A scenario of large amount of radioactive materials discharge to the air from the Unit 2 reactor in the Fukushima Daiichi NPP accident
Creators
- 1. Sociotechnical Systems Safety Research Inst., Hitachinaka, Ibaraki (Japan)
Description
Based on an analysis of the measured data with review of calculated results on the core melt accident, a scenario is investigated for large amount of radioactive materials discharge to the air from the Unit 2 reactor. The containment pressure suppression chamber (S/C) should have failed until the noon on 12 March 2011 only by seismic load due to the huge earthquake on 11 March or by combination of seismic deterioration and dynamic load due to steam flowing-in through safety relief valve. Opening of the two safety relief valves (SRVs) at 14 March 21:18 should have resulted in discharge of large amount of radioactive materials through the S/C breach with the measured air dose rate peak value of 3.130E-3Sv/h at 21:37 near the main gate of the site. The containment drywell (D/W) should have failed at 15 March 06:25, at the cable penetration seal due to high temperature caused by the fuel materials heating up on the floor of the D/W, which had flowed out from the reactor pressure vessel. Then large amount of radioactive materials should have been discharged through the D/W breach with the measured air dose rate peak value of 1.193E-2Sv/h at 15 March 9:00. (author)
Availability note (English)
Available from http://dx.doi.org/10.1080/00223131.2012.669237Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 49
- Journal Issue
- 3-4
- Journal Page Range
- p. 360-365
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 43093668
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- DAILY VARIATIONS; DOSE RATES; FISSION PRODUCT RELEASE; FUKUSHIMA-2 REACTOR; HOURLY VARIATIONS; MELTDOWN; PRESSURE SUPPRESSION; RADIATION MONITORING; REACTOR VESSELS; RELIEF VALVES; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; BWR TYPE REACTORS; CONTAINERS; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; MONITORING; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; VALVES; VARIATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs., 3 figs.