Sensitivity of SC-HTGR Conduction Cooldown to Reactor Cavity Cooling System Failure-Reference-Cited by-同舟云学术

Sensitivity of SC-HTGR Conduction Cooldown to Reactor Cavity Cooling System Failure

Published:2021-10-13 Issue: Volume: Page:1-13
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Mays Brian¹^ORCID,Lommers Lewis²,Yoder Stacy³,Shahrokhi Farshid¹^ORCID

Affiliation:

1. Framatome Inc., 3315 Old Forest Road, Lynchburg, Virginia 24501

2. Framatome Inc., 2101 Horn Rapids Road, Richland, Washington 99354

3. Framatome Inc., 155 Mill Ridge Road, Lynchburg, Virginia 24502

Funder

Framatome Internal Advanced Reactor R&D

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2021.1947664

Reference15 articles.

1. J. C. CLEVELAND and S. R. GREENE, “Application of THERMIX-KONVEK Code to Accident Analyses of Modular Pebble Bed High Temperature Reactors (HTRs),” ORNL/TM-9905, Oak Ridge National Laboratory (1986).

2. “Heat Transport and Afterheat Removal for Gas Cooled Reactors Under Accident Conditions,” IAEA-TECDOC-1163, International Atomic Energy Agency (2001).

3. Sensitivity studies of modular high-temperature gas-cooled reactor postulated accidents

4. Gas-cooled reactor thermal hydraulic analyses with MELCOR

5. “Preliminary Safety Information Document (PSID) for the Standard MHTGR,” DOE-HTGR-86-024, U.S. Department of Energy (1992).

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