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).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).
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 29018327
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ALARA; CANDU TYPE REACTORS; CONCRETES; M CODES; MAXIMUM PERMISSIBLE ACTIVITY; PERSONNEL DOSIMETRY; PUBLIC HEALTH; Q CODES; RADIATION DOSES; RADIATION PROTECTION; RADIOACTIVE WASTE FACILITIES; SHIELDING; SHIELDING MATERIALS; SPENT FUEL STORAGE; WASTE STORAGE
- Descriptors DEC
- BUILDING MATERIALS; COMPUTER CODES; DOSIMETRY; HEAVY WATER MODERATED REACTORS; MANAGEMENT; MATERIALS; MEDICINE; NUCLEAR FACILITIES; POWER REACTORS; PRESSURE TUBE REACTORS; PREVENTIVE MEDICINE; REACTORS; SAFETY STANDARDS; STANDARDS; STORAGE; THERMAL REACTORS; WASTE MANAGEMENT
Optional Information
- Notes
- 6 refs. Imprint:Proceedings published in two parts.