Published August 1997 | Version v1
Report Open

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

  • 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)

Description

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

Files

28068459.pdf

Files (262.4 kB)

Name Size Download all
md5:8071bc4030b2cf0b18dbd8c9e0bc0c0a
262.4 kB Preview Download
Part of:
Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting
Imprint Pagination
559 p.
Journal Page Range
p. 157-169.
ISSN
1011-4289
Report number
IAEA-TECDOC--957

Conference

Title
Technical committee meeting on water reactor fuel element modelling at high burnup and its experimental support.
Dates
19-23 Sep 1994.
Place
Windermere (United Kingdom).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
28068459
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; FUEL RODS; GEOMETRY; MECHANICAL PROPERTIES; OPERATION; P CODES; SAFETY; SIMULATION; THERMODYNAMIC PROPERTIES; VARIATIONS; WWER-3 REACTOR
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; MATHEMATICS; PHYSICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information