Published 1985 | Version v1
Journal article

Shielding calculations for ships carrying irradiated nuclear fuel

Creators

  • 1. UKAEA Risley Nuclear Power Development Establishment. Process Technology and Safety Directorate

Description

A number of ships have been constructed to carry irradiated fuel from Japan to the U.K. and France, for reprocessing. About 20 transport flasks may be carried on each voyage. Permanent shielding must be provided on the ships to ensure that no member of the crew receives an annual dose greater than a specified limit. As the fuel is of varying type and radiation history, and as flasks of differing designs are used, many shielding calculations are needed. There are a number of difficulties in making shielding calculations for the ships. The geometry is complex, dimensions are large and considerable air spaces are involved. The paper considers possible methods of calculation. The line-of-sight method is chosen for most of the calculations, for both γ-radiation and neutrons. The basic data which is used in the calculations is described. As the methods of calculation are somewhat approximate, it is necessary to provide confirmation that they are sufficiently accurate. Validation has been provided in two ways. First, measurements have been made on board one of the ships, Pacific Crane, and these have been checked against calculation. Second, a simplified model of the flasks and ship has been set up, and calculations checked against more sophisticated methods. Results of the validation checks are presented, and it is shown that adequate accuracy is achieved. (author)

Additional details

Publishing Information

Journal Title
Ann. Nucl. Energy
Journal Volume
12
Journal Issue
2
Series
Ann. Nucl. Energy.
Journal Page Range
53-64
ISSN
0306-4549

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
16064422
Subject category
S42: ENGINEERING; S42: ENGINEERING;
Descriptors DEI
A CODES; COMPUTER CALCULATIONS; D CODES; M CODES; MONTE CARLO METHOD; R CODES; SHIELDING; SHIPS; SPECIFICATIONS; SPENT FUELS; TRANSPORT THEORY; VERIFICATION
Descriptors DEC
COMPUTER CODES; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS