Relevance of passive safety testing at the fast flux test facility to advanced liquid metal reactors - 5127
Creators
- 1. Pacific Northwest National Laboratory, 902 Battelle Boulevard, P.O. Box 999, MSIN K8-34, Richland, Washington, 99352 (United States)
Description
Significant cost and safety improvements can be realized in advanced liquid metal reactor (LMR) designs by emphasizing inherent or passive safety through crediting the beneficial reactivity feedbacks associated with core and structural movement. This passive safety approach was adopted for the Fast Flux Test Facility (FFTF), and an experimental program was conducted to characterize the structural reactivity feedback. Testing at the Rapsodie and EBR-II reactors had demonstrated the beneficial effect of reactivity feedback caused by changes in fuel temperature and core geometry mechanisms in a liquid metal fast reactor in a holistic sense. The FFTF passive safety testing program was developed to examine how specific design elements influenced dynamic reactivity feedback in response to a reactivity input and to demonstrate the scalability of reactivity feedback results from smaller cores like Rapsodie and EBR-II to reactor cores that were more prototypic in scale to reactors of current interest. The U.S. Department of Energy, Office of Nuclear Energy Advanced Reactor Technology program is in the process of preserving, protecting, securing, and placing in electronic format information and data from the FFTF, including the core configurations and data collected during the passive safety tests. Evaluation of these actual test data could provide insight to improve analytical methods which may be used to support future licensing applications for LMRs. (authors)
Availability note (English)
Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France)Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- ISBN
- 978-1-4951-6286-2
- Imprint Title
- GLOBAL 2015 Proceedings
- Imprint Pagination
- 2455 p.
- Journal Page Range
- p. 448-457
Conference
- Title
- Nuclear fuel cycle for a low-carbon future
- Acronym
- GLOBAL 2015
- Dates
- 21-24 Sep 2015
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 49023704
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FFTF REACTOR; LOSS OF FLOW; REACTIVITY COEFFICIENTS; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS
- Descriptors DEC
- ACCIDENTS; EPITHERMAL REACTORS; FAST REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SIMULATION; SODIUM COOLED REACTORS; TEST FACILITIES; TEST REACTORS
Optional Information
- Notes
- 6 refs.