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Science and Technology of Nuclear Installations
Volume 2010, Article ID 425658, 17 pages
http://dx.doi.org/10.1155/2010/425658
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Role of RELAP/SCDAPSIM in Nuclear Safety

Innovative Systems Software, LLC, 1284 South Woodruff Avenue, Idaho Falls, ID 83404, USA

Received 17 August 2009; Accepted 10 January 2010

Academic Editor: Michel Giot

Copyright © 2010 C. M. Allison and J. K. Hohorst. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Citations to this Article [38 citations]

The following is the list of published articles that have cited the current article.

  • Gergana Gerova, Ivan Spasov, Chris Allison, and Martin Steinbrück, “Modeling and simulation of the QUENCH 12 experiment with the RELAP/SCDAPSIM/MOD3.5 code,” vol. 2048, pp. 020019, . View at Publisher · View at Google Scholar
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  • C. M. Allison, J. K. Hohorst, B. S. Allison, D. Konjarek, T. Bajs, R. Pericas, F. Reventos, and R. Lopez, “Preliminary Assessment of the Possible BWR Core/Vessel Damage States for Fukushima Daiichi Station Blackout Scenarios Using RELAP/SCDAPSIM,” Science and Technology of Nuclear Installations, vol. 2012, pp. 1–25, 2012. View at Publisher · View at Google Scholar
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  • Pavlin Groudev, Marina Andreeva, and Malinka Pavlova, “Investigation of nuclear power plant behaviour at low power and cold conditions during an overpressurization in primary circuit,” Annals of Nuclear Energy, vol. 62, pp. 231–241, 2013. View at Publisher · View at Google Scholar
  • Stefan Nicolici, Daniel Dupleac, and Ilie Prisecaru, “Numerical analysis of debris melting phenomena during late phase CANDU 6 severe accident,” Nuclear Engineering And Design, vol. 254, pp. 272–279, 2013. View at Publisher · View at Google Scholar
  • Javier Ortiz-Villafuerte, Andrés Rodríguez-Hernández, Enrique Araiza-Martínez, Luis Fuentes-Márquez, and Jorge Viais-Juárez, “BWR/5 Pressure-Suppression Pool Response during an SBO,” Science and Technology of Nuclear Installations, vol. 2013, pp. 1–8, 2013. View at Publisher · View at Google Scholar
  • Algirdas Kaliatka, Viktor Ognerubov, Virginijus Vileiniškis, and Eugenijus Ušpuras, “Analysis of the Processes in Spent Fuel Pools in Case of Loss of Heat Removal due to Water Leakage,” Science and Technology of Nuclear Installations, vol. 2013, pp. 1–11, 2013. View at Publisher · View at Google Scholar
  • J. Fleurot, I. Lindholm, N. Kononen, S. Ederli, B. Jaeckel, A. Kaliatka, J. Duspiva, M. Steinbrueck, and T. Hollands, “Synthesis of spent fuel pool accident assessments using severe accident codes,” Annals of Nuclear Energy, 2014. View at Publisher · View at Google Scholar
  • Hiroshi Madokoro, Nejdet Erkan, and Koji Okamoto, “Assessment of the models in RELAP/SCDAPSIM with QUENCH-06 analysis,” Journal of Nuclear Science and Technology, pp. 1–8, 2015. View at Publisher · View at Google Scholar
  • Chris Allison, Víctor Martinez-Quiroga, Sabahattin Akbas, Fatih Aydogan, and Abderrafi M. Ougouag, “Coupling of RELAP5-SCDAP MOD4.0 and neutronic codes,” ASME International Mechanical Engineering Congress and Exposition, Proceedings (IMECE), vol. 6, 2015. View at Publisher · View at Google Scholar
  • 建阁 刘, “A Comparison Study of Once-Through Steam Generation Calculation with the Different Fluid Dynamic Models of the RELAP5 Code,” Nuclear Science and Technology, vol. 03, no. 03, pp. 70–77, 2015. View at Publisher · View at Google Scholar
  • Khanna, Munshi, Trivedi, and Allison, “RELAP5/SCDAPSIM model development for AP1000 and verification for large break LOCA,” Nuclear Engineering and Design, vol. 305, pp. 222–229, 2016. View at Publisher · View at Google Scholar
  • A.K. Trivedi, C. Allison, A. Khanna, and P. Munshi, “AP1000 station blackout study with and without depressurization using RELAP5/SCDAPSIM,” Nuclear Engineering and Design, vol. 307, pp. 299–308, 2016. View at Publisher · View at Google Scholar
  • Javier Ortiz-Villafuerte, “Time step impact on the results of BWR SBO severe accident simulations using the versions bi7 and bik of RELAP/SCDAPSIM/MOD3.4 executing on AMD and Intel processors,” International Journal of Nuclear Energy Science and Technology, vol. 10, no. 3, pp. 245–256, 2016. View at Publisher · View at Google Scholar
  • Javier Ortiz-Villafuerte, and Enrique Araiza-Martínez, “Platform independence study of RELAP/SCDAPSIM/MOD3.4 versions bi7 and bik on two AMD and two Intel processors by simulation of a BWR SBO severe accident,” International Journal of Nuclear Energy Science and Technology, vol. 10, no. 4, pp. 338–355, 2016. View at Publisher · View at Google Scholar
  • Pavlin Groudev, and Marina Andreeva, “Study of Accident Progression in Unsealed WWER-1000/V320 Reactor during Maintenance,” Journal of Power and Energy Engineering, vol. 04, no. 08, pp. 68–78, 2016. View at Publisher · View at Google Scholar
