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Dose Calculation for Emergency Control Room HVAC Filter

Davor Grgić, ; Faculty of Electrical Engineering and Computing, University of Zagreb Unska 3, Zagreb, Hrvatska
Štefica Vlahović, ; Faculty of Electrical Engineering and Computing, University of Zagreb Unska 3, Zagreb, Hrvatska
Mario Matijević, ; Faculty of Electrical Engineering and Computing, University of Zagreb Unska 3, Zagreb, Hrvatska
Paulina Dučkić ; Faculty of Electrical Engineering and Computing, University of Zagreb Unska 3, Zagreb, Hrvatska
Srđan Špalj ; Nuclear Power Plant Krško Vrbina 12, 8270 Krško, Croatia

Sažetak

NPP Krsko is introducing Emergency Control Room (ECR) as part of safety upgrades.
According to 10CFR50 Appendix A, GDC 19, both main control room and emergency control
room should have adequate radiation protection to permit operators to shutdown the plant and keep
it in safe shutdown conditions without receiving more than 50 mSv effective whole body dose,
within 30 days from accident initiation. One of the important prerequisites to achieve that is proper
operation of control room HVAC. In this work we are focused to calculation of gamma doses from
radioactive materials accumulated in HEPA and charcoal filters during 30 days of HVAC operation.
The dose at selected points around the filter was calculated using Microshield 10.0 point kernel
code. The radioactive gamma source is calculated using RADTRAD 3.03 for plant's severe accident
SGTR sequence calculated with MAAP 4.0.7 code. Calculated dose rates at peak filter activity are
compared against results obtained with SCALE 6.2 MAVRIC shielding sequence (Monaco Monte
Carlo functional module and CADIS methodology). The reasonable agreement between point
kernel and hybrid Monte Carlo results was obtained.

Ključne riječi

Emergency Control Room, HVAC filter, gamma dose, point kernel, Monte Carlo

Hrčak ID:

247093

URI

https://hrcak.srce.hr/247093

Datum izdavanja:

28.10.2019.

Posjeta: 364 *