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YKAe - Research programme on nuclear power plant systems behaviour and operational aspects of safety. Interim report January 1990 - May 1992

Technical Report:

Abstract

The major part of nuclear energy research in Finland has been organised as five-year nationally coordinated research programs. The research programme on Systems Behaviour and Operational Aspects of Safety is under way during 1990-1994. Its annual volume has been about 35 person-years and its annual expenditure about FIM 18 million. Studies in the field on safe operational margins of nuclear fuel and reactor core concentrate on fuel high burn-up behaviour, VVER fuel experiments, and reactor core behaviour in complex reactivity transients such as 3-D phenomena and ATWS events. The PACTEL facility is used for the thermal hydraulic studies of the Loviisa type reactors (scaled 1:305). Validation of accident analysis codes is carried out by participation in international standard problems. Advanced foreign computer codes for severe reactor accidents are implemented, modified as needed and applied to level-2 PSAs and the improvement of accident management procedures. Fire simulation methods are tested using data from experiments in the German HDR facility. A nuclear plant analyzer for efficient safety analyses is being developed using the APROS process simulation environment. Computerized operator support systems are being studied in cooperation with the OECD Halden Project. The basic factors affecting plant operator activities and the development of  More>>
Authors:
Mattila, L; Vanttola, T [1] 
  1. eds.
Publication Date:
Dec 31, 1992
Product Type:
Technical Report
Report Number:
KTM/E-B-119
Reference Number:
SCA: 210200; 210100; 990100; PA: AIX-24:002503; SN: 93000913289
Resource Relation:
Other Information: DN: Finland`s energy research programmes.; PBD: 1992
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; FINLAND; REACTOR SAFETY; COORDINATED RESEARCH PROGRAMS; BWR TYPE REACTORS; COMPUTER CODES; COMPUTERIZED SIMULATION; NUCLEAR FUELS; REACTOR ACCIDENTS; REACTOR KINETICS; RISK ASSESSMENT; WWER TYPE REACTORS; 210200; 210100; 990100; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, BOILING WATER COOLED; MANAGEMENT
OSTI ID:
10108834
Research Organizations:
Ministry of Trade and Industry, Helsinki (Finland). Energy Dept.
Country of Origin:
Finland
Language:
English
Other Identifying Numbers:
Other: ON: DE93609469; ISBN 951-47-5893-5; TRN: FI9200080002503
Availability:
OSTI; NTIS; INIS
Submitting Site:
FIN
Size:
[183] p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Mattila, L, and Vanttola, T. YKAe - Research programme on nuclear power plant systems behaviour and operational aspects of safety. Interim report January 1990 - May 1992. Finland: N. p., 1992. Web.
Mattila, L, & Vanttola, T. YKAe - Research programme on nuclear power plant systems behaviour and operational aspects of safety. Interim report January 1990 - May 1992. Finland.
Mattila, L, and Vanttola, T. 1992. "YKAe - Research programme on nuclear power plant systems behaviour and operational aspects of safety. Interim report January 1990 - May 1992." Finland.
@misc{etde_10108834,
title = {YKAe - Research programme on nuclear power plant systems behaviour and operational aspects of safety. Interim report January 1990 - May 1992}
author = {Mattila, L, and Vanttola, T}
abstractNote = {The major part of nuclear energy research in Finland has been organised as five-year nationally coordinated research programs. The research programme on Systems Behaviour and Operational Aspects of Safety is under way during 1990-1994. Its annual volume has been about 35 person-years and its annual expenditure about FIM 18 million. Studies in the field on safe operational margins of nuclear fuel and reactor core concentrate on fuel high burn-up behaviour, VVER fuel experiments, and reactor core behaviour in complex reactivity transients such as 3-D phenomena and ATWS events. The PACTEL facility is used for the thermal hydraulic studies of the Loviisa type reactors (scaled 1:305). Validation of accident analysis codes is carried out by participation in international standard problems. Advanced foreign computer codes for severe reactor accidents are implemented, modified as needed and applied to level-2 PSAs and the improvement of accident management procedures. Fire simulation methods are tested using data from experiments in the German HDR facility. A nuclear plant analyzer for efficient safety analyses is being developed using the APROS process simulation environment. Computerized operator support systems are being studied in cooperation with the OECD Halden Project. The basic factors affecting plant operator activities and the development of their competence are being investigated. A comprehensive system for the control of plant operational safety is being developed by combining living PSA and safety indicators.}
place = {Finland}
year = {1992}
month = {Dec}
}