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Probabilistic safety analysis of the Kozloduy NPP units 1-4 (WWER-440/230) using independent emergency feedwater system; Veroyatnostnyj analiz bezopasnosti I-IV blokov AEhS `Kozloduy` s reaktorami tipa WWER-440 (V 230) pri vklyuchenii nezavisimoj sistemy avarijnoj podpitki PG

Abstract

The safety of the Kozloduy NPP is being promoted by backfitting and improved operational practice. Special measures mitigating potential severe accidents consequences are needed because of some deficiencies in the original design of the four WWER-440 units. In conditions of a total LOCA (Loss Of Coolant Accident) it is impossible to ensure decay heat removal using the existing safety system. In such cases an extra emergency feedwater system independent of the plant`s other systems has been introduced which offers a new alternative means of removing the residual heat from the reactor. A probabilistic safety analysis is carried out using the method of event trees. A comparison between the existing safety system and the newly proposed is made. The simulation results of the unit behaviour prove that the damage frequency of the active zone is lower with the new system. 3 refs., 3 tabs., 2 figs.
Authors:
Kalchev, B; Marinov, M; Dimitrov, B; Avdzhiev, K [1] 
  1. Energoproekt, Sofia (Bulgaria)
Publication Date:
Dec 31, 1995
Product Type:
Miscellaneous
Report Number:
INIS-BG-0013; CONF-9410364-
Reference Number:
SCA: 210200; PA: AIX-28:034600; EDB-97:060678; SN: 97001775176
Resource Relation:
Conference: 1. scientific and technical conference on nuclear safety conference dedicated to NPP Kozloduy, Kozloduy (Bulgaria), 25-26 Oct 1994; Other Information: PBD: 1995; Related Information: Is Part Of Proceedings of a scientific-technical conference dedicated to the 20-th anniversary of Kozloduy NPP with international participation; PB: 442 p.
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; KOZLODUY-1 REACTOR; SAFETY; KOZLODUY-2 REACTOR; KOZLODUY-3 REACTOR; KOZLODUY-4 REACTOR; FAULT TREE ANALYSIS; FEEDWATER; LOSS OF COOLANT; PROBABILISTIC ESTIMATION; REACTOR OPERATION; RISK ASSESSMENT; THEORETICAL DATA
OSTI ID:
463255
Country of Origin:
Bulgaria
Language:
Russian
Other Identifying Numbers:
Other: ON: DE97621621; TRN: BG9600411034600
Availability:
INIS; OSTI as DE97621621
Submitting Site:
INIS
Size:
pp. 143-148
Announcement Date:

Citation Formats

Kalchev, B, Marinov, M, Dimitrov, B, and Avdzhiev, K. Probabilistic safety analysis of the Kozloduy NPP units 1-4 (WWER-440/230) using independent emergency feedwater system; Veroyatnostnyj analiz bezopasnosti I-IV blokov AEhS `Kozloduy` s reaktorami tipa WWER-440 (V 230) pri vklyuchenii nezavisimoj sistemy avarijnoj podpitki PG. Bulgaria: N. p., 1995. Web.
Kalchev, B, Marinov, M, Dimitrov, B, & Avdzhiev, K. Probabilistic safety analysis of the Kozloduy NPP units 1-4 (WWER-440/230) using independent emergency feedwater system; Veroyatnostnyj analiz bezopasnosti I-IV blokov AEhS `Kozloduy` s reaktorami tipa WWER-440 (V 230) pri vklyuchenii nezavisimoj sistemy avarijnoj podpitki PG. Bulgaria.
Kalchev, B, Marinov, M, Dimitrov, B, and Avdzhiev, K. 1995. "Probabilistic safety analysis of the Kozloduy NPP units 1-4 (WWER-440/230) using independent emergency feedwater system; Veroyatnostnyj analiz bezopasnosti I-IV blokov AEhS `Kozloduy` s reaktorami tipa WWER-440 (V 230) pri vklyuchenii nezavisimoj sistemy avarijnoj podpitki PG." Bulgaria.
@misc{etde_463255,
title = {Probabilistic safety analysis of the Kozloduy NPP units 1-4 (WWER-440/230) using independent emergency feedwater system; Veroyatnostnyj analiz bezopasnosti I-IV blokov AEhS `Kozloduy` s reaktorami tipa WWER-440 (V 230) pri vklyuchenii nezavisimoj sistemy avarijnoj podpitki PG}
author = {Kalchev, B, Marinov, M, Dimitrov, B, and Avdzhiev, K}
abstractNote = {The safety of the Kozloduy NPP is being promoted by backfitting and improved operational practice. Special measures mitigating potential severe accidents consequences are needed because of some deficiencies in the original design of the four WWER-440 units. In conditions of a total LOCA (Loss Of Coolant Accident) it is impossible to ensure decay heat removal using the existing safety system. In such cases an extra emergency feedwater system independent of the plant`s other systems has been introduced which offers a new alternative means of removing the residual heat from the reactor. A probabilistic safety analysis is carried out using the method of event trees. A comparison between the existing safety system and the newly proposed is made. The simulation results of the unit behaviour prove that the damage frequency of the active zone is lower with the new system. 3 refs., 3 tabs., 2 figs.}
place = {Bulgaria}
year = {1995}
month = {Dec}
}