Published 1969
| Version v1
Report
Fuel Cycles for the HTGR
Creators
- 1. Gulf General Atomic Incorporation (United States)
Description
The High Temperature Gas-Cooled Reactor (HTGR) is particularly suited to accommodate a variety of fuel cycles because of its core characteristics. Specific qualities such as the inherently low neutron losses, the high specific power, the high burnup capabilities and the high thermal efficiency result primarily from the type of fuel element used. Graphite serves as structural material, moderator, and fission product barrier and with its low capture cross section assures a low level of parasitic neutron absorption. The excellent material properties of graphite at elevated temperatures permit high gas outlet temperatures which lead to compact, high-efficiency plants.
Additional details
Publishing Information
- Imprint Title
- Lectures Delivered at the International Survey Course on Technical and Economic Aspects of Nuclear Power. V.1
- Imprint Pagination
- 458 p.
- Journal Page Range
- 27 p.
- Report number
- IAEA--114(v.1)
Conference
- Title
- 2. International Survey Course on Technical and Economic Aspects of Nuclear Power
- Dates
- 1-12 Sep 1969
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 50069284
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CROSS SECTIONS; FISSION PRODUCTS; FUEL CYCLE; FUEL ELEMENTS; GRAPHITE; HTGR TYPE REACTORS; MODERATORS; NEUTRONS; THERMAL EFFICIENCY
- Descriptors DEC
- BARYONS; CARBON; EFFICIENCY; ELEMENTARY PARTICLES; ELEMENTS; FERMIONS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HADRONS; ISOTOPES; MATERIALS; MINERALS; NONMETALS; NUCLEONS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- 4 refs., 5 figs., 5 tabs.