Knowledge preservation at the fast flux test facility
Creators
- 1. Pacific Northwest National Laboratory, Richland, Washington (United States)
Description
One of the goals of the Department of Energy's Office of Nuclear Energy, initiated under the Fuel Cycle Research and Development Program (FCRD) and continued under the Advanced Reactor Concepts Program (ARC) is to preserve the knowledge that has been gained in the United States on Liquid Metal Reactors (LMRs) that could support the development of an environmentally and economically sound nuclear fuel cycle. The Fast Flux Test Facility (FFTF) is the most recent LMR to operate in the United States, from 1982 to 1992, and was designed as a fully instrumented test reactor with on-line, real time test control and performance monitoring of components and tests installed in the reactor. The 10 years of operation of the FFTF provided a very useful framework for testing the advances in LMR safety technology based on passive safety features that may be of increased importance to new designs after the events at Fukushima. Knowledge preservation at the FFTF is focused on the areas of design, construction, and startup of the reactor, as well as on preserving information obtained from 10 years of successful operating history and extensive irradiation testing of fuels and materials. In order to ensure protection of information at risk, the program to date has sequestered reports, files, tapes, and drawings to allow for secure retrieval. A disciplined and orderly approach has been developed to respond to client's requests for documents and data in order to minimize the search effort and ensure that future requests for this information can be readily accommodated. (author)
Additional details
Publishing Information
- Imprint Title
- The 10th international conference. GLOBAL 2011. Toward and over the Fukushima Daiichi accident. Proceedings
- Imprint Pagination
- [2136 p.]
- Journal Page Range
- [8 p.]
Conference
- Title
- 10. international conference. Toward and over the Fukushima Daiichi accident
- Acronym
- GLOBAL 2011
- Dates
- 11-16 Dec 2011
- Place
- Chiba (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 44029949
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S96: KNOWLEDGE MANAGEMENT AND PRESERVATION;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BENCHMARKS; DOCUMENTATION; FFTF REACTOR; FUEL CYCLE; INTERNATIONAL COOPERATION; IRRADIATION; KNOWLEDGE PRESERVATION; SAFETY; SIMULATION; VALIDATION
- Descriptors DEC
- COOPERATION; EPITHERMAL REACTORS; FAST REACTORS; KNOWLEDGE MANAGEMENT; LIQUID METAL COOLED REACTORS; MANAGEMENT; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS; TESTING
Optional Information
- Notes
- Available as CD-ROM Data in PDF format, Paper ID: a11_01_500579.pdf; 6 refs., 3 figs., 1 tab.