ATWS analyses for VVER-91 concept by the SMATRA Code

Journal Article · Fri Dec 31 04:00:00 EST 1993 · Transactions of the American Nuclear Society

OSTI ID:107300

Kyrki-Rajamaeki, R; Miettinen, J; Raety, H; Vanttola, T ^[1]; Siltanen, P ^[2]; Fil, N S ^[3]

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1. Technical Research Centre, Espoo (Finland)
2. Imatran Voima Oy, Espoo (Finland)
3. OKB Gidopress, Moscow (Russian Federation)

This year, 7 different offers have been handed in for the fifth nuclear power unit of Finland. One of them is the VVER-91 plant concept of VVO Atomenergoexport (AEE). In cooperation with IVO International planning work has been made in order to fulfil the strict safety criteria of the Finnish authorities. Part of the accident analyses have been made by the Technical Research Centre of Finland (VTT). In Finland there is experience of the VVER type reactors. There are two VVER-440 reactors in Loviisa. A group of analyses made in VTT includes cases that belong to the class of Anticipated Transient Without Scram (ATWS). In this paper, methods and results of some loss of feedwater ATWS analyses are discussed.

• OSTI ID: 107300
• Report Number(s): CONF-920957--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Journal Issue: Suppl.1 Vol. 67; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
CONTROL ELEMENTS
FEEDWATER
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
S CODES
SCRAM