Simulation of the neutron flux in the irradiation facility at RA-3 reactor

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A facility for the irradiation of a section of patients' explanted liver and lung was constructed at RA-3 reactor, Comisión Nacional de Energía Atómica, Argentina. The facility, located in the thermal column, is characterized by the possibility to insert and extract samples without the need to...

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Autor principal: Bortolussi, S.
Otros Autores: Pinto, J.M, Thorp, S.I, Farias, R.O, Soto, M.S, Sztejnberg, M., Pozzi, E.C.C, Gonzalez, S.J, Gadan, M.A, Bellino, A.N, Quintana, J., Altieri, S., Miller, M.
Formato: Capítulo de libro
Lenguaje:Inglés
Publicado: 2011
Materias:
MICA
ARGENTINA
Acceso en línea:Registro en Scopus
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100 1 |a Bortolussi, S. 
245 1 0 |a Simulation of the neutron flux in the irradiation facility at RA-3 reactor 
260 |c 2011 
270 1 0 |m Bortolussi, S.; Department of Nuclear and Theoretical Physics, University of Pavia, Via Bassi 6 27100, Pavia, Italy; email: silva.bortolussi@pv.infn.it 
506 |2 openaire  |e Política editorial 
504 |a Miller, M., Quintana, J., Ojeda, J., Langan, S., Thorp, S., Pozzi, E., Sztejnberg, M., Graiño, F., New irradiation facility for biomedical applications at the RA-3 reactor thermal column. (2008), pp. 379-382. , In: Proceedings of the 13th ICNCT; Miller, M.E., Mariani, L.E., Sztejnberg Gonçalves Carralves, M.L., Skumanic, M., Thorp, S.I., Implantable self-powered detector for on-line determination of neutron flux in patients during NCT treatment (2004) Appl. Radiat. Isot., 61 (5), pp. 1033-1037 
504 |a Soto, M.S., González, S.J., Thorp, S.I., Pozzi, E.C.C., Farías, R.O., Gadan, M.A., Miller, M.E., Characterization and optimization of the RA-3 preliminary dosimetry for the radiotolerance study of the normal sheep lung. (2009), In: Proceedings of the Young Researchers Boron Neutron Capture Therapy Meeting, Mainz, Germany; (2005), 1-2. , X-5 Monte Carlo Team, MCNP-a general Monte Carlo N-Particle transport code, version 5, LA-UR-031987, LA-CP-03-0245, and LA-CP-03-0284, Los Alamos National Laboratory, New Mexico, USA; Zonta, A., Pinelli, T., Prati, U., Roveda, L., Ferrari, C., Clerici, A.M., Zonta, C., Fossati, F., Extra-corporeal liver BNCT for the treatment of diffuse metastases: what was learned and what is still to be learned (2009) Appl. Radiat. Isot., 67, pp. 67-70 
520 3 |a A facility for the irradiation of a section of patients' explanted liver and lung was constructed at RA-3 reactor, Comisión Nacional de Energía Atómica, Argentina. The facility, located in the thermal column, is characterized by the possibility to insert and extract samples without the need to shutdown the reactor. In order to reach the best levels of security and efficacy of the treatment, it is necessary to perform an accurate dosimetry. The possibility to simulate neutron flux and absorbed dose in the explanted organs, together with the experimental dosimetry, allows setting more precise and effective treatment plans. To this end, a computational model of the entire reactor was set-up, and the simulations were validated with the experimental measurements performed in the facility. © 2011 Elsevier Ltd.  |l eng 
593 |a Department of Nuclear and Theoretical Physics, University of Pavia, Via Bassi 6 27100, Pavia, Italy 
593 |a National Institute of Nuclear Physics (INFN), Section of Pavia, Via Bassi 6 27100, Pavia, Italy 
593 |a Department of Instrumentations and Control, Comisión Nacional de Energía Atómica (CNEA), Presbítero Luis González y Aragon 15 (B1802AYA), Buenos Aires, Argentina 
593 |a Department of Research and Production Reactors, Comisión Nacional de Energía Atómica (CNEA), Av. del Libertador 8250 (1429), Buenos Aires, Argentina 
593 |a Department of Radiobiology, Comisión Nacional de Energía Atómica (CNEA), Av. del Libertador 8250 (1429), Buenos Aires, Argentina 
593 |a CONICET, Avda. Rivadavia 1917, (1033) C.A.B.A., Argentina 
593 |a FCEyN, Universidad de Buenos Aires (1428), Cdad. Universitaria. C.A.B.A., Argentina 
690 1 0 |a BNCT 
690 1 0 |a IRRADIATION FACILITY SIMULATION 
690 1 0 |a NEUTRON DOSIMETRY 
690 1 0 |a ABSORBED DOSE 
690 1 0 |a BNCT 
690 1 0 |a COMPUTATIONAL MODEL 
690 1 0 |a EXPERIMENTAL MEASUREMENTS 
690 1 0 |a IRRADIATION FACILITIES 
690 1 0 |a IRRADIATION FACILITY SIMULATION 
690 1 0 |a NEUTRON DOSIMETRY 
690 1 0 |a THERMAL COLUMN 
690 1 0 |a TREATMENT PLANS 
690 1 0 |a COMPUTER SIMULATION 
690 1 0 |a DOSIMETRY 
690 1 0 |a EXTRACTION 
690 1 0 |a NEUTRON BEAMS 
690 1 0 |a NEUTRON FLUX 
690 1 0 |a PLANT SHUTDOWNS 
690 1 0 |a NEUTRON IRRADIATION 
690 1 0 |a ARTICLE 
690 1 0 |a CONTROLLED STUDY 
690 1 0 |a MATHEMATICAL ANALYSIS 
690 1 0 |a MONTE CARLO METHOD 
690 1 0 |a NEUTRON CAPTURE THERAPY 
690 1 0 |a NEUTRON DOSIMETRY 
690 1 0 |a NEUTRON RADIATION 
690 1 0 |a PHANTOM 
690 1 0 |a PRIORITY JOURNAL 
690 1 0 |a RADIATION DOSE 
690 1 0 |a REACTOR 
690 1 0 |a SIMULATION 
690 1 0 |a TREATMENT PLANNING 
651 4 |a ARGENTINA 
650 1 7 |2 spines  |a MICA 
700 1 |a Pinto, J.M. 
700 1 |a Thorp, S.I. 
700 1 |a Farias, R.O. 
700 1 |a Soto, M.S. 
700 1 |a Sztejnberg, M. 
700 1 |a Pozzi, E.C.C. 
700 1 |a Gonzalez, S.J. 
700 1 |a Gadan, M.A. 
700 1 |a Bellino, A.N. 
700 1 |a Quintana, J. 
700 1 |a Altieri, S. 
700 1 |a Miller, M. 
773 0 |d 2011  |g v. 69  |h pp. 1924-1927  |k n. 12  |p Appl. Radiat. Isot.  |x 09698043  |w (AR-BaUEN)CENRE-3781  |t Applied Radiation and Isotopes 
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