Trench reactor: an overview
Creators
- 1. Iowa State Univ., Ames (USA)
Description
Recent fast, sodium-cooled reactor designs reflect new conditions. In nuclear energy these conditions are (a) emphasis on maintainability and operability, (b) design for more transparent safety, and (c) a surplus of uranium and enrichment availability that eases concerns about light water reactor fueling costs. In utility practice the demand is for less capital exposure, short construction time, smaller new unit sizes, and low capital cost. The PRISM, SAFR, and integral fast reactor (IFR) concepts are responses to these conditions. Fast reactors will not soon be deployed commercially, so more radical designs can be considered. The trench reactor is the product of such thinking. Its concepts are intended as contributions to the literature, which may be picked up by one of the existing programs or used in a new experimental project. The trench reactor is a thin-slab, pool-type reactor operated at very low power density and- for sodium-modest temperature. The thin slab is repeated in the sodium tank and the reactor core. The low power density permits a longer than conventional core height and a large-diameter fuel pin. Control is by borated steel slabs that can be lowered between the core and lateral sodium reflector. Shutdown is by semaphore slabs that can be swung into place just outside the control slabs. The paper presents major characteristics of the trench reactor that have been changed since the last report
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 57
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 316-317
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Joint meeting of the European Nuclear Society and the American Nuclear Society.
- Dates
- 30 Oct - 4 Nov 1988.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20085938
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORON; CAPITALIZED COST; CONSTRUCTION; ECONOMICS; ENRICHED URANIUM; FABRICATION; FUEL PINS; HEAT SINKS; LOSS OF COOLANT; LOSS OF FLOW; NEUTRON REFLECTORS; PLANNING; PLUTONIUM; POOL TYPE REACTORS; POWER DENSITY; POWER SYSTEMS; REACTIVITY; REACTOR CONTROL SYSTEMS; REACTOR CORES; REACTOR MAINTENANCE; REACTOR OPERATION; REACTOR SAFETY; REPROCESSING; SODIUM COOLED REACTORS; TRANSIENTS; URANIUM
- Descriptors DEC
- ACCIDENTS; ACTINIDES; CONTROL SYSTEMS; COST; ELEMENTS; FUEL ELEMENTS; ISOTOPE ENRICHED MATERIALS; LIQUID METAL COOLED REACTORS; MAINTENANCE; MATERIALS; METALS; OPERATION; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SEMIMETALS; SEPARATION PROCESSES; TRANSURANIUM ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-881011--.