A flooding induced station blackout analysis for a pressurized water reactor using the RISMC toolkit
Abstract
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.
- Authors:
-
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Publication Date:
- Research Org.:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1223301
- Grant/Contract Number:
- AC07-05ID14517
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Science and Technology of Nuclear Installations
- Additional Journal Information:
- Journal Volume: 2015; Journal ID: ISSN 1687-6075
- Publisher:
- Hindawi
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
Citation Formats
Mandelli, Diego, Prescott, Steven, Smith, Curtis, Alfonsi, Andrea, Rabiti, Cristian, Cogliati, Joshua, and Kinoshita, Robert. A flooding induced station blackout analysis for a pressurized water reactor using the RISMC toolkit. United States: N. p., 2015.
Web. doi:10.1155/2015/308163.
Mandelli, Diego, Prescott, Steven, Smith, Curtis, Alfonsi, Andrea, Rabiti, Cristian, Cogliati, Joshua, & Kinoshita, Robert. A flooding induced station blackout analysis for a pressurized water reactor using the RISMC toolkit. United States. https://doi.org/10.1155/2015/308163
Mandelli, Diego, Prescott, Steven, Smith, Curtis, Alfonsi, Andrea, Rabiti, Cristian, Cogliati, Joshua, and Kinoshita, Robert. Sun .
"A flooding induced station blackout analysis for a pressurized water reactor using the RISMC toolkit". United States. https://doi.org/10.1155/2015/308163. https://www.osti.gov/servlets/purl/1223301.
@article{osti_1223301,
title = {A flooding induced station blackout analysis for a pressurized water reactor using the RISMC toolkit},
author = {Mandelli, Diego and Prescott, Steven and Smith, Curtis and Alfonsi, Andrea and Rabiti, Cristian and Cogliati, Joshua and Kinoshita, Robert},
abstractNote = {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.},
doi = {10.1155/2015/308163},
journal = {Science and Technology of Nuclear Installations},
number = ,
volume = 2015,
place = {United States},
year = {Sun May 17 00:00:00 EDT 2015},
month = {Sun May 17 00:00:00 EDT 2015}
}
Web of Science
Works referenced in this record:
A concept paper on dynamic reliability via Monte Carlo simulation
journal, August 1998
- Marseguerra, M.; Zio, E.; Devooght, J.
- Mathematics and Computers in Simulation, Vol. 47, Issue 2-5
Versatile rigid-fluid coupling for incompressible SPH
journal, July 2012
- Akinci, Nadir; Ihmsen, Markus; Akinci, Gizem
- ACM Transactions on Graphics, Vol. 31, Issue 4
Versatile rigid-fluid coupling for incompressible SPH
journal, August 2012
- Akinci, Nadir; Ihmsen, Markus; Akinci, Gizem
- ACM Transactions on Graphics, Vol. 31, Issue 4
Latin hypercube sampling and the propagation of uncertainty in analyses of complex systems
journal, July 2003
- Helton, J. C.; Davis, F. J.
- Reliability Engineering & System Safety, Vol. 81, Issue 1
MOOSE: A parallel computational framework for coupled systems of nonlinear equations
journal, October 2009
- Gaston, Derek; Newman, Chris; Hansen, Glen
- Nuclear Engineering and Design, Vol. 239, Issue 10
Reduced Order Modeling for Nonlinear Multi-Component Models
journal, January 2012
- Abdel-Khalik, Hany S.; Bang, Youngsuk; Kennedy, Christopher
- International Journal for Uncertainty Quantification, Vol. 2, Issue 4
Works referencing / citing this record:
Large-scale solitary wave simulation with implicit incompressible SPH
journal, June 2016
- Sampath, Ramprasad; Montanari, Niels; Akinci, Nadir
- Journal of Ocean Engineering and Marine Energy, Vol. 2, Issue 3
Mining data in a dynamic PRA framework
journal, September 2018
- Mandelli, D.; Maljovec, D.; Alfonsi, A.
- Progress in Nuclear Energy, Vol. 108