Reactor physics input to the safety analysis report for the High Flux Isotope Reactor

Technical Report · Sun Mar 01 00:00:00 EST 1992

DOI:https://doi.org/10.2172/5780442· OSTI ID:5780442

Primm, III., R. T.

HFIR specific, few group neutron and coupled neutron-gamma libraries have been prepared. These are based on data from ENDF/B-V and beginning-of-life (BOL) conditions. The neutron library includes actinide data for curium target rods. Six critical experiments, collectively designated HFIR critical experiment 4, were analyzed. Calculated k-effective was 2% high at BOL-typical conditions but was 1.0 at end-of-life-typical conditions. The local power density distributions were calculated for each of the critical experiments. The axially averaged values at a given radius were frequently within experimental error. However at individual points, the calculated local power densities were significantly different from the experimentally derived values (several times greater than experimental uncertainty). A reassessment of the foil activation data with transport theory techniques seems desirable. Using the results of the critical experiments study, a model of current HFIR configuration was prepared. As with the critical experiments, BOL k-effective was high (3%). However, end-of-life k-effective was high (2%). The end-of-life concentrations of fission products were compared to those generated using the ORIGEN code. Agreement was generally good through differences in the inventories of some important nuclides, Xe and I, need to be understood. End-of-cycle curium target isotopics based on measured, discharged target rods were compared to calculated values and agreement was good. Axial flux plots at various irradiation positions were generated. Time-dependent power distributions based on two-dimensional calculations were provided.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5780442
• Report Number(s): ORNL/TM-11956; ON: DE92010369
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
HFIR REACTOR
REACTOR PHYSICS
SAFETY ANALYSIS
ACTINIDES
CROSS SECTIONS
FISSION PRODUCTS
IODINE
NUCLEAR DATA COLLECTIONS
POWER DENSITY
POWER DISTRIBUTION
REACTOR KINETICS
SAFETY REPORTS
TRANSPORT THEORY
XENON
ELEMENTS
ENRICHED URANIUM REACTORS
FLUIDS
GASES
HALOGENS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
ISOTOPES
KINETICS
MATERIALS
METALS
NONMETALS
PHYSICS
RADIOACTIVE MATERIALS
RARE GASES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
220100 - Nuclear Reactor Technology- Theory & Calculation