Comparison of neutron dose quantities and instrument and dosemeter readings at representative locations in an MOX fuel fabrication plant-Reference-Cited by-同舟云学术

Comparison of neutron dose quantities and instrument and dosemeter readings at representative locations in an MOX fuel fabrication plant

Published:2002-01 Issue:1-2 Volume:476 Page:446-451
ISSN:0168-9002
Container-title:Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
language:en
Short-container-title:Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

Author:

Bartlett D.T,Hager L.G,Tanner R.J,Haley R.M,Cooper A.J

Publisher

Elsevier BV

Subject

Instrumentation,Nuclear and High Energy Physics

Reference13 articles.

1. Answers Software Service, MCBEND User Guide to Version 9D, Issue 7, AEA Technology, Winfrith, 1994.

2. A.J. Cooper, R.M. Haley, Considerations of dosimetry quantities in dose and ALARP assessments, ANS Radiation Protection and Shielding Division Topical Conference, Nashville, TN, April 19–23, 1998.

3. International Commission on Radiation Units and Measurements, Conversion Coefficients for Use in Radiological Protection Against External Radiation, ICRU Report 57, ICRU, Bethesda, 1998.

4. International Commission on Radiological Protection, Conversion Coefficients for use in Radiological Protection Against External Radiation, ICRP Publication 74, Pergamon Press, Oxford, 1996.

5. R.A. Hollnagel, private communication, 1994.

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