Characterisation of the IRSN graphite moderated Americium-Beryllium neutron field

Radiation Protection Dosimetry

Volumn 110, Issue 1-4, 2004, Pages 135-139

  Lacoste, Veronique ^a   Gressier, V ^a   Muller, H ^a   Lebreton, L ^a  

^a INSTITUT DE RADIOPROTECTION ET DE SÛRETÉ NUCLÉAIRE IRSN   (France)

Author keywords

[No Author keywords available]

Indexed keywords

AMERICIUM; BERYLLIUM; GOLD; GRAPHITE;

ARTICLE; CALCULATION; CALIBRATION; CONTROLLED STUDY; FAST NEUTRON RADIATION; INTERMETHOD COMPARISON; MONTE CARLO METHOD; NEUTRON DOSIMETRY; NEUTRON RADIATION; NEUTRON SCATTERING; PROTON RADIATION; RADIATION DOSE DISTRIBUTION; RADIATION ENERGY; RADIATION FIELD; SPECTROMETRY;

ALGORITHMS; AMERICIUM; BERYLLIUM; BODY BURDEN; CALIBRATION; COMPUTER SIMULATION; COMPUTER-AIDED DESIGN; EQUIPMENT FAILURE ANALYSIS; FRANCE; GRAPHITE; INTERNATIONALITY; MODELS, STATISTICAL; MONTE CARLO METHOD; NEUTRONS; NUCLEAR REACTORS; OCCUPATIONAL EXPOSURE; PHOTONS; RADIATION DOSAGE; RADIATION PROTECTION; RADIOISOTOPES; RADIOMETRY; REFERENCE STANDARDS; RELATIVE BIOLOGICAL EFFECTIVENESS; REPRODUCIBILITY OF RESULTS; SCATTERING, RADIATION; SENSITIVITY AND SPECIFICITY;

EID: 4644370195     PISSN: 01448420     EISSN: None     Source Type: Journal    
DOI: 10.1093/rpd/nch188     Document Type: Article

References (14)

1. International Organization for Standardization. Reference neutron radiations - Part 1: characteristics and methods of production. ISO 8529-1 (General: ISO) (2001).
2. Briesmeister, J. F. Ed. MCNP™ - A general Monte Carlo N-particle transport code, Version 4C. Report LA-13709-M (Los Alamos National Laboratory, Los Alamos, NM) (2000).
3. Lacoste, V., Gressier, V. and Muller, H. MCNP4C simulation of the thermal neutron radiation field at the IRSN SIGMA facility. Report IRSN/DPHD/SDOS/2003-11 (2003).
4. NUMEC Americium Data Sheet, Nuclear Materials and Equipment Corporation, Technical Data Sheet, Apollo, Pennsylvania (1967).
5. International Commission on Radiation Units and Measurements. Conversion coefficients for use in radiological protection against external radiation. ICRU Report 57 (Bethesda, MD: ICRU) (1998).
6. Westcott, C. H., Walker, W. H. and Alexander, T. K. Effective cross sections and cadmium ratios for the neutron spectra of thermal reactors. In: Proceedings of the Second International Conference on the Peaceful Uses of Atomic Energy, Geneva, Report A/Conf. 15/P/202. (New York: United Nations) 1958.
7. Ryves, T. B. and Paul, E. B. The construction and calibration of a standard thermal neutron flux facility at the National Physical Laboratory. J. Nucl. Energy 22(12), 759-775 (1968).
8. Geiger, K. W. and Van Der Zwan, L. Slowing down spectra and neutron temperature in a thermal neutron flux density standard. Metrologia 2(1), 1-5 (1966).
9. Gressier, V., Lacoste, V., Lebreton, L. and Muller, H. Experimental determination of the neutron radiation field at the SIGMA facility. Report IRSN/DPHD/SDOS/2003-12 (2003).
10. Matzke, M. Unfolding of pulse height spectra: the HEPRO program system. Report PTB-N-19 (1994).
11. Tomás, M., Fernández, F., Bakali, M. and Muller, H. MITOM: a new unfolding code based on a spectra model method applied to neutron spectrometry. Radiat. Prot. Dosim. 110(1-4), 545-548 (2004).
12. Lacoste, V., Gressier, V., Pochat, J. L., Fernández, F., Bakali, M. and Bouassoule, T. Characterisation of Bonner sphere systems at monoenergetic and thermal neutron fileds. Radiat. Prot. Dosim. 110(1-4), 529-532 (2004).
13. Pichenot, G. Characterisation of spherical recoil proton proportional counters used for neutron spectrometry. Nucl. Instrum Meth. A 476, 165-169 (2002).
14. Scott, M. C., Bennet, J. W. and Petler, J. S. Neutron spectrum studies in phantoms ftom 30 keV to 14 MeV. In: Fourth symposium on Neutron Dosimetry, Munich-Neuherberg, Germany, 2, pp. 167-180 (1981).