of burn-up, as well as on irradiation-induced creep rate of the cladding tubes are presented. Future prospect on possible modifications is also given. (S. Ohno)

Availability note (English)

Available from DOI: https://doi.org/10.3327/jaesj.41.766

Abstract (Japanese)

ロシアの原子力発電というと、我が国では一般に、チェルノブイリ原子力発電所の黒鉛減速沸騰軽水冷却チャンネル型大型炉(RBMK)が有名で、現在、旧ソ連圏で50基近く運転使用されている加圧型軽水炉VVER(Atomic Power Station with Water-cooled and Water-moderated Reactorのロシア語略称)については余り広く知られていない。一方、我が国や西側世界で主に原子力発電で運転使用されている軽水炉は、加圧水型炉(PWR)と沸騰水型炉(BWR)の2種類があり、いずれも1950年代後半から60年初めに米国で商業運転を開始したものが原点になっている。しかしVVERは旧ソ連が1950年半ばから独自の設計理念で開発し、発展させてきた商業用発電炉で技術的に興味深いものがある。本稿ではまずVVERプラントについて簡単に紹介した後に、主としてVVER-1000の燃料について概要を報告する。(日本)

Additional details

Additional titles

Original title (Japanese)
ロシア型軽水炉VVERの燃料

Identifiers

Publishing Information

Journal Title
Nippon Genshiryoku Gakkai-Shi
Journal Volume
41
Journal Issue
7
Journal Page Range
p. 766-772
ISSN
0004-7120

Optional Information

Notes
This record replaces 30051334