A Flooding Induced Station Blackout Analysis for a Pressurized Water Reactor Using the RISMC Toolkit
In this paper we evaluate the impact of a power uprate on a pressurized water reactor (PWR) for a tsunami-induced flooding test case. This analysis is performed using the RISMC toolkit: the RELAP-7 and RAVEN codes. RELAP-7 is the new generation of system analysis codes that is responsible for simula...
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| Format: | Article |
| Language: | English |
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Wiley
2015-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2015/308163 |
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| author | Diego Mandelli Steven Prescott Curtis Smith Andrea Alfonsi Cristian Rabiti Joshua Cogliati Robert Kinoshita |
| author_facet | Diego Mandelli Steven Prescott Curtis Smith Andrea Alfonsi Cristian Rabiti Joshua Cogliati Robert Kinoshita |
| author_sort | Diego Mandelli |
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| description | In this paper we evaluate the impact of a power uprate on a pressurized water reactor (PWR) for a tsunami-induced flooding test case. This analysis is performed using the RISMC toolkit: the RELAP-7 and RAVEN codes. RELAP-7 is the new generation of system analysis codes that is responsible for simulating the thermal-hydraulic dynamics of PWR and boiling water reactor systems. RAVEN has two capabilities: to act as a controller of the RELAP-7 simulation (e.g., component/system activation) and to perform statistical analyses. In our case, the simulation of the flooding is performed by using an advanced smooth particle hydrodynamics code called NEUTRINO. The obtained results allow the user to investigate and quantify the impact of timing and sequencing of events on system safety. In addition, the impact of power uprate is determined in terms of both core damage probability and safety margins. |
| format | Article |
| id | doaj-art-19b5690e8fc44b69bbb2b9a44ede5950 |
| institution | OA Journals |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2015-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-19b5690e8fc44b69bbb2b9a44ede59502025-08-20T02:02:05ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832015-01-01201510.1155/2015/308163308163A Flooding Induced Station Blackout Analysis for a Pressurized Water Reactor Using the RISMC ToolkitDiego Mandelli0Steven Prescott1Curtis Smith2Andrea Alfonsi3Cristian Rabiti4Joshua Cogliati5Robert Kinoshita6Idaho National Laboratory (INL), 2525 Fremont Avenue, Idaho Falls, ID 83415, USAIdaho National Laboratory (INL), 2525 Fremont Avenue, Idaho Falls, ID 83415, USAIdaho National Laboratory (INL), 2525 Fremont Avenue, Idaho Falls, ID 83415, USAIdaho National Laboratory (INL), 2525 Fremont Avenue, Idaho Falls, ID 83415, USAIdaho National Laboratory (INL), 2525 Fremont Avenue, Idaho Falls, ID 83415, USAIdaho National Laboratory (INL), 2525 Fremont Avenue, Idaho Falls, ID 83415, USAIdaho National Laboratory (INL), 2525 Fremont Avenue, Idaho Falls, ID 83415, USAIn this paper we evaluate the impact of a power uprate on a pressurized water reactor (PWR) for a tsunami-induced flooding test case. This analysis is performed using the RISMC toolkit: the RELAP-7 and RAVEN codes. RELAP-7 is the new generation of system analysis codes that is responsible for simulating the thermal-hydraulic dynamics of PWR and boiling water reactor systems. RAVEN has two capabilities: to act as a controller of the RELAP-7 simulation (e.g., component/system activation) and to perform statistical analyses. In our case, the simulation of the flooding is performed by using an advanced smooth particle hydrodynamics code called NEUTRINO. The obtained results allow the user to investigate and quantify the impact of timing and sequencing of events on system safety. In addition, the impact of power uprate is determined in terms of both core damage probability and safety margins.http://dx.doi.org/10.1155/2015/308163 |
| spellingShingle | Diego Mandelli Steven Prescott Curtis Smith Andrea Alfonsi Cristian Rabiti Joshua Cogliati Robert Kinoshita A Flooding Induced Station Blackout Analysis for a Pressurized Water Reactor Using the RISMC Toolkit Science and Technology of Nuclear Installations |
| title | A Flooding Induced Station Blackout Analysis for a Pressurized Water Reactor Using the RISMC Toolkit |
| title_full | A Flooding Induced Station Blackout Analysis for a Pressurized Water Reactor Using the RISMC Toolkit |
| title_fullStr | A Flooding Induced Station Blackout Analysis for a Pressurized Water Reactor Using the RISMC Toolkit |
| title_full_unstemmed | A Flooding Induced Station Blackout Analysis for a Pressurized Water Reactor Using the RISMC Toolkit |
| title_short | A Flooding Induced Station Blackout Analysis for a Pressurized Water Reactor Using the RISMC Toolkit |
| title_sort | flooding induced station blackout analysis for a pressurized water reactor using the rismc toolkit |
| url | http://dx.doi.org/10.1155/2015/308163 |
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