  • Efrizon Umar, Anhar Riza Antariksawan, Surip Widodo, Mulya Juarsa, and Mukhsinun Hadi Kusuma, “TRIGA-2000 research reactor thermal-hydraulic analysis using RELAP/SCDAPSIM/MOD3.4,” International Journal of Technology, vol. 8, no. 4, pp. 698–708, 2017. View at Publisher · View at Google Scholar
  • Feng Zhou, and David R. Novog, “RELAP5 simulation of CANDU Station Blackout accidents with/without water make-up to the steam generators,” Nuclear Engineering and Design, vol. 318, pp. 35–53, 2017. View at Publisher · View at Google Scholar
  • R.S. Denning, and R.J. Budnitz, “Impact of probabilistic risk assessment and severe accident research in reducing reactor risk,” Progress in Nuclear Energy, 2017. View at Publisher · View at Google Scholar
  • Noppawan Rattanadecho, Somboon Rassame, Kampanart Silva, Chris Allison, and Judith Hohorst, “Assessment of RELAP/SCDAPSIM/MOD3.4 Prediction Capability with Severe Fuel Damage Scoping Test,” Science and Technology of Nuclear Installations, vol. 2017, pp. 1–12, 2017. View at Publisher · View at Google Scholar
  • Anhar R. Antariksawan, Giarno, M. Hadi Kusuma, Nandy Putra, Surip Widodo, and Mulya Juarsa, “Preliminary investigation of natural circulation stability in FASSIP-01 experimental facility using RELAP5 code,” AIP Conference Proceedings, vol. 2001, 2018. View at Publisher · View at Google Scholar
  • F. Zhou, and D.R. Novog, “Mechanistic modelling of station blackout accidents for a generic 900 MW CANDU plant using the modified RELAP/SCDAPSIM/MOD3.6 code,” Nuclear Engineering and Design, vol. 335, pp. 71–93, 2018. View at Publisher · View at Google Scholar
  • F. Zhou, D. R. Novog, L. J. Siefken, and C. M. Allison, “Development and Benchmark of Mechanistic Channel Deformation Models in RELAP/SCDAPSIM/MOD3.6 for CANDU Severe Accident Analysis,” Nuclear Science and Engineering, pp. 1–29, 2018. View at Publisher · View at Google Scholar
  • Anhar R. Antariksawan, Puradwi I. Wahyono, and Taxwim, “Steady state and LOCA analysis of Kartini reactor using RELAP5/SCDAP code: The role of passive system,” Journal of Physics: Conference Series, vol. 962, pp. 012048, 2018. View at Publisher · View at Google Scholar
  • F. Salaun, and D. R. Novog, “Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations,” Journal of Nuclear Engineering and Radiation Science, vol. 4, no. 2, pp. 021003, 2018. View at Publisher · View at Google Scholar
  • Carolina Introini, Stefano Lorenzi, Antonio Cammi, Davide Baroli, Bernhard Peters, and Stéphane Bordas, “A Mass Conservative Kalman Filter Algorithm for Computational Thermo-Fluid Dynamics,” Materials, vol. 11, no. 11, pp. 2222, 2018. View at Publisher · View at Google Scholar
  • Frederic Salaun, and David R. Novog, “Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics,” Science and Technology of Nuclear Installations, vol. 2018, pp. 1–17, 2018. View at Publisher · View at Google Scholar
  • Anuj Trivedi, Marina Perez-Ferragut, Katarzyna Skolik, and Chris Allison, “Assessment of RELAP/SCDAPSIM for turbine trip transient in nuscale-SMR,” International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 6B, 2018. View at Publisher · View at Google Scholar
  • Le, Gerova, Hohorst, Allison, Spasov, and Perez-Ferragut, “Quench-06 experiment post-test calculations and integrated uncertainty analysis with RELAP/SCDAPSIM/MOD3.4 and MOD3.5,” International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 4, 2018. View at Publisher · View at Google Scholar
  • Surip Widodo, and Andi Sofrany Ekariansyah, “Transient Analysis of CVCS Malfunction in Large Passive PWR,” Journal of Physics: Conference Series, vol. 1198, no. 2, pp. 022016, 2019. View at Publisher · View at Google Scholar
  • Anhar R. Antariksawan, Mukhsinun Hadi Kusuma, Surip Widodo, Giarno, Mulya Juarsa, Hendro Tjahyono, and Dedy Haryanto, “Assessment of RELAP5 code model to simulate U-shaped heat pipe performance for heat sink,” Journal of Physics: Conference Series, vol. 1198, no. 2, pp. 022063, 2019. View at Publisher · View at Google Scholar
  • Sabahattin Akbas, Chris Allison, Victor M. Quiroga, Fatih Aydogan, and Abderrafi M. Ougouag, “Thermal-hydraulics and neutronic code coupling for RELAP/SCDAPSIM/MOD4.0,” Nuclear Engineering and Design, vol. 344, pp. 174–182, 2019. View at Publisher · View at Google Scholar
  • Farhan Zahid, Fatih Aydogan, Mahmood Shakil, Muhammad Ilyas, and Masroor Ahmad, “Analysis of loss of residual heat removal system during mid-loop operation of a 300 MWe PWR,” Progress in Nuclear Energy, vol. 112, pp. 1–6, 2019. View at Publisher · View at Google Scholar
  • Hiroshi Madokoro, Alexei Miassoedov, and Thomas Schulenberg, “Coupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver,” Journal of Nuclear Engineering and Radiation Science, vol. 5, no. 1, pp. 011017, 2019. View at Publisher · View at Google Scholar