Skip Navigation

Radiation Protection Dosimetry 2004 110(1-4):123-127; doi:10.1093/rpd/nch190
This Article
Right arrow Full Text
Right arrow Full Text (PDF)
Right arrow Alert me when this article is cited
Right arrow Alert me if a correction is posted
Services
Right arrow Email this article to a friend
Right arrow Similar articles in this journal
Right arrow Similar articles in ISI Web of Science
Right arrow Similar articles in PubMed
Right arrow Alert me to new issues of the journal
Right arrow Add to My Personal Archive
Right arrow Download to citation manager
Right arrow Search for citing articles in:
ISI Web of Science (14)
Right arrowRequest Permissions
Google Scholar
Right arrow Articles by Lacoste, V.
Right arrow Articles by Gressier, V.
Right arrow Search for Related Content
PubMed
Right arrow PubMed Citation
Right arrow Articles by Lacoste, V.
Right arrow Articles by Gressier, V.
Social Bookmarking
Add to CiteULike   Add to Connotea   Add to Del.icio.us  
What's this?

Radiation Protection Dosimetry Vol. 110 Nos. 1-4 © Oxford University Press 2004; all rights reserved

Monte Carlo simulation of the IRSN CANEL/T400 realistic mixed neutron–photon radiation field

V. Lacoste* and V. Gressier

Institut de Radioprotection et de Sûreté Nucléaire BP 3, 13115 Saint-Paul-lez-Durance Cedex, France

* Corresponding author: Veronique.Lacoste{at}irsn.fr

The calibration of dosemeters and spectrometers in realistic neutron fields simulating those encountered at workplaces is of high necessity to provide true and reliable dosimetric information to the exposed nuclear workers. The CANEL assembly was set-up at IRSN to produce such neutron fields. It comprises a depleted uranium shell, to produce fission neutrons, then iron and water to moderate them and a polyethylene duct. The new presented CANEL facility is used with 3.3 MeV neutrons. Calculations were performed with the MCNP4C code to characterise this mixed neutron–photon expanded radiation field at the position where calibrations are usually performed. The neutron fluence energy and the direction distributions were calculated and the operational quantities were derived from these distributions. The photon fluence and corresponding ambient dose equivalent were also estimated. Comparison with experimental results showed an overall good agreement.


Add to CiteULike CiteULike   Add to Connotea Connotea   Add to Del.icio.us Del.icio.us    What's this?


This article has been cited by other articles:


Home page
 Radiat Prot DosimetryHome page
M. Luszik-Bhadra, D. Bartlett, T. Bolognese-Milsztajn, M. Boschung, M. Coeck, G. Curzio, F. d'Errico, A. Fiechtner, V. Lacoste, L. Lindborg, et al.
CHARACTERISATION OF MIXED NEUTRON PHOTON WORKPLACE FIELDS AT NUCLEAR FACILITIES BY SPECTROMETRY (ENERGY AND DIRECTION) WITHIN THE EVIDOS PROJECT
Radiat Prot Dosimetry, September 23, 2007; (2007) ncm419v1.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
V. Lacoste
Design of a new IRSN thermal neutron field facility using Monte-Carlo simulations
Radiat Prot Dosimetry, August 1, 2007; 126(1-4): 58 - 63.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
M. Luszik-Bhadra, V. Lacoste, M. Reginatto, and A. Zimbal
Energy and direction distribution of neutrons in workplace fields: implication of the results from the EVIDOS project for the set-up of simulated workplace fields
Radiat Prot Dosimetry, August 1, 2007; 126(1-4): 151 - 154.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
Q. Chau and T. Lahaye
Evaluation of dose equivalent by the electronic personal dosemeter for neutron 'Saphydose-N' at different workplaces of nuclear facilities
Radiat Prot Dosimetry, July 1, 2007; 125(1-4): 271 - 274.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
J. Kyllonen and L. Lindborg
Photon and neutron dose discrimination using low pressure proportional counters with graphite and A150 walls
Radiat Prot Dosimetry, July 1, 2007; 125(1-4): 314 - 317.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
M. Luszik-Bhadra, T. Bolognese-Milsztajn, M. Boschung, M. Coeck, G. Curzio, F. d'Errico, A. Fiechtner, V. Lacoste, L. Lindborg, M. Reginatto, et al.
Direction distributions of neutrons and reference values of the personal dose equivalent in workplace fields
Radiat Prot Dosimetry, July 1, 2007; 125(1-4): 364 - 368.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
M. Reginatto
Bayesian approach for quantifying the uncertainty of neutron doses derived from spectrometric measurements
Radiat Prot Dosimetry, December 1, 2006; 121(1): 64 - 69.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
P. Crovisier, B. Asselineau, G. Pelcot, L. Van-Ryckeghem, A. Cadiou, H. Truffert, J. E. Groetz, and M. Benmosbah
French comparison exercise with the rotating neutron spectrometer, 'ROSPEC'
Radiat Prot Dosimetry, December 20, 2005; 115(1-4): 324 - 328.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
A. Fiechtner, M. Boschung, and C. Wernli
Present status of the personal neutron dosemeter based on direct ion storage
Radiat Prot Dosimetry, August 1, 2004; 110(1-4): 213 - 217.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
M. Luszik-Bhadra, M. Reginatto, and V. Lacoste
Measurement of energy and direction distribution of neutron and photon fluences in workplace fields
Radiat Prot Dosimetry, August 1, 2004; 110(1-4): 237 - 241.
[Abstract] [Full Text] [PDF]

Home page
 Radiat Prot DosimetryHome page
T. Bolognese-Milsztajn, D. Bartlett, M. Boschung, M. Coeck, G. Curzio, F. d'Errico, A. Fiechtner, V. Giusti, V. Gressier, J. Kyllonen, et al.
Individual neutron monitoring in workplaces with mixed neutron/photon radiation
Radiat Prot Dosimetry, August 1, 2004; 110(1-4): 753 - 758.
[Abstract] [Full Text] [PDF]


Disclaimer: Please note that abstracts for content published before 1996 were created through digital scanning and may therefore not exactly replicate the text of the original print issues. All efforts have been made to ensure accuracy, but the Publisher will not be held responsible for any remaining inaccuracies. If you require any further clarification, please contact our Customer Services Department.