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

Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

Volumn 476, Issue 1-2, 2002, Pages 446-451

  Bartlett, D T ^a   Hager, L G ^a   Tanner, R J ^a   Haley, R M ^b   Cooper, A J ^b  

^a PUBLIC HEALTH ENGLAND   (United Kingdom)

^b SELLAFIELD LTD   (United Kingdom)

Author keywords

Direction distribution measurements; MOX fuel; Neutron dosimetry

Indexed keywords

DOSIMETERS; MONTE CARLO METHODS; NEUTRONS; NUCLEAR FUELS; NUCLEAR POWER PLANTS; RADIATION PROTECTION; SPECTRUM ANALYSIS;

NEUTRON DOSES;

DOSIMETRY;

EID: 0036133330     PISSN: 01689002     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0168-9002(01)01488-7     Document Type: Article

References (13)

1. Considerations of dosimetry quantities in dose and ALARP assessments
2. Conversion coefficients for use in radiological protection against external radiation
3. Recent enhancements to the understanding of the response of the NRPB neutron personal dosemeter
4. The response of a neutron rem counter to thermal, to intermediate energy, and to fast neutrons