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Experimental support of WWER-440 fuel reliability and serviceability at high burnup

Abstract

Results from post-reactor examination of two WWER-440 fuel assemblies spent at the Kola NPP Unit 3 during 4 and 5 fuel cycles are presented. The fuel assembly states and their serviceability allowance are estimated experimentally at the RIAR hot laboratory and studied by non-destructive and destructive methods. The following parameters are examined: fuel assembly overall dimensions change; fuel element diameter change; fuel element cladding corrosion and hydriding; fuel element cladding mechanical properties; fission gas release from fuel and gas pressure; fuel macro- and microstructure. it has been found that the maximum fuel burnup of fuel assemblies No. 1 and No.2 achieved is 58.3 and 64.0 MWd/kg, respectively. The mechanical fuel pellets-cladding interaction has been observed at the average fuel burnup above 45 MWd/kg that occurred with increasing the local cladding diameter at the areas of pellets end arrangement (bamboo stick). The gas release linearly increases at the range 2.7% per 10 MWd/kg within burnup of 43-60 MWd/kg. 9 figs., 3 refs.
Authors:
Smirnov, A; Ivanov, V; Pnyushkin, A; [1]  Tzibulya, V; [2]  Kolosovsky, V; Bibilashvili, Yu; [3]  Dubrovin, K [4] 
  1. Nauchno-Issledovatel`skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation)
  2. AO Mashinostroitelnij Zavod Electrostal (Russian Federation)
  3. Vsesoyuznyj Nauchno-Issledovatel`skij Inst. Neorganicheskikh Materialov, Moscow (Russian Federation)
  4. Russian Research Centre Kurchatov Inst., Moscow (Russian Federation)
Publication Date:
Dec 31, 1994
Product Type:
Miscellaneous
Report Number:
INIS-BG-0012; CONF-9409463-
Reference Number:
SCA: 210200; PA: AIX-28:031113; EDB-97:054333; SN: 97001765476
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 ASSEMBLIES; BURNUP; KOLA-3 REACTOR; CORROSION RESISTANCE; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; FUEL RODS; FUEL-CLADDING INTERACTIONS; HYDRIDATION; LENGTH; MICROSTRUCTURE; REACTOR OPERATION; RELIABILITY
OSTI ID:
456088
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: BG9600370031113
Availability:
INIS; OSTI as DE97620150
Submitting Site:
INIS
Size:
pp. 141-146
Announcement Date:
Apr 21, 1997

Citation Formats

Smirnov, A, Ivanov, V, Pnyushkin, A, Tzibulya, V, Kolosovsky, V, Bibilashvili, Yu, and Dubrovin, K. Experimental support of WWER-440 fuel reliability and serviceability at high burnup. Bulgaria: N. p., 1994. Web.
Smirnov, A, Ivanov, V, Pnyushkin, A, Tzibulya, V, Kolosovsky, V, Bibilashvili, Yu, & Dubrovin, K. Experimental support of WWER-440 fuel reliability and serviceability at high burnup. Bulgaria.
Smirnov, A, Ivanov, V, Pnyushkin, A, Tzibulya, V, Kolosovsky, V, Bibilashvili, Yu, and Dubrovin, K. 1994. "Experimental support of WWER-440 fuel reliability and serviceability at high burnup." Bulgaria.
@misc{etde_456088,
title = {Experimental support of WWER-440 fuel reliability and serviceability at high burnup}
author = {Smirnov, A, Ivanov, V, Pnyushkin, A, Tzibulya, V, Kolosovsky, V, Bibilashvili, Yu, and Dubrovin, K}
abstractNote = {Results from post-reactor examination of two WWER-440 fuel assemblies spent at the Kola NPP Unit 3 during 4 and 5 fuel cycles are presented. The fuel assembly states and their serviceability allowance are estimated experimentally at the RIAR hot laboratory and studied by non-destructive and destructive methods. The following parameters are examined: fuel assembly overall dimensions change; fuel element diameter change; fuel element cladding corrosion and hydriding; fuel element cladding mechanical properties; fission gas release from fuel and gas pressure; fuel macro- and microstructure. it has been found that the maximum fuel burnup of fuel assemblies No. 1 and No.2 achieved is 58.3 and 64.0 MWd/kg, respectively. The mechanical fuel pellets-cladding interaction has been observed at the average fuel burnup above 45 MWd/kg that occurred with increasing the local cladding diameter at the areas of pellets end arrangement (bamboo stick). The gas release linearly increases at the range 2.7% per 10 MWd/kg within burnup of 43-60 MWd/kg. 9 figs., 3 refs.}
place = {Bulgaria}
year = {1994}
month = {Dec}
}