A flooding induced station blackout analysis for a pressurized water reactor using the RISMC toolkit

Journal Article · Sun May 17 00:00:00 EDT 2015 · Science and Technology of Nuclear Installations

DOI:https://doi.org/10.1155/2015/308163· OSTI ID:1223301

Mandelli, Diego ^[1]; Prescott, Steven ^[1]; Smith, Curtis ^[1]; Alfonsi, Andrea ^[1]; Rabiti, Cristian ^[1]; Cogliati, Joshua ^[1]; Kinoshita, Robert ^[1]

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1. Idaho National Lab. (INL), Idaho Falls, ID (United States)

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. The impact of power uprate is determined in terms of both core damage probability and safety margins.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE
• Grant/Contract Number: AC07-05ID14517
• OSTI ID: 1223301
• Journal Information: Science and Technology of Nuclear Installations, Vol. 2015; ISSN 1687-6075
• Publisher: Hindawi
• Country of Publication: United States
• Language: English

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