Analysis of epithermal neutron beam experiments at the HIFAR reactor

Journal Article · Sun Jan 01 04:00:00 EST 1995 · Nuclear Technology

OSTI ID:31979

Harrington, B V; Constantine, G ^[1]

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1. Australian Nuclear Science and Technology Organisation, Menai (Australia)

A calculated model of the entire core of the DIDO class reactor HIFAR has been used to analyze epithermal neutron beam experiments. In the experiments, an off-center fuel element was replaced by a dummy fuel element voided by a dry liner in which an aluminium spectrum shifter was suspended at core center to extract the beam. Various combinations of the filter materials aluminum, iron, sulfur, titanium, and cadmium were inserted near the top of the dry liner, and liquid argon was placed in a cryostat above the dummy element. Reaction rates were measured in a fission chamber, sandwiched between various thicknesses of polyethylene, in order to assess the accuracy of the calculational model for different regions of the neutron energy spectrum of the beam. The neutron source distribution of the HIFAR core was obtained from a three-dimensional diffusion calculation, with burnup-dependent fuel compositions and fission products included, using the AUS modular code scheme. Argon cross sections were generated from ENDL-84 data and resonance parameters taken from Neutron Cross Sections (1984). A whole-core MCNP source calculation was used to analyze the experiments giving good agreement between measured and calculated reaction rates. This whole-core model of HIFAR may be applied with confidence to predict the performance of filtered beams for boron neutron capture therapy and also to other HIFAR calculations.

• OSTI ID: 31979
• Journal Information: Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 1 Vol. 109; ISSN 0029-5450; ISSN NUTYBB
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
55 BIOLOGY AND MEDICINE
BASIC STUDIES
BEAM HOLES
COMPUTERIZED SIMULATION
DATA ANALYSIS
ENERGY SPECTRA
HIFAR REACTOR
M CODES
NEUTRON BEAMS
NEUTRON CAPTURE THERAPY
NEUTRON SOURCES
NEUTRON TRANSPORT
NUCLEAR REACTION KINETICS
PERFORMANCE
RADIATION DOSE DISTRIBUTIONS
REACTOR CORES