Determination of neutron flux distribution in an Am-Be irradiator using the MCNP

Applied Radiation and Isotopes

Volumn 59, Issue 4, 2003, Pages 263-266

  Shtejer Diaz, K ^a,b   Zamboni, C B ^b   Zahn, G S ^b   Zevallos Chavez J Y ^c  

^a CENTRO DE APLICACIONES TECNOLÓGICAS Y DESARROLLO NUCLEAR CEADEN   (Cuba)

^b INSTITUTO DE PESQUISAS ENERGÉTICAS E NUCLEARES   (Brazil)

^c UNIVERSITY OF SÃO PAULO   (Brazil)

Author keywords

MCNP; Neutron dose; Neutron flux

Indexed keywords

CODES (SYMBOLS); IRRADIATION; NUCLEAR REACTORS; THERMAL EFFECTS;

IRRADIATORS; NEUTRON FLUX;

NEUTRONS;

AMERICIUM; BERYLLIUM;

ABSORPTION; ARTICLE; CALCULATION; COMPUTER PROGRAM; IRRADIATION; MATERIAL STATE; NEUTRON; NEUTRON RADIATION; NUCLEAR REACTOR; PREDICTION; PRIORITY JOURNAL; QUALITATIVE ANALYSIS; QUANTITATIVE ANALYSIS; TEMPERATURE;

AMERICIUM; BERYLLIUM; BORON NEUTRON CAPTURE THERAPY; COMPUTER SIMULATION; EQUIPMENT DESIGN; EQUIPMENT FAILURE ANALYSIS; ISOTOPE LABELING; MODELS, CHEMICAL; NEUTRONS; RADIATION DOSAGE; RADIOMETRY; RADIOPHARMACEUTICALS; RADIOTHERAPY PLANNING, COMPUTER-ASSISTED; REPRODUCIBILITY OF RESULTS; SENSITIVITY AND SPECIFICITY;

EID: 1542713363     PISSN: 09698043     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0969-8043(03)00167-2     Document Type: Article

References (6)

1. Angioletto, E., 2000. Medidas e Cálculos de Espectro de Nêutrons Emergentes de Dutos em Blindagens. M.Sc. Thesis, IPEN, São Paulo, Brazil.
2. Briesmeister, J.F. (Ed.), 2000. MCNP - a general Monte Carlo N-particle transport Code. Version 4C, LA-13709 M.
3. International Commission on Radiological Protection, 1971. Data for protection against ionizing radiation from external sources: supplement to ICRP publication 15. ICRP-21.
4. International Organization for Standardization, 1989. Neutron reference radiations for calibrating neutron-measuring devices used for radiation protection purposes and for determining their response as a function of neutron energy. ISO 8259.
5. National Council on Radiation Protection and Measurements, 1971. Protection against neutron radiation. NCRP-38.
6. Thonsom M.N. Neutron spectra from Am-α-Be and Ra-α-Be sources. Nucl. Instrum. Meas. 37:1965;305-308.