Inherent safety evaluation of a long-life fast reactor (SALUS-100) under unprotected loss of heat sink conditions
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The Korea Atomic Energy Research Institute (KAERI) is developing the long-life sodium-cooled fast reactor SALUS-100, designed for continuous 20-year operation without refueling. The concept adapts the proven technology of the Prototype Generation-IV SFR (PGSFR) to a non-light-water small modular reactor platform. To verify that these inherited technologies still provide the intrinsic sodium-cooled fast reactors (SFR) safety features—negative reactivity feedback and passive decay-heat removal via the diverse residual heat-removal system (DRHRS)—an unprotected loss-of-heat-sink (ULOHS) analysis was performed. The transient calculations employed GAMMA+ 2.0, a system code validated against data from JOYO, PFBR, Monju, EBR-II, FFTF and other SFR facilities. A concurrent station blackout was assumed to challenge the passive cooling path, and separate cases examined the loss of one versus two intermediate-loop pumps. During the ULOHS event, a rise in core-inlet temperature triggered dominant negative reactivity through the Doppler effect and radial core expansion, stabilizing the reactor. With a single IHTS pump trip, − 0.0207 $ of reactivity was inserted at 213 s, fixing power at 73 % of nominal. When both IHTS pumps tripped, − 0.0501 $ occurred at 216 s, stabilizing power at 42.6 %. The magnitude of the initial power excursion scaled with the inlettemperature spike, highlighting the influence of rapid temperature changes on early transients. Sensitivity studies also quantified the impact of intermediate heat-transport system (IHTS) pump coast-down characteristics and timing of operator actions.
Abstract
The Korea Atomic Energy Research Institute (KAERI) is developing the long-life sodium-cooled fast reactor SALUS-100, designed for continuous 20-year operation without refueling. The concept adapts the proven technology of the Prototype Generation-IV SFR (PGSFR) to a non-light-water small modular reactor platform. To verify that these inherited technologies still provide the intrinsic sodium-cooled fast reactors (SFR) safety features—negative reactivity feedback and passive decay-heat removal via the diverse residual heat-removal system (DRHRS)—an unprotected loss-of-heat-sink (ULOHS) analysis was performed. The transient calculations employed GAMMA+ 2.0, a system code validated against data from JOYO, PFBR, Monju, EBR-II, FFTF and other SFR facilities. A concurrent station blackout was assumed to challenge the passive cooling path, and separate cases examined the loss of one versus two intermediate-loop pumps. During the ULOHS event, a rise in core-inlet temperature triggered dominant negative reactivity through the Doppler effect and radial core expansion, stabilizing the reactor. With a single IHTS pump trip, − 0.0207 $ of reactivity was inserted at 213 s, fixing power at 73 % of nominal. When both IHTS pumps tripped, − 0.0501 $ occurred at 216 s, stabilizing power at 42.6 %. The magnitude of the initial power excursion scaled with the inlettemperature spike, highlighting the influence of rapid temperature changes on early transients. Sensitivity studies also quantified the impact of intermediate heat-transport system (IHTS) pump coast-down characteristics and timing of operator actions.