Operating limits for the ultra-high-flux reactor
Description
The need for a neutron-producing source that will provide steady-state fluxes of at least 1.0 x 1016 n/cm2 x s has caused a critical review of thermal-hydraulics limits for plate-type cores. A high-intensity neutron sources will be used in various aspects of material, biological, and fundamental physics research. Because the neutron flux is nearly an order of magnitude larger than present plate-type reactors, the power density for the Ultra-High-Flux Reactor (UHFR) is also an order of magnitude larger. To save costs, the use of existing data and experience with an aluminum plate-type fuel was selected. The UHFR is basically a cylindrical core, double-donut, split axially with each axial section 15.2 cm high and a heavy-water-filled space of 15.2 cm between each section. The core is small, 43 cm o.d. with a volume of ∼ 40 ell and a power density at beginning of life (BOL) of nearly 10 MW/ell. The core thermal hydraulics are summarized. Even though the UHFR will have a much larger neutron flux and hence heat flux over existing facilities, adequate margins still exist in the thermal-hydraulics limits to allow safe operation
Additional details
Publishing Information
- Journal Title
- Trans. Am. Nucl. Soc.
- Journal Volume
- 52
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 495-496
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- American Nuclear Society annual meeting.
- Dates
- 15-20 Jun 1986.
- Place
- Reno, NV (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18066104
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATR REACTOR; CORROSION; CRITICAL HEAT FLUX; FUEL PLATES; HEAT TRANSFER; HYDRAULICS; M CODES; NEUTRON FLUX; REACTOR CORES; REACTOR SAFETY; REACTOR STABILITY; RESEARCH AND TEST REACTORS; SPECIFICATIONS; STEADY-STATE CONDITIONS; TEMPERATURE DEPENDENCE; THERMAL STRESSES; TIME DEPENDENCE
- Descriptors DEC
- CHEMICAL REACTIONS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; HEAT FLUX; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTORS; SAFETY; STABILITY; STRESSES; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-860610--.