Measurement of dose rates and Monte Carlo analysis of neutrons in a spent-fuel shipping vessel

Journal Article · Fri Aug 01 04:00:00 EDT 1986 · Nucl. Technol.; (United States)

OSTI ID:5366483

Ueki, K; Namito, Y; Fuse, T

On-board experiments were carried out in a spent-fuel shipping vessel, the Pacific Swan, in which 13 casks of TN-12A and Excellox 3 were loaded in five holds, and neutron and gamma-ray dose rates were measured on the hatch covers of the holds. Before shipping those casks, dose rates were also measured on the cask surfaces, one by one, to eliminate radiation from other casks. The Monte Carlo coupling technique was employed successfully to analyze the measured neutron dose rate distributions in the spent-fuel shipping vessel. Through this study, the Monte Carlo coupling code system, MORSE-CG/CASK-VESSEL, on which the MORSE-CG code was based, was established. The agreement between the measured and the calculated neutron dose rates on the TN-12A cask surface was quite satisfactory. The calculated neutron dose rates agreed with the measured values within a factor of 1.5 on the hold 3 hatch cover and within a factor of 2 on the hold 5 hatch cover in which the concrete shield was fixed in the Pacific Swan.

• Research Organization: Ship Research Institute, Nuclear Technology Div., Mitaka, Tokyo 181
• OSTI ID: 5366483
• Journal Information: Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 74:2; ISSN NUTYB
• Country of Publication: United States
• Language: English

Related Subjects

050900 -- Nuclear Fuels-- Transport
Handling
& Storage
054000* -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
42 ENGINEERING
420204 -- Engineering-- Shipping Containers
BARYONS
BUILDING MATERIALS
CASKS
COMPUTER CODES
CONCRETES
CONTAINERS
CONTAMINATION
DOSE RATES
DOSIMETRY
ELECTROMAGNETIC RADIATION
ELEMENTARY PARTICLES
ENERGY SOURCES
FERMIONS
FUELS
GAMMA DOSIMETRY
GAMMA RADIATION
HADRONS
IONIZING RADIATIONS
M CODES
MARITIME TRANSPORT
MATERIALS
MEASURING METHODS
MONTE CARLO METHOD
NEUTRON DOSIMETRY
NEUTRONS
NUCLEAR FUELS
NUCLEONS
RADIATIONS
REACTOR MATERIALS
RESEARCH PROGRAMS
SHIELDING
SHIELDS
SHIPS
SPENT FUEL CASKS
SPENT FUELS
SURFACE CONTAMINATION
TRANSPORT