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Plant experience with check valves in passive systems

Abstract

In the design of the advanced nuclear reactors there is a tendency to introduce more passive safety systems. The 25 year old design of the GKN nuclear reactor is different from the present BWR reactors because of some special features, such as the Natural Circulation - and the Passive Isolation Condenser system. When reviewing the design, one can conclude that the plant has 25 years of experience with check valves in passive systems and as passive components in systems. The result of this experience has been modeled in a plant-specific ``living PSA`` for the plant. A data-analysis has been performed on components which are related to the safety systems in the plant. As part of this study also the check valves have been taken in consideration. At GKN, the check valves have shown to be reliable components in the systems and no catastrophic failures have been experienced during the 25 years of operation. Especially the Isolation Condenser with its operation experience can contribute substantially to the insight of check valves in stand-by position at reactor pressure and operating by gravity under different pressure conditions. With the introduction of several passive systems in the SBWR-600 design, such as the Isolation Condensers,  More>>
Authors:
Pahladsingh, R R [1] 
  1. GKN Joint Nuclear Power Plant, Dodewaard (Netherlands)
Publication Date:
Dec 01, 1996
Product Type:
Conference
Report Number:
IAEA-TECDOC-920; CONF-9411339-
Reference Number:
SCA: 210100; PA: AIX-28:021731; EDB-97:039685; SN: 97001747488
Resource Relation:
Conference: Advisory group meeting on technical feasibility and reliability of passive safety systems for nuclear power plants, Juelich (Germany), 21-24 Nov 1994; Other Information: PBD: Dec 1996; Related Information: Is Part Of Technical feasibility and reliability of passive safety systems for nuclear power plants. Proceedings of an advisory group meeting; PB: 357 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; REACTOR SAFETY; DESIGN; ISOLATION CONDENSERS; MODIFICATIONS; NATURAL CONVECTION; NUCLEAR POWER PLANTS; VALVES
OSTI ID:
443190
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 1011-4289; Other: ON: DE97615987; TRN: XA9743159021731
Availability:
INIS; OSTI as DE97615987
Submitting Site:
INIS
Size:
pp. 67-78
Announcement Date:

Citation Formats

Pahladsingh, R R. Plant experience with check valves in passive systems. IAEA: N. p., 1996. Web.
Pahladsingh, R R. Plant experience with check valves in passive systems. IAEA.
Pahladsingh, R R. 1996. "Plant experience with check valves in passive systems." IAEA.
@misc{etde_443190,
title = {Plant experience with check valves in passive systems}
author = {Pahladsingh, R R}
abstractNote = {In the design of the advanced nuclear reactors there is a tendency to introduce more passive safety systems. The 25 year old design of the GKN nuclear reactor is different from the present BWR reactors because of some special features, such as the Natural Circulation - and the Passive Isolation Condenser system. When reviewing the design, one can conclude that the plant has 25 years of experience with check valves in passive systems and as passive components in systems. The result of this experience has been modeled in a plant-specific ``living PSA`` for the plant. A data-analysis has been performed on components which are related to the safety systems in the plant. As part of this study also the check valves have been taken in consideration. At GKN, the check valves have shown to be reliable components in the systems and no catastrophic failures have been experienced during the 25 years of operation. Especially the Isolation Condenser with its operation experience can contribute substantially to the insight of check valves in stand-by position at reactor pressure and operating by gravity under different pressure conditions. With the introduction of several passive systems in the SBWR-600 design, such as the Isolation Condensers, Gravity Driven Cooling, and Suppression Pool Cooling System, the issue of reliability of check valves in these systems is actual. Some critical aspects for study in connection with check valves are: What is the reliability of a check valve in a system at reactor pressure, to open on demand; what is the reliability of a check valve in a system at low pressure (gravity), to open on demand; what is the reliability of a check valve to open/close when the stand-by check wave is at zero differential pressure. The plant experience with check valves in a few essential safety systems is described and a brief introduction will be made about the application of check valves in the design of the new generation reactors is given. (author). 6 figs, 1 tab.}
place = {IAEA}
year = {1996}
month = {Dec}
}