Comparative Safety Assessment of Upflow Versus Downflow GCFR Core Designs

Technical Report · Mon Sep 01 00:00:00 EDT 1980

DOI:https://doi.org/10.2172/6771881· OSTI ID:6771881

Frank, M. V. ^[1]; Kang, C. S. ^[1]; Reilly, J. T. ^[1]; Wheeler, P. A. ^[1]

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1. General Atomic Co., San Diego, CA (United States)

This report presents a hypothetical core disruptive accident safety assessment and a post-accident fuel containment evaluation which were performed for the upflow versus downflow core design decision for the GCFR. Differences between the upflow and downflow unprotected accident sequences were not significant. However, differences do appear when potential accident mitigation and recriticality prevention design concepts are investigated for the loss of shutdown cooling and flow blockage accidents. An in-vessel molten fuel containment system is preferred over an ex-vessel system for both the upflow and downflow concepts.

• Research Organization: General Atomic Co., San Diego, CA (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AT03-76SF71023
• OSTI ID: 6771881
• Report Number(s): GA-A--15421
• Country of Publication: United States
• Language: English

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