Neutron spectra and angular distributions of concrete-moderated neutron calibration fields at JAERI

Radiation Protection Dosimetry

Volumn 110, Issue 1-4, 2004, Pages 81-84

  Yoshizawa, M ^a   Tanimura, Y ^a   Saegusa, J ^a   Nemoto, H ^b   Yoshida, M ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

^b Institute of Radiation Measurements   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

AMERICIUM 241; BERYLLIUM;

ARTICLE; CALCULATION; CONTROLLED STUDY; DEVICE; LIQUID SCINTILLATION COUNTING; NEUTRON; NEUTRON DOSIMETRY; RADIATION FIELD; REFERENCE VALUE; SIMULATION; SPECTROMETER; WORKPLACE;

ALGORITHMS; AMERICIUM; BERYLLIUM; BODY BURDEN; CALIBRATION; COMPUTER SIMULATION; CONSTRUCTION MATERIALS; EQUIPMENT FAILURE ANALYSIS; GUIDELINES; HUMANS; JAPAN; MODELS, CHEMICAL; MONTE CARLO METHOD; NEUTRONS; RADIATION DOSAGE; RADIATION PROTECTION; RADIOISOTOPES; RADIOMETRY; REFERENCE STANDARDS; RELATIVE BIOLOGICAL EFFECTIVENESS; SCATTERING, RADIATION;

EID: 4644329101     PISSN: 01448420     EISSN: None     Source Type: Journal    
DOI: 10.1093/rpd/nch198     Document Type: Article

References (12)

1. International Organization for Standardization (ISO). Reference neutron radiations - Characteristics and methods of production of simulated workplace neutron fields. International Standard ISO 12789 (2000).
2. Ing, H., Clifford, T., McLean, T., Webb, W., Cousins, T. and Dhermain, J. ROSPEC - a simple reliable high resolution neutron spectrometer. Radiat. Prot. Dosim. 70(1-4), 273-278 (1997).
3. McElroy, W. N., Berg, S., Crockett, T. and Hawkins, R. G. A computer-automated iterative method for neutron flux spectra determination by foil activation. AFWL-TR-67-41 I-IV (1967). Air Force Weapons Laboratory.
4. Benjamin, P. W., Kemshall, C. D. and Brickstock, A. The analysis of recoil proton spectra. AWRE-O9/68 (1968). UK Atomic Energy Authority, Atomic Weapons Research Establishment.
5. Johnson, R. H., Wehring, B. W. and Dorning, B. W. Smoothing in the FERDOR method of neutron spectrum unfolding. Trans. Am. Nucl. Soc. 22, 798 (1975).
6. Engle, W. W. Jr. ANISN, A one-dimensional discrete ordinates transport code with anisotropic scattering. K-1693 (Oak Ridge, TN: Oak Ridge National Laboratory) (1967).
7. 3 proportional counter with multi-sphere moderators. HOKEN BUTSURI 22, 445-451 (1987). (In Japanese)
8. Briesmeister, J. F. (Ed.) MCNP - a general Monte Carlo N-Particle transport code, Version 4B. LA-12625-M, Version 4B (Los Alamos, NM: Los Alamos National Laboratory) (1997).
9. Nakagawa, T., et al. Japanese evaluated nuclear data library version 3 revision-2: JENDL-3.2. J. Nucl. Sci. Technol. 32, 1259 (1995).
10. International Organization for Standardization (ISO). Reference neutron radiations - Part 1: Characteristics and methods of production. International Standard ISO 8529-1 (2001).
11. International Atomic Energy Agency. Compendium of neutron spectra and detector responses for radiation protection purposes. Technical Report Series No. 318. IAEA STI/DOC/010/318 (1990).
12. International Commission on Radiological Protection (ICRP). Conversion coefficients for use in radiological protection against external radiation. ICRP Publication 74. Ann. ICRP 27(4), Pergamon Press, London and New York (1997).