Published 1991 | Version v1
Journal article

Modelling simplifications in flask shielding

  • 1. Nuclear Transport Ltd., Risley (United Kingdom)

Description

Flask shielding calculations are required to predict the dose rates external to the flask package. The flask package must endure that the radiation levels are within the regulatory limits specified for the transportation of radioactive material. Modelling the geometrical heterogeneities in the flask design, such as neutron moderators embedded in the flask wall are often simplified for rapid solution/sensitivity studies for flask shielding problems. Examples of modelling simplifications used in flask shielding studies are described. The results presented show that the simplified approach may, in certain cases, under-predict the external dose rates compared with explicit modelling. (author)

Additional details

Additional titles

Augmented title (English)
Radioactive material transport

Publishing Information

Journal Title
International Journal of Radioactive Materials Transport
Journal Volume
2
Journal Issue
1-3
Series
Int. J. Radioact. Mater. Transp.
Journal Page Range
53-56
ISSN
0957-476X
CODEN
IJRTE

Conference

Title
2. International conference on transport for the nuclear industry.
Dates
8-10 May 1991.
Place
Bournemouth (United Kingdom).

INIS

Country of Publication
United Kingdom
Country of Input or Organization
United Kingdom
INIS RN
23014769
Subject category
S42: ENGINEERING; S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BIOLOGICAL SHIELDING; CASKS; COMPUTERIZED SIMULATION; DOSE RATES; MATHEMATICAL MODELS; NEUTRONS; SPENT FUELS; TRANSPORT
Descriptors DEC
BARYONS; CONTAINERS; ELEMENTARY PARTICLES; ENERGY SOURCES; FERMIONS; FUELS; HADRONS; MATERIALS; NUCLEAR FUELS; NUCLEONS; REACTOR MATERIALS; SHIELDING; SIMULATION

Optional Information

Secondary number(s)
CONF--910577.