Advanced search
Publication Cover
Nuclear Technology Volume 186, 2014 - Issue 2
Submit an article Journal homepage
83
Views
1
CrossRef citations to date
0
Altmetric
Technical Paper

MELCOR Simulations of the Severe Accident at the Fukushima Daiichi Unit 1 Reactor

Randall GaunttSandia National Laboratories, P.O. Box 5800, MS 0748, Albuquerque, New Mexico 87185-0748
,
Donald KalinichSandia National Laboratories, P.O. Box 5800, MS 0748, Albuquerque, New Mexico 87185-0748
,
Jeffrey CardoniSandia National Laboratories, P.O. Box 5800, MS 0748, Albuquerque, New Mexico 87185-0748
&
Jesse PhillipsSandia National Laboratories, P.O. Box 5800, MS 0748, Albuquerque, New Mexico 87185-0748
Pages 161-178 | Published online: 20 Mar 2017

REFERENCES

  • R. O. GAUNTT et al., “MELCOR Computer Code Manuals, Vol. 2: Reference Manuals, Version 1.8.6 (Vol. 2, Rev. 3),” NUREG/CR-6119, Sandia National Laboratories (2005).
  • R. GAUNTT et al., “Fukushima Daiichi Accident Study,” SAND2012-6173, Sandia National Laboratories (Aug. 2012).
  • “State-of-the-Art Reactor Consequence Analysis Project, Volume 1: Peach Bottom Integrated Analysis,” NUREG/CR-7110, Vol. 1, U.S. Nuclear Regulatory Commission (2012).
  • R. O. GAUNTT et al., “MELCOR Computer Code Manuals, Vol. 3: Demonstration Problems,” NUREG/CR-6119, Sandia National Laboratories (2001).
  • R. O. GAUNTT, “Synthesis of VERCORS and Phebus Data in Severe Accident Codes and Applications,” SAND-2010-1663, Sandia National Laboratories (2010).
  • F. MARTIN-FUERTES et al., “Analysis of Source Term Aspects in the Experiment Phebus FPR-1 with MELCOR and CTX Codes,” Nucl. Eng. Des., 237, 509 (2007); http://dx.doi.org/10.1016/j.nucengdes.2006.07.006.
  • L. E. HERRANZ et al., “Experimental Interpretation and Code Validation Based on the PHEBUC-FP Programme: Lessons Learnt from the Analysis of the Containment Scenario of FPT1 and FPT2 Tests,” Nucl. Eng. Des., 237, 2210 (2007); http://dx.doi.org/10.1016ZJ.nucengdes.2007.03.022.
  • T. HASTE et al., “MELCOR/MACCS Simulation of the TMI-2 Severe Accident and Initial Recovery Phases, Off-Site Fission Product Release and Consequences,” Nucl. Eng. Des, 236, 1099 (2006); http://dx.doi.org/10.1016/j.nucengdes.2005.11.012.
  • K. VIEROW et al., “Severe Accident Analysis of a PWR Station Blackout with the MELCOR, MAAP4 and SCDAP/RELAP5 Codes,” Nucl. Eng. Des., 234, 129 (2004); http://dx.doi.org/10.1016/j.nucengdes.2004.09.001.
  • R. O. GAUNTT et al., “The DF-4 Fuel Damage Experiment in ACRR with a BWR Control Blade and Channel Box,” NUREG/CR-4671, Sandia National Laboratories (1986).
  • R. O. GAUNTT and L. L. HUMPHRIES, “Final Results of the XR2-1 BWR Metallic Melt Relocation Experiment,” NUREG/CR-6527, U.S. Nuclear Regulatory Commission (1997).
  • T. Y. CHU et al., “Lower Head Failure Experiments and Analysis,” NUREG/CR-5582, Sandia National Laboratories (1998).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Order Reprints Request Corporate Permissions

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

Request Academic Permissions

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.

Supercharge Your Next Research Paper: Research and write your next paper with Jenni AI.

Related research

People also read lists articles that other readers of this article have read.

Recommended articles lists articles that we recommend and is powered by our AI driven recommendation engine.

Cited by lists all citing articles based on Crossref citations.
Articles with the Crossref icon will open in a new tab.