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Modelling of WWER-440 fuel rod behaviour under operational conditions with the PIN-micro code

Abstract

The report summarizes the first practical experience obtained by fuel rod performance modelling at the Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Sciences. The results of application of the PIN-micro code and the code modification PINB1 for thermomechanical analysis of WWER-440 fuel assemblies (FAs) are presented. The aim of this analysis is to study the fuel rod behaviour of the operating WWER reactors. The performance of two FAs with maximal linear power and varying geometrical and technological parameters is analyzed. On the basis of recent publications on WWER fuel performance modelling at extended burnup, a modified PINB1 version of the standard PIN-micro code is shortly described and applied for the selected FAs. Comparison of the calculated results is performed. The PINB1 version predicts higher fuel temperatures and more adequate FGR rate, accounting for the extended burnup. The results presented in this paper prove the existence of sufficient safety margins, for the fuel performance limiting parameters during the whole considered period of core operation. (author). 8 refs, 16 figs, 1 tab.
Authors:
Stefanova, S; Vitkova, M; Simeonova, V; Passage, G; Manolova, M; [1]  Haralampieva, Z; [2]  Scheglov, A; Proselkov, V [3] 
  1. Institute for Nuclear Research and Nuclear Energy, Sofia (Bulgaria)
  2. National Electric Company Ltd., Kozloduy (Bulgaria)
  3. Institute of Nuclear Reactors, RSC Kurchatov Inst., Moscow (Russian Federation)
Publication Date:
Aug 01, 1997
Product Type:
Conference
Report Number:
IAEA-TECDOC-957; CONF-9409411-
Reference Number:
SCA: 210200; PA: AIX-28:068459; EDB-97:129945; SN: 97001863065
Resource Relation:
Conference: IAEA technical committee meeting on water reactor fuel element modelling at high burnup and its experimental support, Windermere (United Kingdom), 19-23 Sep 1994; Other Information: PBD: Aug 1997; Related Information: Is Part Of Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting; PB: 559 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; FUEL RODS; P CODES; SIMULATION; BURNUP; GEOMETRY; MECHANICAL PROPERTIES; OPERATION; SAFETY; THERMODYNAMIC PROPERTIES; VARIATIONS; WWER-3 REACTOR
OSTI ID:
534355
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 1011-4289; Other: ON: DE98602336; TRN: XA9744796068459
Availability:
INIS; OSTI as DE98602336
Submitting Site:
INIS
Size:
pp. 157-169
Announcement Date:
Oct 31, 1997

Citation Formats

Stefanova, S, Vitkova, M, Simeonova, V, Passage, G, Manolova, M, Haralampieva, Z, Scheglov, A, and Proselkov, V. Modelling of WWER-440 fuel rod behaviour under operational conditions with the PIN-micro code. IAEA: N. p., 1997. Web.
Stefanova, S, Vitkova, M, Simeonova, V, Passage, G, Manolova, M, Haralampieva, Z, Scheglov, A, & Proselkov, V. Modelling of WWER-440 fuel rod behaviour under operational conditions with the PIN-micro code. IAEA.
Stefanova, S, Vitkova, M, Simeonova, V, Passage, G, Manolova, M, Haralampieva, Z, Scheglov, A, and Proselkov, V. 1997. "Modelling of WWER-440 fuel rod behaviour under operational conditions with the PIN-micro code." IAEA.
@misc{etde_534355,
title = {Modelling of WWER-440 fuel rod behaviour under operational conditions with the PIN-micro code}
author = {Stefanova, S, Vitkova, M, Simeonova, V, Passage, G, Manolova, M, Haralampieva, Z, Scheglov, A, and Proselkov, V}
abstractNote = {The report summarizes the first practical experience obtained by fuel rod performance modelling at the Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Sciences. The results of application of the PIN-micro code and the code modification PINB1 for thermomechanical analysis of WWER-440 fuel assemblies (FAs) are presented. The aim of this analysis is to study the fuel rod behaviour of the operating WWER reactors. The performance of two FAs with maximal linear power and varying geometrical and technological parameters is analyzed. On the basis of recent publications on WWER fuel performance modelling at extended burnup, a modified PINB1 version of the standard PIN-micro code is shortly described and applied for the selected FAs. Comparison of the calculated results is performed. The PINB1 version predicts higher fuel temperatures and more adequate FGR rate, accounting for the extended burnup. The results presented in this paper prove the existence of sufficient safety margins, for the fuel performance limiting parameters during the whole considered period of core operation. (author). 8 refs, 16 figs, 1 tab.}
place = {IAEA}
year = {1997}
month = {Aug}
}