Source term study for the General Electric simplified boiling water reactor (SBWR)
This report presents the analysis of the response of General Electric's Simplified Boiling Water Reactor (SBWR) plant for two selected severe accident sequences: (i) a high-pressure station blackout; (ii) a bottom drain line break. Sequences were analysed using the SBWR version of the MAAP 3. OB-Rev. 4 code that treats both thermal-hydraulics and FP-transport and deposition phenomena simultaneously. Thermal-hydraulic results are presented for some selected volumes of the primary circuit (core, steam separators, steam dryers, upper plenum and isolation condenser) and of the containment (lower drywell, central drywell, upper drywell, wetwell, passive containment cooling sytem (PCCS) and IC/PCCS pool). PF transport and deposition data are presented for noble gases, Csl, CsOH, Te(2) and SrO. Main areas of interest were: (i) FP sorption by structural materials and aerosol deposit revaporisation; (ii) FP depletion by steam condensation; (iii) late source of aerosols due to re-entrainment and resuspension from boiling pools.
Bibliographic Reference: EUR 15052 EN (1993) 132 pp., FS, free of charge
Availability: Available from Joint Research Centre, Publication Department, I-21020 Ispra (Va.) (IT)
Record Number: 199511390 / Last updated on: 1995-10-31
Original language: en
Available languages: en