Assessment of dose factor changes to spent-fuel cask analyses

Conference · Wed Jan 01 04:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6707733

Broadhead, B L; Parks, C V ^[1]

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1. Oak Ridge National Lab., TN (United States)

This paper assesses how calculated doses from light water reactor (LWR) spent-fuel casks will be affected by the recently adopted American National Standards Institute (ANSI) standard neutron and gamma-ray fluence-to-dose factors as specified in ANSI-ANS-6.1.1-1991 (designated as ANSI91 herein) and changes in the neutron quality factor as per the 1985 International Commission on Radiological Protection (ICRP) recommendations. The 1985 ICRP recommendation of a uniform increase of a factor of 2 in the neutron quality factor was chosen for study because it appears to be an upper bound on the later changes recommended by both the National Council on Radiation Protection and Measurements NCRP Report 91 (1987) and ICRP Publication 60 (1991).

• OSTI ID: 6707733
• Report Number(s): CONF-921102--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
• Country of Publication: United States
• Language: English

Related Subjects

050900 -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
560100* -- Biomedical Sciences
Applied Studies-- Radiation Effects
63 RADIATION, THERMAL, AND OTHER ENVIRON. POLLUTANT EFFECTS ON LIVING ORGS. AND BIOL. MAT.
CALCULATION METHODS
CASKS
CONTAINERS
DOSE RATES
DOSES
DOSIMETRY
ICRP
INTERNATIONAL ORGANIZATIONS
NEUTRON DOSIMETRY
NEUTRON FLUENCE
QUALITY FACTOR
SPENT FUEL CASKS
STANDARDS