Innovative safety features of the modular HTGR
The Modular High Temperature Gas-Cooled Reactor (MHTGR) is an advanced reactor concept under development through a cooperative program involving the US Government, the nuclear industry, and the utilities. Near-term development is focused on electricity generation. The top-level safety requirement is that the plant's operation not disturb the normal day-to-day activities of the public. Quantitatively, this requires that the design meet the US Environmental Protection Agency's Protective Action Guides at the site boundary and hence preclude the need for sheltering or evacuation of the public. To meet these stringent safety requirements and at the same time provide a cost competitive design requires the innovative use of the basic high temperature gas-cooled reactor features of ceramic fuel, helium coolant, and a graphite moderator. The specific fuel composition and core size and configuration have been selected to the use the natural characteristics of these materials to develop significantly higher margins of safety. In this document the innovative safety features of the MHTGR are reviewed by examining the safety response to events challenging the functions relied on to retain radionuclides within the coated fuel particles. A broad range of challenges to core heat removal are examined, including a loss of helium pressure of a simultaneous loss of forced cooling of the core. The challenges to control of heat generation consider not only the failure to insert the reactivity control systems but also the withdrawal of control rods. Finally, challenges to control of chemical attack of the ceramic-coated fuel are considered, including catastrophic failure of the steam generator, which allows water ingress, or failure of the pressure vessels, which allows air ingress. The plant's response to these extreme challenges is not dependent on operator action, and the events considered encompass conceivable operator errors.
- Research Organization:
- General Atomics, San Diego, CA (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC03-89SF17885
- OSTI ID:
- 5759158
- Report Number(s):
- GA-A-20789; CONF-9205125-1; ON: DE92008810
- Resource Relation:
- Conference: 1992 Edison Electric Institute (EEI) engineering and operating computer committee meeting, Denver, CO (United States), 17-20 May 1992
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR SAFETY
CHEMICAL REACTIONS
COATED FUEL PARTICLES
ENGINEERED SAFETY SYSTEMS
FAILURES
FISSION PRODUCT RELEASE
FLUID FLOW
HEAT TRANSFER
HUMAN FACTORS
PRESSURE VESSELS
STEAM GENERATORS
BOILERS
CONTAINERS
ENERGY TRANSFER
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
REACTORS
SAFETY
VAPOR GENERATORS
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
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