Conservatism of RADTRAN line-source model for estimating worker exposures
Conference
·
OSTI ID:7132109
- Western Washington Univ., Bellingham, WA (United States)
- Sandia National Labs., Albuquerque, NM (United States)
The dose rate to which these inspectors and handlers are exposed of radioactive materials during transport inspection is higher than the dose rate to which any other group is exposed during incident-free truck transportation (other groups include occupants of other vehicles on the route, persons residing near the route, others who might share the rights-of-way with trucks the spent fuel, and persons at stops), and higher than the dose rate to the drivers when they are in the truck cab. For most radioactive materials shipped in the United States there are only two handlings: one at the origin and one at the destination. The number of handlers does not vary greatly from one shipment to another of the same type. However, the number of inspections a given shipment might experience en route cannot be predicted with confidence because it can vary with changing state regulations, since there is no regulatory limit on the number of inspections that might occur. The potential population dose and risk associated with redundant inspections of spent fuel shipments should be evaluated carefully in the context of ALARA. That is the focus of this study. Two different methods were used to estimate gamma doses to inspectors for a representative fuel shipment. These methods were compared, and the results of the dose calculations were compared to other components of incident-free dose. Comparison is also made to a measured dose rate mapped in another investigation (Hostick, et al., 1992).
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 7132109
- Report Number(s):
- SAND--91-2601C; TTC--1119; CONF-920905--28; ON: DE93000757
- Country of Publication:
- United States
- Language:
- English
Similar Records
Intermodal transfer of spent fuel
Application of the RADTRAN 5 stop model
Experimental validation of the RADTRAN 5 incident-free and handler dose models
Conference
·
Mon Dec 31 23:00:00 EST 1990
·
OSTI ID:7202070
Application of the RADTRAN 5 stop model
Conference
·
Tue Dec 30 23:00:00 EST 1997
·
OSTI ID:663178
Experimental validation of the RADTRAN 5 incident-free and handler dose models
Journal Article
·
Thu Jul 01 00:00:00 EDT 1999
· Transactions of the American Nuclear Society
·
OSTI ID:20005739
Related Subjects
050900 -- Nuclear Fuels-- Transport
Handling
& Storage
054000* -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
560101 -- Biomedical Sciences
Applied Studies-- Radiation Effects-- Dosimetry & Monitoring-- (1992-)
61 RADIATION PROTECTION AND DOSIMETRY
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ANIMALS
CASKS
COMPUTER CODES
CONTAINERS
DOSES
INSPECTION
MAMMALS
MAN
MATERIALS
OCCUPATIONAL EXPOSURE
P CODES
PACKAGING
PRIMATES
R CODES
RADIATION DOSES
RADIOACTIVE MATERIALS
RISK ASSESSMENT
SPENT FUEL CASKS
TRANSPORT
VERTEBRATES
Handling
& Storage
054000* -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
560101 -- Biomedical Sciences
Applied Studies-- Radiation Effects-- Dosimetry & Monitoring-- (1992-)
61 RADIATION PROTECTION AND DOSIMETRY
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ANIMALS
CASKS
COMPUTER CODES
CONTAINERS
DOSES
INSPECTION
MAMMALS
MAN
MATERIALS
OCCUPATIONAL EXPOSURE
P CODES
PACKAGING
PRIMATES
R CODES
RADIATION DOSES
RADIOACTIVE MATERIALS
RISK ASSESSMENT
SPENT FUEL CASKS
TRANSPORT
VERTEBRATES