Modelling of neutron survey instrument performance and experimental validation of those calculated response data-Reference-Cited by-同舟云学术

Modelling of neutron survey instrument performance and experimental validation of those calculated response data

Published:2005-12-20 Issue:1-4 Volume:116 Page:406-410
ISSN:1742-3406
Container-title:Radiation Protection Dosimetry
language:en
Short-container-title:

Author:

Tanner R. J.,Bartlett D. T.,Hager L. G.,Jones L. N.,Molinos C.,Roberts N. J.,Taylor G. C.,Thomas D. J.

Publisher

Oxford University Press (OUP)

Subject

Public Health, Environmental and Occupational Health,Radiology Nuclear Medicine and imaging,General Medicine,Radiation,Radiological and Ultrasound Technology

Link

http://academic.oup.com/rpd/article-pdf/116/1-4/406/4536380/nci078.pdf

Reference10 articles.

1. Andersson, I. Ö. and Braun, J. A neutron rem counter with uniform sensitivity from 0.025 eV to 10 MV. In: Proceedings of the Symposium on Neutron Dosimetry, Harwell (1962) (Vienna: IAEA), Vol. 2, pp. 85–89 (1963).

2. Andersson, I. Ö. and Braun, J. A neutron rem counter. Nucleonik6, 237–241 (1964).

3. Leake, J. W. A spherical dose equivalent neutron detector. Nucl. Instrum. Methods phys. Res. A45, 151–156 (1965).

4. Leake, J. W. An improved spherical dose equivalent neutron detector. Nucl. Instrum. Methods Phys. Res. A63, 329–332 (1968).

5. Briesmeister, J. F., Ed. MCNP™—a general Monte Carlo N-particle transport code, Version 4C. LANL Report LA-13709-M. (Los Alamos National Laboratory, Los Alamos, NM) (2000).

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