Followup calculations for the UVAR LEU conversion
- 1. Department of Mechanical, Aerospace and Nuclear Engineering University of Virginia, Charlottesville, VA (United States)
Description
The UVAR reactor was successfully converted to LEU fuel in April 1994. Void coefficient measurements were made on the 4- by-4 fully-graphite-reflected LEU-1 core configuration, and an isothermal temperature coefficient measurement was made on the operational 4-by-5 partially-graphite-reflected LEU-2 core configuration. Both of these experiments have now been modeled in their critical configurations using the 3DBUM code. The LEU cores were also modeled using the Monte Carlo code MCNP in order to obtain a neutron/gamma source for BNCT filter design calculations. Advanced BNCT filters have been evaluated using both MCNP and the discrete ordinates code DORT. The results indicate that the UVAR would be an ideal source for the BNCT treatment of brain tumors. (author)
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Additional details
Publishing Information
- Imprint Title
- Reduced Enrichment for Research and Test Reactors. Proceedings of the XVIII international meeting
- Imprint Pagination
- 557 p.
- Journal Page Range
- [12 p.]
- Report number
- INIS-XA-C--005
Conference
- Title
- 18. international meeting on Reduced Enrichment for Research and Test Reactors
- Dates
- 17-21 Sep 1995
- Place
- Paris (France)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35044381
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- D CODES; DISCRETE ORDINATE METHOD; GRAPHITE; M CODES; MONTE CARLO METHOD; NEUTRON CAPTURE THERAPY; NEUTRON REFLECTORS; SLIGHTLY ENRICHED URANIUM; TEMPERATURE COEFFICIENT; UVAR REACTOR; VOID COEFFICIENT
- Descriptors DEC
- ACTINIDES; CALCULATION METHODS; CARBON; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; MATERIALS; MEDICINE; METALS; MINERALS; NEUTRON THERAPY; NONMETALS; NUCLEAR MEDICINE; POOL TYPE REACTORS; RADIOLOGY; RADIOTHERAPY; REACTIVITY COEFFICIENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TEST FACILITIES; TEST REACTORS; THERAPY; THERMAL REACTORS; TRAINING REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs, 8 figs, 4 tabs