Experimental and Monte Carlo evaluations of the dosimetric characteristics of a thermal neutron calibration assembly

Radiation Protection Dosimetry

Volumn 85, Issue 1-4, 1999, Pages 79-84

  Vilela, E ^a   Morelli, B ^a   Gualdrini, G ^a   Burn, K W ^a   Monteventi, F ^a  

^a ENEA   (Italy)

Author keywords

[No Author keywords available]

Indexed keywords

LITHIUM FLUORIDE; POLYETHYLENE;

ALGORITHM; ATMOSPHERIC RADIOACTIVITY; CALIBRATION; CONFERENCE PAPER; EVALUATION; NEUTRON DOSIMETRY; NEUTRON RADIATION; RADIATION FIELD; RADIATION PROTECTION; SPECTRUM; STATISTICS; SYSTEM ANALYSIS; THERMAL CONDUCTIVITY; THERMOLUMINESCENCE DOSIMETER;

EID: 0032800884     PISSN: 01448420     EISSN: None     Source Type: Journal    
DOI: 10.1093/oxfordjournals.rpd.a032915     Document Type: Conference Paper

References (10)

1. Bresmeister, J. F. (Ed.) MCNP - A General Monte Carlo N-Particle Transport Code: version 4B. LA-12625 (March 1997).
2. Fantuzzi, E., Gualdrini, G., Monteventi, F., Morelli, B. and Uleri, G. Dosimetri a TL per Neutroni Termici e Gamma impiegati in ENEA: Metodo, Calibrazione e Qualificazione. RT/AMB/ /98 (in press).
3. Morelli, B., Vilela, E. and Fantuzzi, E. Studio dei Parametri di Attacco Chimico di Due Rivelatori di CR39 per Impieghi in Dosimetria Neutronica Personale di Routine. RT/AMB/ /98 (in press).
4. Vilela, E., Morelli, B. and Fantuzzi, E. Dosimetric Performance of the Fast Neutron Personal Dosemeter developed at the Institute for Radiation Protection of ENEA/BO. RT/AMB/ /98 (in press).
5. ICRP. Conversion Coefficients for Use in Radiological Protection Against External Radiation. Publication 74 (Oxford: Elsevier) (1997).
6. International Organization for Standardization. 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 8529 (1989).
7. Scale: A Modular Code System for Performing Standardized Computer Analyses for Licensing Evaluation. NUREG/CR-0200 (Oak Ridge National Laboratory) (1990).
8. Burn, K. W. and Nava, E. Optimization of Variance Reduction Parameters in Monte Carlo Radiation Transport Calculations to a Number of Responses of Interest. In: Proc. Int. Conf. on Nuclear Data for Science and Technology, Trieste, Italy, May 1997 (p. 260) (Italian Physical Society) (1997).
9. Burn, K. W. and Gualdrini, G. Optimizing the Monte Carlo Evaluation of Neutron Spectra within a Thermal Neutron Calibration Assembly. RT ENEA/AMB/ /1998 (to be published).
10. Vilela, E., Morelli, B., Gualdrini, G., Burn, K. W., Monteventi, F. and Fantuzzi, E. Characterizing a Thermal Neutron Calibration Assembly by Solid State, Nuclear Track Dosemeters and Monte Carlo Technique. RT ENEA/AMB/ /1998 (to be published).