Analysis of Core Disruptive Accidents in a Small Sodium Fast Reactor
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
Analysis of core disruptive accidents (CDA) starts with liquid fuel interspersed with void spaces left in the core when the sodium coolant is expelled. As temperature rises, the voids are filled with the expanded liquid, thus producing saturated vapor pressure. If the liquid reaches the threshold energy to fill the voids completely, pressure begins to rise rapidly. In this study, the equation of state for the fuel vapor pressure developed recently by Joseph et al.1 was cross-checked and used in this study. A set of core disassembly analyses was subsequently performed for the sodium-voided core of the KALIMER-150 design2 by using the VENUS-II code3 for the various reactivity insertion rate up to 100 $/s , which had been assumed to set the upper-bound design limits of containment systems in early safety studies
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2010 autumn meeting of the KNS
- Dates
- 21-22 Oct 2010
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 42084927
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCIDENTS; CONTAINMENT SYSTEMS; DESIGN; REACTOR CORES; SODIUM COOLED REACTORS; SPACE; VAPOR PRESSURE; VOIDS
- Descriptors DEC
- CONTAINMENT; ENGINEERED SAFETY SYSTEMS; LIQUID METAL COOLED REACTORS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- 5 refs, 2 figs, 1 tab