Presentation is loading. Please wait.

Presentation is loading. Please wait.

KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association Institute for Neutron Physics and Reactor.

Similar presentations


Presentation on theme: "KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association Institute for Neutron Physics and Reactor."— Presentation transcript:

1 KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association Institute for Neutron Physics and Reactor Technology Containment assessment results for ALFRED Results and conclusions (EA) E. Bubelis of behalf of Task 5.6 of LEADER WP5

2 Institute for Neutron Physics and Reactor Technology (INR) E. Bubelis – LEADER/ELECTRA Safety Review Workshop, Petten Model for RADTRAD calculation

3 Institute for Neutron Physics and Reactor Technology (INR) E. Bubelis – LEADER/ELECTRA Safety Review Workshop, Petten 7/171 SAs severely damaged Source term  Fission Products: Kr, Xe, I, Sr, Cs, 3 H  ENEA Activation: 3 H (CR), 210 Po (Pb)  ENEA 100% release from pins & immediate release Volatilization fractions  800ºC (ULOF)  I, Cs, Sr, Po (by KTH) Radionuclides Noble Gases IodineCaesiumStrontiumPoloniumTritium Volatilization Fraction (800ºC - ULOF) 100%2.99E-54.91E-65.34E E-7100% Volatilization Fraction (480ºC) 100%9.51E-82.41E-77.53E E-10100% Data & assumptions (1/2)

4 Institute for Neutron Physics and Reactor Technology (INR) E. Bubelis – LEADER/ELECTRA Safety Review Workshop, Petten Containment Model Chemical form of Iodine isotopes  R.G  Irrelevant (No removal) Radionuclide removal from containment  only decay and leakage, NO natural deposition, NO spray Primary Containment Leak rate  0.1% d -1 (EUR for LWR, Vol. 2, Rev. C) Dose Conversion Factors  FGR-11&12 X/Q  need of meteorological data  Pitesti (Romania) Reference values for accident condition (Spanish NPP) Site Distance (m) X/Q (s/m 3 ) 0-2 h2-8 h8-24 h24-96 h96 h – end Spanish NPP E-41.91E-41.36E-46.66E-52.40E-5 Data & assumptions (2/2)

5 Institute for Neutron Physics and Reactor Technology (INR) E. Bubelis – LEADER/ELECTRA Safety Review Workshop, Petten Activity Released to Environment Noble Gases & Tritium Lead-soluble FP & AP ~ Bq (~100%) ~ Bq (<0.01%)

6 Institute for Neutron Physics and Reactor Technology (INR) E. Bubelis – LEADER/ELECTRA Safety Review Workshop, Petten Whole-body dose Xenon & Krypton ~0.1 mSv after 30 days (~100%) 88 Kr+ 135 Xe+ 133 Xe (84%)

7 Institute for Neutron Physics and Reactor Technology (INR) E. Bubelis – LEADER/ELECTRA Safety Review Workshop, Petten Thyroid dose Iodine & Tritium ~0.03 mSv after 30 days (~100%) 131 I+ 3 H+ 133 I (99%)

8 Institute for Neutron Physics and Reactor Technology (INR) E. Bubelis – LEADER/ELECTRA Safety Review Workshop, Petten Total Effective Dose Equivalent (TEDE) Noble Gases & Tritium ~0.1 mSv after 30 days (100%)

9 Institute for Neutron Physics and Reactor Technology (INR) E. Bubelis – LEADER/ELECTRA Safety Review Workshop, Petten Doses Whole-body, Thyroid & TEDE ~ % of US NRC limits after 30 days Calculation Whole-body (mSv) Thyroid (mSv) TEDE (mSv) NG, Sr, Cs, I9.43E E E-02 3H3H1.16E E Po1.93E E E-04 Total9.43E E E-01 NRC Limit 250 (R.G ) 3000 (R.G ) 250 (R.G.1.183) Target: 50 % Limit Target: 0.22

10 Institute for Neutron Physics and Reactor Technology (INR) E. Bubelis – LEADER/ELECTRA Safety Review Workshop, Petten Doses – Sensitivity Analysis Whole-body, Thyroid & TEDE X/Q*10 & leakage*10  Source term 100 times higher Calculation Whole-body (mSv) Thyroid (mSv) TEDE (mSv) NG, Sr, Cs, I9.36E E E+00 3H3H1.05E E Po1.76E E E-02 Total9.36E E E+01 NRC Limit 250 (R.G ) 3000 (R.G ) 250 (R.G.1.183) Target: 50 % Limit Target: 21.5


Download ppt "KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association Institute for Neutron Physics and Reactor."

Similar presentations


Ads by Google