An European Conimunity sponsored Project focused on the subject ‘Accident Management (AIVI) in VVER-1000 reactors’ and is fmalized to the availability of suitable computational tools for AM optimization studies in those reactor types. The understanding of the current AM technology in Russian NPP, namely in the Balakovo Unit 3, and the critica! appraisal of the connected methocls are part of the Project activities. The Accident Management (and related terms ‘procedures’ and ‘strategies’) constitutes a branch of the nuclear reactor safety. The understanding of the meaning and of the objectives of the AM branch requires the knowledge of the safety/licensing concepts like Design Basis Accicient (DBA), Beyond DBA (BDBA), and Severe Accident (SA), as well as Probabilìstic Safety Assessment (PSA) and role of Human Factors (HF) within nuclear reactor safety. Based on the terminology, the AM branch occupies a virtual region before or upstream the SA area and aims at forming an additional boundary to the progression of accidents that eventually escaped the DBA boundary. This is done consistently with findings and requirements of the PSA branch, taking into account of the HF and of the available NPP components and systems and oftheir actual status. The best AIVI practice adopted in Westem Countries was considered. Specìfic features of the VVER- 1000 NPP were modeled including the deaerator and the related connections with the secondary side of steam generators. The result is the proposal of an AM procedure, where secondary side depressurization & feeding by deaerators connected with primary side depressurization & feeding by accumulators allow the longest time for keeping the integrity of the core inclucling the possibility of cooling by Low Pressure lnjection System (LPIS).

Accident management in VVER-1000

D'AURIA, FRANCESCO SAVERIO;
2006-01-01

Abstract

An European Conimunity sponsored Project focused on the subject ‘Accident Management (AIVI) in VVER-1000 reactors’ and is fmalized to the availability of suitable computational tools for AM optimization studies in those reactor types. The understanding of the current AM technology in Russian NPP, namely in the Balakovo Unit 3, and the critica! appraisal of the connected methocls are part of the Project activities. The Accident Management (and related terms ‘procedures’ and ‘strategies’) constitutes a branch of the nuclear reactor safety. The understanding of the meaning and of the objectives of the AM branch requires the knowledge of the safety/licensing concepts like Design Basis Accicient (DBA), Beyond DBA (BDBA), and Severe Accident (SA), as well as Probabilìstic Safety Assessment (PSA) and role of Human Factors (HF) within nuclear reactor safety. Based on the terminology, the AM branch occupies a virtual region before or upstream the SA area and aims at forming an additional boundary to the progression of accidents that eventually escaped the DBA boundary. This is done consistently with findings and requirements of the PSA branch, taking into account of the HF and of the available NPP components and systems and oftheir actual status. The best AIVI practice adopted in Westem Countries was considered. Specìfic features of the VVER- 1000 NPP were modeled including the deaerator and the related connections with the secondary side of steam generators. The result is the proposal of an AM procedure, where secondary side depressurization & feeding by deaerators connected with primary side depressurization & feeding by accumulators allow the longest time for keeping the integrity of the core inclucling the possibility of cooling by Low Pressure lnjection System (LPIS).
2006
1877040584
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11568/101463
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