Conceptual Design of a Clinical BNCT Beam in an Adjacent Dry Cell of the Jožef Stefan Institute TRIGA Reactor

The MCNP4B Monte Carlo transport code is used in a feasibility study of the epithermal neutron boron neutron capture therapy facility in the thermalizing column of the 250-kW TRIGA Mark II reactor at the Jožef Stefan Institute (JSI). To boost the epithermal neutron flux at the reference irradiation...

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Bibliographic Details
Published in:Nuclear technology 2000-11, Vol.132 (2), p.179-195
Main Author: MAUCEC, Marko
Format: Article
Language:English
Subjects:
ALUMINIUM FLUORIDES
ALUMINIUM OXIDES
BEAMS
Biological and medical sciences
DESIGN
ENRICHED URANIUM
EPITHERMAL NEUTRONS
FAST NEUTRONS
FEASIBILITY STUDIES
FUEL ELEMENTS
IRRADIATION
LEAD FLUORIDES
Medical sciences
MONTE CARLO METHOD
NEUTRON CAPTURE THERAPY
PATIENTS
Radiotherapy. Instrumental treatment. Physiotherapy. Reeducation. Rehabilitation, orthophony, crenotherapy. Diet therapy and various other treatments (general aspects)
REACTOR CORES
SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
Technology. Biomaterials. Equipments. Material. Instrumentation
THERMAL COLUMNS
TRIGA-2 REACTOR
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Summary:The MCNP4B Monte Carlo transport code is used in a feasibility study of the epithermal neutron boron neutron capture therapy facility in the thermalizing column of the 250-kW TRIGA Mark II reactor at the Jožef Stefan Institute (JSI). To boost the epithermal neutron flux at the reference irradiation point, the efficiency of a fission plate with almost 1.5 kg of 20% enriched uranium and 2.3 kW of thermal power is investigated. With the same purpose in mind, the TRIGA reactor core setup is optimized, and standard fresh fuel elements are concentrated partly in the outermost ring of the core. Further, a detailed parametric study of the materials and dimensions for all the relevant parts of the irradiation facility is carried out. Some of the standard epithermal neutron filter/moderator materials, as well as "pressed-only" low-density Al 2 O 3 and AlF 3 , are considered. The proposed version of the BNCT facility, with PbF 2 as the epithermal neutron filter/moderator, provides an epithermal neutron flux of ~1.1 × 10 9 n/cm 2 ·s, thus enabling patient irradiation times of
ISSN:0029-5450
1943-7471
DOI:10.13182/NT00-A3137