Guideline for Performing Systematic Approach to Evaluate and Qualify Legacy Documents that Support Advanced Reactor Technology Activity

Honma, George¹ 

[1] Idaho National Lab. (INL), Idaho Falls, ID (United States)

关键词: REACTOR LICENSING;    INFORMATION RETRIEVAL;    FFTF REACTOR;    REACTOR TECHNOLOGY;    EVALUATION;    KNOWLEDGE MANAGEMENT;    EBR-2 REACTOR;    GUIDELINES;    SODIUM COOLED REACTORS;    FAST REACTORS;    SOURCE TERMS;    NUCLEAR FUELS Fast Flux Test Facility;    ART;    DOE;    Licensing;    Sodium Advanced Fast Reactor;   

DOI  :  10.2172/1236795
RP-ID  :  INL/EXT--15-35805
PID  :  OSTI ID: 1236795
Others  :  TRN: US1600264

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来源: SciTech Connect

【 摘 要 】

The establishment of a systematic process for the evaluation of historic technology information for use in advanced reactor licensing is described. Efforts are underway to recover and preserve Experimental Breeder Reactor II and Fast Flux Test Facility historical data. These efforts have generally emphasized preserving information from data-acquisition systems and hard-copy reports and entering it into modern electronic formats suitable for data retrieval and examination. The guidance contained in this document has been developed to facilitate consistent and systematic evaluation processes relating to quality attributes of historic technical information (with focus on sodium-cooled fast reactor (SFR) technology) that will be used to eventually support licensing of advanced reactor designs. The historical information may include, but is not limited to, design documents for SFRs, research-and-development (R&D) data and associated documents, test plans and associated protocols, operations and test data, international research data, technical reports, and information associated with past U.S. Nuclear Regulatory Commission (NRC) reviews of SFR designs. The evaluation process is prescribed in terms of SFR technology, but the process can be used to evaluate historical information for any type of advanced reactor technology. An appendix provides a discussion of typical issues that should be considered when evaluating and qualifying historical information for advanced reactor technology fuel and source terms, based on current light water reactor (LWR) requirements and recent experience gained from Next Generation Nuclear Plant (NGNP).