Published 1997 | Version v1
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Overcooling transient selection and thermal hydraulic analyses of the Loviisa PTS assessments

Creators

  • 1. IVO Power Engineering Ltd, Vantaa (Finland)

Description

This paper describes transients selection and thermal hydraulic analyses of various PTS assessment studies performed for the pressure vessels of the Loviisa WWER-reactors. Deterministic analyses have been performed in various stages of the PTS studies and they have always made the formal basis for design and licensing of the reactor pressure vessel. The integrated, probabilistic PTS study was carried out to give an overview of the severity of all different PTS sequences, and give a quantitative estimate of the importance of the PTS issues in relation to the overall safety of the plant. Later, the sequences including external flooding of the pressure vessels were added to the PTS assessment. Thermal recovery annealing of the Loviisa 1 reactor pressure vessel took place during refuelling outage in 1996. (author). 10 refs, 4 figs, 3 tabs

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Part of:
Methodology for pressurized thermal shock evaluation. Proceedings of the IAEA specialists meeting. Working material

Additional details

Publishing Information

Imprint Title
Methodology for pressurized thermal shock evaluation. Proceedings of the IAEA specialists meeting. Working material
Imprint Pagination
457 p.
Journal Page Range
p. 207-221.
Report number
IWG-LMNPP--96/1

Conference

Title
IAEA specialists' meeting on methodology for pressurized thermal shock evaluation.
Dates
5-8 May 1997.
Place
Esztergom (Hungary).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
28059645
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
EVALUATION; HYDRAULICS; LOVIISA-1 REACTOR; LOVIISA-2 REACTOR; PRESSURE VESSELS; PROBABILISTIC ESTIMATION; TEMPERATURE DEPENDENCE; THERMAL SHOCK; TRANSIENTS
Descriptors DEC
CONTAINERS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information