Characterization of dosimetry of the BMRR horizontal thimble tubes and broad beam facility
Creators
- Hu, J.-P.1
- Reciniello, R.N.1
- Holden, N. E.1
- European Commission, Joint Research Centre, Institute for Energy, Westerduinweg 3, 1755 LE, Petten (Netherlands)
- European Working Group on Reactor Dosimetry - EWGRD (European Commission (EC))
- ASTM Committee E1O on Nuclear Technology and Applications, ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA, 19428-2959 (United States)
- 1. Brookhaven National Laboratory, Upton, NY 11973-5000 (United States)
Description
The Brookhaven Medical Research Reactor was a 5 mega-watt, light-water cooled and heavy graphite moderated research facility. It has two shutter-equipped treatment rooms, three horizontally extended thimble tubes, and an ex-core broad beam facility. The three experimental thimbles, or activation ports, external to the reactor tank were designed for several uses, including the investigations on diagnostic and therapeutic methods using radioactive isotopes of very short half-life, the analysis of radiation exposure on tissue equivalent materials using a collimated neutron beam, and the evaluation of dose effects on biological cells to improve medical treatment. At the broad beam facility where the distribution of thermal neutrons was essential uniform, a wide variety of mammalian whole-body exposures were studied using animals such as burros or mice. Also studied at the broad beam were whole-body phantom experiments, involving the use of a neutron or photon beam streaming through a screen to obtain the flux spectrum suitable for dose analysis on the sugar urea-water mixture, a tissue-equivalent material. Calculations of the flux and the dose at beam ports based on Monte Carlo particle-transport code were performed, and measurements conducted at the same tally locations were made using bare or cadmium-covered gold foils. Analytical results, which show good agreement with measurement data, are presented in the paper. (author)
Availability note (English)
Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addressesAdditional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- INIS-XE-ISRD--13
Conference
- Title
- 13. International Symposium on Reactor Dosimetry
- Acronym
- ISRD-13
- Dates
- 25-29 May 2008
- Place
- Akersloot (Netherlands)
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- France
- INIS RN
- 54030176
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CADMIUM; DOSIMETRY; FOILS; GOLD; GRAPHITE; MONTE CARLO METHOD; MRR REACTOR; NEUTRON BEAMS; PHOTON BEAMS; RADIATION DOSES; RADIATION TRANSPORT; RADIOISOTOPES; REACTOR DESIGN; SPECTRA; THERMAL NEUTRONS; TISSUE-EQUIVALENT MATERIALS
- Descriptors DEC
- BARYONS; BEAMS; CALCULATION METHODS; CARBON; DESIGN; DOSES; ELEMENTARY PARTICLES; ELEMENTS; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; ISOTOPES; MATERIALS; METALS; MINERALS; NEUTRONS; NONMETALS; NUCLEON BEAMS; NUCLEONS; PARTICLE BEAMS; REACTOR LIFE CYCLE; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs.