Published 1992 | Version v1
Book

Intermediate level waste transport shielding study

  • 1. Physics and Thermal Hydraulics Div., AEA Reactor Services, AEA Technology, Risley, Warrington, Cheshire WA3 6AT (United Kingdom)
  • 2. United Kingdom Nirex Limited, Curie Avenue, Harwell, Didcot, Oxfordshire OX11 0RH (United Kingdom)

Description

In this paper a scoping study is carried out to determine the likely shielding requirements for containers to transport UK operational Intermediate Level Wastes. Each re-usable container will carry four 500-litre drums of immobilized waste. shielding calculations for gamma and neutron radiation are required for 300 waste streams; a scaling technique was developed to reduce the burden of computation. Dose rates at the container surface and at a distance of 2 metres were calculated as a function of container wall thickness, and were also calculated for the unshielded wastes. An example is presented for one waste stream. A histogram summarizing the whole study will enable the optimum numbers of containers of various wall thicknesses to be determined for the UK waste disposal programme

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (United States)
ISBN
0-87262-891-4
Imprint Title
Proceedings of high level radioactive waste management
Imprint Pagination
2425 p.
Journal Page Range
p. 2062-2068.

Conference

Title
3. international high level radioactive waste management (IHLRWM) conference.
Dates
12-16 Apr 1992.
Place
Las Vegas, NV (United States).

Optional Information

Secondary number(s)
CONF-920430--.