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State-of-the-art and perspectives of the fuel rod and material development activities in Russia

Abstract

A review of experimental, design and pilot work made in Russia to improve nuclear fuel operational reliability and technical-economical parameters of fuel cycles is presented. A reliable operation of WWER-1000 in a three year mode and WWER-440 in a four year mode is promoted at the mean discharge fuel burnup of about 42-43 Mwd/kg U. The operational experience shows that in 1991-93 in Russia and Ukraine the frequency of fuel rod leakage did not exceed on the average 2.10{sup -5}. The comparison made between the individual characteristics of Russian WWER fuel performance and those of standard PWR fuel shows the superiority of the Russian fuel in the whole series of features important for further increase in lifetime. The new programme is aimed at higher fuel utilization and at further improvement of technical and economical parameters of fuel cycles through extension of lifetime of structural materials and fuel rods to promote the mean fuel burnup up to 55-60 Mwd/kg U and higher. The behaviour of prototype fuels in research reactors up to burnup significantly higher (a factor of 1.5-2.0) than the design burnup of commercial reactor fuel has been studied. The investigations show that the design and technological solutions on fuels  More>>
Authors:
Bibilashvili, Yu K [1] 
  1. Vsesoyuznyj Nauchno-Issledovatel`skij Inst. Neorganicheskikh Materialov, Moscow (Russian Federation)
Publication Date:
Dec 31, 1994
Product Type:
Miscellaneous
Report Number:
INIS-BG-0012; CONF-9409463-
Reference Number:
SCA: 210200; PA: AIX-28:031103; EDB-97:054308; SN: 97001765466
Resource Relation:
Conference: International seminar on WWER reactor fuel performance, modelling and experimental support, Varna (Bulgaria), 7-11 Sep 1994; Other Information: PBD: 1994; Related Information: Is Part Of WWER reactor fuel performance, modelling and experimental support. Proceedings; Stefanova, S.; Chantoin, P.; Kolev, I. [eds.]; PB: 272 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; FUEL RODS; ZIRCONIUM BASE ALLOYS; RUSSIAN FEDERATION; BURNUP; CORROSION RESISTANT ALLOYS; CRACK PROPAGATION; EXPERIMENTAL DATA; FUEL-CLADDING INTERACTIONS; INTERSTITIAL HYDROGEN GENERATION; STRESS INTENSITY FACTORS; WWER-3 REACTOR; WWER-5 REACTOR
OSTI ID:
456078
Research Organizations:
Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika
Country of Origin:
Bulgaria
Language:
English
Other Identifying Numbers:
Other: ON: DE97620150; TRN: BG9600356031103
Availability:
INIS; OSTI as DE97620150
Submitting Site:
INIS
Size:
pp. 39-48
Announcement Date:
Apr 21, 1997

Citation Formats

Bibilashvili, Yu K. State-of-the-art and perspectives of the fuel rod and material development activities in Russia. Bulgaria: N. p., 1994. Web.
Bibilashvili, Yu K. State-of-the-art and perspectives of the fuel rod and material development activities in Russia. Bulgaria.
Bibilashvili, Yu K. 1994. "State-of-the-art and perspectives of the fuel rod and material development activities in Russia." Bulgaria.
@misc{etde_456078,
title = {State-of-the-art and perspectives of the fuel rod and material development activities in Russia}
author = {Bibilashvili, Yu K}
abstractNote = {A review of experimental, design and pilot work made in Russia to improve nuclear fuel operational reliability and technical-economical parameters of fuel cycles is presented. A reliable operation of WWER-1000 in a three year mode and WWER-440 in a four year mode is promoted at the mean discharge fuel burnup of about 42-43 Mwd/kg U. The operational experience shows that in 1991-93 in Russia and Ukraine the frequency of fuel rod leakage did not exceed on the average 2.10{sup -5}. The comparison made between the individual characteristics of Russian WWER fuel performance and those of standard PWR fuel shows the superiority of the Russian fuel in the whole series of features important for further increase in lifetime. The new programme is aimed at higher fuel utilization and at further improvement of technical and economical parameters of fuel cycles through extension of lifetime of structural materials and fuel rods to promote the mean fuel burnup up to 55-60 Mwd/kg U and higher. The behaviour of prototype fuels in research reactors up to burnup significantly higher (a factor of 1.5-2.0) than the design burnup of commercial reactor fuel has been studied. The investigations show that the design and technological solutions on fuels developed for commercial reactors are optimal. A new structural material is reported that compared to Zr-1%Nb alloy should have a higher irradiation resistance to higher cladding wall temperature and low coolant boiling as well as a low corrosion sensitivity to water chemistry variations, including free oxygen in the coolant. This alloy, Zr-1.2%Sn-1%Nb(0.3-0.4)%Fe, is already commercially available in Russia. 6 tabs., 14 figs., 5 refs.}
place = {Bulgaria}
year = {1994}
month = {Dec}
}