HRB-22 preirradiation thermal analysis
Description
This report describes the preirradiation thermal analysis of the HRB-22 capsule designed for irradiation in the removable beryllium (RB) position of the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). CACA-2 a heavy isotope and fission product concentration calculational code for experimental irradiation capsules was used to determine time dependent fission power for the fuel compacts. The Heat Engineering and Transfer in Nine Geometries (HEATING) computer code, version 7.2, was used to solve the steady-state heat conduction problem. The diameters of the graphite fuel body that contains the compacts and the primary pressure vessel were selected such that the requirements of running the compacts at an average temperature of < 1,250 C and not exceeding a maximum fuel temperature of 1,350 C was met throughout the four cycles of irradiation
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE95013507; NTIS; US Govt. Printing Office Dep.Files
26074025.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 43 p.
- Report number
- ORNL/M--3563
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26074025
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- C CODES; DESIGN; GRAPHITE; H CODES; HFIR REACTOR; HTTR REACTOR; IRRADIATION CAPSULES; NUCLEAR FUELS; PERFORMANCE; PROBABILISTIC ESTIMATION; THEORETICAL DATA; THERMAL ANALYSIS; THERMAL CONDUCTIVITY; THERMAL EXPANSION
- Descriptors DEC
- CARBON; COMPUTER CODES; DATA; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPANSION; EXPERIMENTAL REACTORS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; INFORMATION; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; NONMETALS; NUMERICAL DATA; PHYSICAL PROPERTIES; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Funding organization
- USDOE, Washington, DC (United States).