Thermal Hydraulic Challenges of Gas Cooled Fast Reactors with Passive Safety Features
Description
Transient response of a Gas cooled Fast Reactor (GFR) coupled to a recompression supercritical CO2 (S-CO2) power conversion system (PCS) in a direct cycle to Loss of Coolant and Loss of Generator Load Accidents is analyzed using RELAP5-3D. A number of thermal hydraulic challenges for GFR design are pointed out as the designers strive to accommodate cooling of the high power density core of a fast reactor by a gas with its inherently low heat transfer capability, in particular under post LOCA events when system pressure is lost and when reliance on passive decay heat removal is emphasized. Although it is possible to design a S-CO2 cooled GFR that can survive LOCA by cooling the core through natural circulating loops between the core and elevated emergency cooling heat exchangers, it is not an attractive approach because of various bypass paths that can, depending on break location, degrade core cooling. Moreover, natural circulation gas loops can operate in deteriorated heat transfer regimes with substantial reduction of heat transfer coefficient: as low as 30% of forced convection values, and data and correlations in these regimes carry large uncertainties. Therefore, reliable battery powered blowers for post-LOCA decay heat removal (DHR) that provide flow in well defined regimes with low uncertainty, and can be easily over-designed to accommodate bypass flows were selected. The results confirm that a GFR with such a DHR system and negative coolant void worth can withstand LOCA with and without scram as well as loss of electrical load without exceeding core temperature and turbomachinery overspeed limits
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 239
- Journal Issue
- 5
- Journal Page Range
- p. 840-854
- ISSN
- 0029-5493
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- United States
- INIS RN
- 40073106
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCIDENTS; AFTER-HEAT REMOVAL; BLOWERS; COOLANTS; DESIGN; FAST REACTORS; FORCED CONVECTION; HEAT EXCHANGERS; HEAT TRANSFER; LOSS OF COOLANT; NATURAL CONVECTION; POWER DENSITY; SAFETY; SCRAM; THERMAL HYDRAULICS; TRANSIENTS; TURBOMACHINERY
- Descriptors DEC
- ACCIDENTS; CONVECTION; ENERGY TRANSFER; EPITHERMAL REACTORS; EQUIPMENT; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MACHINERY; MASS TRANSFER; MECHANICS; REACTOR ACCIDENTS; REACTOR SHUTDOWN; REACTORS; REMOVAL; SHUTDOWN
Optional Information
- Contract/Grant/Project number
- AC07-99ID-13727
- Notes
- doi 10.1016/j.nucengdes.2008.10.023
- Secondary number(s)
- INL/JOU--08-13795