Published October 1997 | Version v1
Miscellaneous

Radiation shielding at interim storage facility for CANDU-type nuclear spent fuel

  • 1. Center of Technology and Engineering for Nuclear Projects - CITON, PO Box 5204 MG-04, R-76900 Bucuresti (Romania)

Description

Technical measures in radiological protection are taken in the interim storage facility design to ensure that, during normal operation, exposures of workers and members of public to ionizing radiation are limited to levels lower than regulatory limits. The spent fuel storage design provides for radiation exposure to be as low as reasonable achievable (ALARA principles). The evaluation of radiation shields includes the most conservative provisions: - all locations which may contain spent fuel are full; - the spent fuel has reached the maximum burnup; - the post irradiation cooling period should be the minimum reasonable; - equipment for handling contains the maximum amount of spent fuel. Radiation shields should ensure that external radiation fields do not exceed limits accepted by the Regulatory Body Module. The evaluation has been performed with two computer codes, QAD-5K and MICROSHIELD-4. (authors)

Availability note (English)

Available from the author(s) or Energy Info-Documentation Centre, Roma-nian Electricity Authority, RENEL - Engineering Studies and Research Group, Bldv. Energeticienilor No.8, Sector 3, R-79619 Bucharest (RO).
Part of:
SIEN'97 - International Symposium on Nuclear Energy. Radioactive Waste Management

Additional details

Publishing Information

Publisher
Energy Info-Documentation Centre.
Imprint Place
Bucharest (Romania)
Imprint Title
SIEN'97 - International Symposium on Nuclear Energy. Radioactive Waste Management
Imprint Pagination
346 p.
Journal Page Range
(pt.1) p. 221-226.

Conference

Title
Radioactive Waste Management.
Acronym
SIEN'97 - International Symposium on Nuclear Energy
Dates
24-25 Oct 1997.
Place
Bucharest (Romania).

Optional Information

Notes
6 refs. Imprint:Proceedings published in two parts.