Proposed Advanced Reactor Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (Reactor) for Sodium-Cooled Fast Reactors and Modular High-Temperature Gas-Cooled Reactors

Technical Report · Wed Mar 01 04:00:00 EST 2017

DOI:https://doi.org/10.2172/1361360· OSTI ID:1361360

Belles, Randy ^[1]; Poore, III, Willis P. ^[1]; Brown, Nicholas R. ^[1]; Flanagan, George F. ^[1]; Holbrook, Mark ^[2]; Moe, Wayne ^[2]; Sofu, Tanju ^[3]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
3. Argonne National Lab. (ANL), Argonne, IL (United States)

This report proposes adaptation of the previous regulatory gap analysis in Chapter 4 (Reactor) of NUREG 0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition. The proposed adaptation would result in a Chapter 4 review plan applicable to certain advanced reactors. This report addresses two technologies: the sodium-cooled fast reactor (SFR) and the modular high temperature gas-cooled reactor (mHTGR). SRP Chapter 4, which addresses reactor components, was selected for adaptation because of the possible significant differences in advanced non-light water reactor (non-LWR) technologies compared with the current LWR-based description in Chapter 4. SFR and mHTGR technologies were chosen for this gap analysis because of their diverse designs and the availability of significant historical design detail.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-00OR22725
• OSTI ID: 1361360
• Report Number(s): ORNL/TM--2017/151; RC0420000; NERC023
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
NUREG-0800
SFR. HTGR
advanced reactors
non-LWR