Published 1991
| Version v1
Journal article
Modelling simplifications in flask shielding
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.