Innovations in the ENHS reactor design and fuel cycle
- 1. Dept. of Nuclear Engineering, Univ. of California, Berkeley, CA (United States)
Description
A number of approaches were explored for improving characteristics of the encapsulated nuclear heat source (ENHS) reactor and its fuel cycle, including: increasing the ENHS module power, power density and the specific power, making the core design insensitive to the actinides composition variation with number of fuel recycling and reducing the positive void coefficient of reactivity. Design innovations examined for power increase include intermediate heat exchanger (IHX) design optimization, riser diameter optimization, introducing a flow partition inside the riser, increasing the cooling time of the LWR discharged TRU, increasing the minor actinides' concentration in the loaded fuel and split-enrichment for power flattening. Another design innovation described utilizes a unique synergism between the use of MA and the design of reduced power ENHS cores. Also described is a radically different ENHS reactor concept that has a solid core from which heat pipes transport the fission power to a coolant circulating around the reflector. Promising features of this design concept include enhanced decay heat removal capability; no positive void reactivity coefficient; no direct contact between the fuel clad and the coolant; a core that is more robust for transportation; higher coolant temperature potentially offering higher energy conversion efficiency and hydrogen production capability. (author)
Additional details
Publishing Information
- Publisher
- Tokyo Inst. of Technology
- Imprint Place
- Tokyo (Japan)
- ISBN
- 978-4-903054-15-5
- Imprint Title
- Innovative nuclear energy systems for sustainable development of the world
- Imprint Pagination
- 727 p.
- Journal Page Range
- p. 129-139
Conference
- Title
- 2. COE-INES international symposium
- Acronym
- INES-2
- Dates
- 26-30 Nov 2006
- Place
- Yokohama, Kanagawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 40008913
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTINIDES; ALLOY NUCLEAR FUELS; BREEDING RATIO; COOLANTS; DESIGN; FAST REACTORS; FUEL CYCLE; HEAT EXCHANGERS; HEAT PIPES; LEAD ALLOYS; NATURAL CONVECTION; REACTOR CORES; THERMAL EFFICIENCY; TRANSURANIUM ELEMENTS; VOID COEFFICIENT
- Descriptors DEC
- ALLOYS; CONVECTION; CONVERSION RATIO; DIMENSIONLESS NUMBERS; EFFICIENCY; ELEMENTS; ENERGY SOURCES; ENERGY TRANSFER; EPITHERMAL REACTORS; FUELS; HEAT TRANSFER; MASS TRANSFER; MATERIALS; METALS; NUCLEAR FUELS; REACTIVITY COEFFICIENTS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SOLID FUELS
Optional Information
- Notes
- 18 refs., 7 figs. Imprint:Also published as Progress in Nuclear Energy (Mar 2008). V.50(2-6)