Published June 1980
| Version v1
Report
Natural removal of particulate radioactivity in an LWR-containment during core meltdown accidents
Creators
- 1. Lab. for Aerosol Physics and Filter Tech., Kernforschungszentrum, Karlsruhe, Germany
Description
During core meltdown accidents in LWRs, large quantities of fission products and core material are vaporized and released to the containment in particulate form. The behavior and the natural removal of this aerosol is calculated with the computer code NAUA. Airborne aerosol mass in the containment and leaked masses are calculated for a typical accident sequence in the German PWR. Additionally, the influence of a containment failure on the total environmental impact is evaluated as a function of time. It is demonstrated that a period of three days of containment integrity is required to minimize the aerosol mass which escapes from the containment
Additional details
Publishing Information
- Imprint Title
- Thermal reactor safety
- Journal Page Range
- p. 1328-1335.
- Report number
- CONF-800403--(Vol.2)
Conference
- Title
- ANS thermal reactor safety meeting.
- Dates
- 8 - 11 Apr 1980.
- Place
- Knoxville, TN, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11570385
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SYSTEMS; ENVIRONMENTAL IMPACTS; FISSION PRODUCT RELEASE; MELTDOWN; PWR TYPE REACTORS; RADIOACTIVE AEROSOLS; RADIOACTIVE EFFLUENTS; RADIOACTIVITY TRANSPORT; REACTOR SAFETY
- Descriptors DEC
- ACCIDENTS; AEROSOLS; COLLOIDS; CONTAINMENT; DISPERSIONS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTOR ACCIDENTS; REACTORS; SAFETY; SOLS; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS