Assessment of the Technical Maturity of Generation IV Concepts for Test or Demonstration Reactor Applications, Revision 2
- 1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Description
The United States Department of Energy (DOE) commissioned a study the suitability of different advanced reactor concepts to support materials irradiations (i.e. a test reactor) or to demonstrate an advanced power plant/fuel cycle concept (demonstration reactor). As part of the study, an assessment of the technical maturity of the individual concepts was undertaken to see which, if any, can support near-term deployment. A Working Group composed of the authors of this document performed the maturity assessment using the Technical Readiness Levels as defined in DOE's Technology Readiness Guide . One representative design was selected for assessment from of each of the six Generation-IV reactor types: gas-cooled fast reactor (GFR), lead-cooled fast reactor (LFR), molten salt reactor (MSR), supercritical water-cooled reactor (SCWR), sodium-cooled fast reactor (SFR), and very high temperature reactor (VHTR). Background information was obtained from previous detailed evaluations such as the Generation-IV Roadmap but other technical references were also used including consultations with concept proponents and subject matter experts. Outside of Generation IV activity in which the US is a party, non-U.S. experience or data sources were generally not factored into the evaluations as one cannot assume that this data is easily available or of sufficient quality to be used for licensing a US facility. The Working Group established the scope of the assessment (which systems and subsystems needed to be considered), adapted a specific technology readiness scale, and scored each system through discussions designed to achieve internal consistency across concepts. In general, the Working Group sought to determine which of the reactor options have sufficient maturity to serve either the test or demonstration reactor missions.
Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 33 p.
- Report number
- INL/EXT--15-36427
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 47046053
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- DESIGN; EVALUATION; FAST REACTORS; FEASIBILITY STUDIES; GAS COOLED REACTORS; HTGR TYPE REACTORS; IRRADIATION REACTORS; LEAD; LIQUID METAL COOLED REACTORS; MOLTEN SALT REACTORS; SODIUM COOLED REACTORS; TEMPERATURE RANGE 1000-4000 K; TEST REACTORS; WATER COOLED REACTORS
- Descriptors DEC
- ELEMENTS; EPITHERMAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; LIQUID METAL COOLED REACTORS; METALS; REACTORS; RESEARCH AND TEST REACTORS; TEMPERATURE RANGE; TEST FACILITIES
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE Office of Nuclear Energy (United States)
- Secondary number(s)
- OSTIID--1236803