736
Views
5
CrossRef citations to date
0
Altmetric
Technical Papers

Severe Accident Phenomena: A Comparison Among the NuScale SMR, Other Advanced LWR Designs, and Operating LWRs

& ORCID Icon
Pages 1351-1360 | Received 13 Dec 2019, Accepted 13 Apr 2020, Published online: 07 Jul 2020

References

  • Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” NUREG-0800, Sec. 19.0, Rev. 3, “Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors,” U.S. Nuclear Regulatory Commission, ADAMAS Accession No. ML15089A068 (2015).
  • Probabilistic Risk Assessment and Severe Accident Evaluation,” Chap. 19, in “NuScale Final Safety Analysis Report, Part 2 – Tier 2,” Rev. 2, NuScale, ADAMS Accession No. ML18310A342 (2018).
  • Tennessee Valley Authority Letter CNL-17-101, Enclosure 1, Response to U.S. Nuclear Regulatory Commission Electronic Request for Additional Information 8885 (eRAI 8885), ADAMS Accession No. ML17237A175 (2017).
  • D. JACQUEMAIN et al., “Nuclear Power Reactor Core Melt Accidents Current State of Knowledge,” Institut de Radioprotection et de Sûreté Nucléaire (2015).
  • K. TERRANI, “Accident Tolerant Fuel Cladding Development: Promise, Status, Challenges,” Oak Ridge National Laboratory (2018).
  • M. GAVRILAS et al., “Severe Accident Considerations,” Safety Features of Operating Light Water Reactors of Western Design, Chap. 9, Massachusetts Institute of Technology, Center for Advanced Nuclear Energy Systems (2000).
  • “Light Water Reactor Hydrogen Manual,” SAND82-1137, NUREG/CR-2726, Sandia National Laboratories, ADAMS Accession No. ML071620344 (1983).
  • F. ARNOULD et al. “State of the Art on Hydrogen Passive Autocatalytic Recombiner (European Union PARSOAR Project),” Proc. 9th Int. Conf. Nuclear Engineering, Nice, France, April 8–12, 2001.
  • “A Reassessment of the Potential for an Alpha-Mode Containment Failure and a Review of the Current Understanding of Broader Fuel-Coolant Interaction Issues,” NUREG-1524, U.S. Nuclear Regulatory Commission (1996).
  • “In-Vessel Retention of Molten Core Debris,” Chap. 19.39, in “Westinghouse AP1000 Design Control Document, Part 2 – Tier 2,” Rev. 19, ADAMS Accession No. ML11171A408 (2011).
  • “Critical Heat Flux (CHF) Phenomenon on a Downward Facing Curved Surface,” NUREG/CR-6507, U.S. Nuclear Regulatory Commission (1997).
  • Severe Accident Phenomena Treatment,” Chap. 19.34, in “Westinghouse AP1000 Design Control Document, Part 2 – Tier 2,” Rev. 19, ADAMS Accession No. ML11171A405 (2011).
  • Probabilistic Risk Assessment and Severe Accidents,” Chap. 19, in “GE-Hitachi ESBWR Design Control Document, Part 2 – Tier 2,” Rev. 10, ADAMS Accession No. ML14100A559 (2014).

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:

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:

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.