Probabilistic safety assessment (PSA) of nuclear power plants is performed to yield insights into the safety, design, and performance of the plants and their potential environmental effects. This includes the identification of dominant risk contributors, determination of the vulnerabilities of plant and containment systems, and comparison of options for risk reduction. Three levels of PSA are recognized. Level-1 addresses the identification of plant failures leading to core damage and their frequencies of occurrence. Level-2 addresses the assessment of containment response leading together with level-1 results to the determination of containment release frequencies. A level-2 PSA analyses the challenges to the containment, the possible containment responses and their estimated probabilities, and an assessment of the consequent releases to the environment. Level-3 is the assessment of off-site consequences leading, together with the results of level-2 analysis, for estimation of public risks. A comprehensive level-2 PSA study of a 220 MWe Indian Pressurized Heavy Water Reactor (IPHWR) is performed to assess the challenges to the containment, the possible containment responses and their estimated probabilities, and consequent releases to the environment. The dominating sequences consist of small-break loss of coolant accident (SBLOCA) and station black out (SBO) followed by containment isolation failure. The results of this are used as an input for developing the severe accident management guidelines (SAMG) measures. All the SAMG measures incorporated in this study have been found as beneficial and resulted in reduced large early release frequency (LERF).
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April 2017
Research-Article
Progression of Severe Accidents, Containment Performance, and Estimates of Releases of Radionuclides-Level-2 Probabilistic Safety Assessment IPHWR
Rajee Guptan,
Rajee Guptan
Department of Atomic Energy,
Nuclear Power Corporation of India Limited,
C-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: grajee@npcil.co.in
Nuclear Power Corporation of India Limited,
C-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: grajee@npcil.co.in
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A. K. Vijaya,
A. K. Vijaya
Department of Atomic Energy,
Nuclear Power Corporation of India Limited,
C-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: akvijaya@npcil.co.in
Nuclear Power Corporation of India Limited,
C-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: akvijaya@npcil.co.in
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Vibha Hari,
Vibha Hari
Department of Atomic Energy,
Nuclear Power Corporation of India Limited,
C-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: vibhahari@npcil.co.in
Nuclear Power Corporation of India Limited,
C-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: vibhahari@npcil.co.in
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Rajeev Nama
Rajeev Nama
Department of Atomic Energy,
Nuclear Power Corporation of India Limited,
B-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: rnama@npcil.co.in
Nuclear Power Corporation of India Limited,
B-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: rnama@npcil.co.in
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Rajee Guptan
Department of Atomic Energy,
Nuclear Power Corporation of India Limited,
C-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: grajee@npcil.co.in
Nuclear Power Corporation of India Limited,
C-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: grajee@npcil.co.in
A. K. Vijaya
Department of Atomic Energy,
Nuclear Power Corporation of India Limited,
C-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: akvijaya@npcil.co.in
Nuclear Power Corporation of India Limited,
C-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: akvijaya@npcil.co.in
Vibha Hari
Department of Atomic Energy,
Nuclear Power Corporation of India Limited,
C-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: vibhahari@npcil.co.in
Nuclear Power Corporation of India Limited,
C-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: vibhahari@npcil.co.in
Rajeev Nama
Department of Atomic Energy,
Nuclear Power Corporation of India Limited,
B-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: rnama@npcil.co.in
Nuclear Power Corporation of India Limited,
B-3 NUB, Anushaktinagar,
Mumbai 400094, India
e-mail: rnama@npcil.co.in
Manuscript received July 19, 2016; final manuscript received January 6, 2017; published online March 1, 2017. Assoc. Editor: Thambiayah Nitheanandan.
ASME J of Nuclear Rad Sci. Apr 2017, 3(2): 020910 (7 pages)
Published Online: March 1, 2017
Article history
Received:
July 19, 2016
Revised:
January 6, 2017
Citation
Guptan, R., Vijaya, A. K., Hari, V., and Nama, R. (March 1, 2017). "Progression of Severe Accidents, Containment Performance, and Estimates of Releases of Radionuclides-Level-2 Probabilistic Safety Assessment IPHWR." ASME. ASME J of Nuclear Rad Sci. April 2017; 3(2): 020910. https://doi.org/10.1115/1.4035783
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