Gas turbine module helium reactor (GT-MHR). A multipurpose passively safe next generation reactor
Creators
- 1. General Atomics, San Diego, California (United States)
Description
The Gas Turbine-Modular Helium Reactor (GT-MHR) is the result of coupling a small passively safe reactor with key technology developments in the U.S. during the last decade: large industrial gas turbines; large active magnetic bearings; and compact, highly effective plate-fin heat exchangers. The GT-MHR provides a step increase in economic performance combined with increased safety. This is accomplished through its unique capability to utilize the Brayton cycle to produce electricity directly with the high temperature helium primary coolant from the reactor driving the gas turbine electrical generator. It retains the high levels of passive safety and the standardized modular design of the steam cycle MHR, while showing promise for a significant reduction in power generating costs by increasing plant net efficiency to a remarkable 47%. The resulting GT-MHR plant also provides and advanced, multipurpose highly efficient, cost effective system with unparalleled safety characteristics for the effective destruction and/or degradation of weapons-grade plutonium. Fueled with either weapons-grade plutonium, plutonium from discharged LWR fuel, high-enriched or low-enriched uranium, the plant can produce more electrical power from a given quantity of fuel than other reactor types and with less thermal discharge. For dispositioning weapons-grade plutonium, the electric revenues available to offset costs are almost 50% greater per unit of plutonium destroyed than for other fission options. The GT-MHR multipurpose plant provides a practical near-term solution for the disposition of surplus weapons-grade plutonium with distinct advantages over other options. The GT-MHR destroys a substantially higher fraction of the plutonium than other reactors using a simple once-through cycle; the discharged product is more diversion resistant than the LWR 'spent fuel' and vitrification options; the residual plutonium is significantly more degraded than the 'spent fuel' option and unattractive for weapon use; and the discharged fuel elements are in suitable form for disposal without the need for reprocessing. The GT-MHR is truly a multipurpose passively safe next generation reactor. (author)
Additional details
Publishing Information
- Imprint Title
- ICONE-3: Proceedings of the 3rd JSME/ASME joint international conference on nuclear engineering. Volume 2
- Imprint Pagination
- 512 p.
- Journal Page Range
- p. 751-759
Conference
- Title
- 3. JSME/ASME joint international conference on nuclear engineering
- Acronym
- ICONE-3
- Dates
- 23-27 Apr 1995
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 38019046
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BRAYTON CYCLE; COATED FUEL PARTICLES; ECONOMICS; GAS TURBINES; GRAPHITE; HEAT EXCHANGERS; HELIUM; HTGR TYPE REACTORS; MAGNETIC BEARINGS; MODULAR STRUCTURES; POWER GENERATION; THERMAL EFFICIENCY
- Descriptors DEC
- BEARINGS; CARBON; EFFICIENCY; ELEMENTS; EQUIPMENT; FLUIDS; FUEL PARTICLES; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; MACHINERY; MINERALS; NONMETALS; RARE GASES; REACTORS; THERMODYNAMIC CYCLES; TURBINES; TURBOMACHINERY
Optional Information
- Notes
- 9 refs., 8 figs., 6 tabs.