AFR-100 safety analyses
Creators
- 1. Argonne National Laboratory, Bldg. 208, 9700 South Cass Avenue, Argonne, IL 60439-4842 (United States)
Description
The Advanced Fast Reactor-100 (AFR-100) is Argonne National Laboratory's 250 MWth metal-fueled modular sodium-cooled pool-type fast reactor concept. [1] A series of accident sequences that focused on the AFR-100's ability to provide protection against reactor damage during low probability accident sequences resulting from multiple equipment failures were examined. Protected and Unprotected Loss of Flow (PLOF and ULOF) and Unprotected Transient Over-Power (UTOP) accidents were simulated using the SAS4A/SASSYS-1 safety analysis code. The large heat capacity of the sodium in the pool-type reactor allows the AFR-100 to absorb large amounts of energy during a PLOF with relatively small temperature increases throughout the system. During a ULOF with a 25-second flow halving time, coolant and cladding temperatures peak around 720 deg. C within the first minute before reactivity feedback effects decrease power to match the flow. Core radial expansion and fuel Doppler provide the necessary feedback during the UTOP to bring the system back to critical before system temperatures exceed allowable limits. Simulation results indicate that adequate ULOF safety margins exist for the AFR-100 design with flow halving times of twenty-five seconds. Significant safety margins are maintained for PLOF accidents as well as UTOP accidents if a rod stop is used. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 978-0-89448-091-1
- Imprint Title
- Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12
- Imprint Pagination
- 2799 p.
- Journal Page Range
- p. 1007-1016
Conference
- Title
- 2012 International Congress on Advances in Nuclear Power Plants
- Acronym
- ICAPP '12
- Dates
- 24-28 Jun 2012
- Place
- Chicago, IL (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 44063849
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; DAMAGE; FAILURES; FAST REACTORS; LOSS OF FLOW; POOL TYPE REACTORS; PROBABILITY; REACTIVITY COEFFICIENTS; SAFETY ANALYSIS; SAFETY MARGINS; SODIUM COOLED REACTORS; SPECIFIC HEAT; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; EPITHERMAL REACTORS; LIQUID METAL COOLED REACTORS; PHYSICAL PROPERTIES; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs.