WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
LEADERLEADERLLead-cooled ead-cooled EEuropean uropean AAdvanced dvanced DEDEmonstration monstration RReactoreactor
WP 5 - MEETINGWP 5 - MEETING
26th February 201326th February 2013
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 22
Participants Royal Institute of Technology – Stockholm (KTH) Empresarios Agrupados (EA)
Objective Provide scoping assessment of the source term available for
release to the environment Thermodynamic calculations Containment leakage and rates Calculations of fission products formed
Assess the transport of airborne radionuclides in containment
Perform calculations of the radiological impact of the releases to the public
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 33
Second Part: In charge of EA Perform the radiological analysis to determine the impact on
the environment Define the methodology to calculate the radiological impact Define the dose limits for each condition
Input needed from: The first part of this Task: Source Term Assessment by KTH WP 3 Conceptual Design, to define the release mode and the
meteorological conditions
Dose assessment for accident condition
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 44
Dose assessment methodology: A preliminary dose assessment will be performed with the
following objectives:
To calculate a preliminary site boundary dose to public (at the Exclusion Area Boundary) based on the reference source terms with no credit to any engineered safeguards.
To verify the compliance with the present European criteria for licensing LWR
To analyse the sensitivity on the dose to the public of the main uncertainties: retention of radionuclides in the primary coolant, fuel damage extension,...
To identify radionuclides with the biggest influence on the environmental dose and to highlight the systems able to limit their release.
To analyse the impact on the results of the dose calculation methodology used.
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 55
The calculation of accident conditions will be processed according to the Regulatory Guide 1.183 issued by the US NRC
In the calculation process, the ways of contamination
considered are:
The external exposure by submersion in a radioactive cloud.
The internal exposure by inhalation of radioactive particles.
No credit is given to the exposure via ingestion of contaminated food (milk, plants, meat…).
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 66
The dose limits for members of the public set in case of accident condition:
The effective dose limits for members of the public set in case of accidents are (NRC RG 1.183):
250 mSv for the accidents assumed to have the worst radiological consequences: a LOCA, a main steam line break for a PWR, a steam generator tube rupture for a PWR…, etc
63 mSv for accidents with less radiological impact: BWR Rod Drop Accident, PWR ROD Ejection Accident…, etc
The new trends for the dose release targets of currently designed power plants are around 50 mSv for accidents
Public
Whole body(External exposure)
250 mSv(R.G. 1.195)
Thyroid(Internal exposure)
3000 mSv(R.G. 1.195)
TEDE (CEDE+DDE)250 mSv
(R.G. 1.183)
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 77
Data and Assumptions 7/171 SAs severely damaged Source term Fission Products: Kr, Xe, I, Sr, Cs, 3H ENEA
Activation: 3H (CR), 210Po (Pb) ENEA
100% release from pins & immediate release Volatilization fractions 800ºC (ULOF) I, Cs, Sr, Po (by KTH)
Radionuclides Noble Gases Iodine Caesium Strontium Polonium Tritium
Volatilization Fraction(800ºC - ULOF)
100% 2.99E-5 4.91E-6 5.34E-13 2.96E-7 100%
Volatilization Fraction(480ºC)
100% 9.51E-8 2.41E-7 7.53E-16 2.09E-10 100%
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 88
Data and Assumptions Containment Model
Chemical form of Iodine isotopes R.G. 1.183 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)
SiteDistance
(m)
X/Q (s/m3)
0-2 h 2-8 h 8-24 h 24-96 h 96 h – end
Spanish NPP 1000 3.75E-4 1.91E-4 1.36E-4 6.66E-5 2.40E-5
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 99
Model for RADTRAD calculation:
Gap Release Coolant Release Cover G. Release
Fraction gap→Pb Dissol. Pb→CG Fraction CG→Cnt. Spray Depos. Decay Leakage Filtering Decay
Noble Gas 100% Instantan. NO Instantan. 1.00E+00 Instantan. NO NO YES YES NO NO
Iodine 100% Instantan. YES Instantan. 2.99E-05 Instantan. NO NO YES YES NO NO
Cesium 100% Instantan. YES Instantan. 4.91E-06 Instantan. NO NO YES YES NO NO
Strontium 100% Instantan. YES Instantan. 5.34E-13 Instantan. NO NO YES YES NO NO3H (TF) 100% Instantan. NO Instantan. 1.00E+00 Instantan. NO NO YES YES NO NO
3H (Act.) - N/A NO Instantan. 1.00E+00 Instantan. NO NO YES YES NO NO
Polonium - N/A YES Instantan. 2.96E-07 Instantan. NO NO YES YES NO NO
Removal after releaseFamily Isotope
Containment Removal (t: 0-720h)
Model simplifications
Release into containment = 100% Core Inventory (instantaneoust=0)
x [Volatilization fraction]
Containment Removal: only DECAY and LEAKAGE (environment)
NO Sprays, NO Deposition
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 1010
PRIMARY COOLANT
(LEAD)
100% Release fromfuel & No
Dissolution
100% Release fromfuel & Dissolution
in coolant
PRIMARY COOLANT
(LEAD)
100% Release fromfuel & No
Dissolution
100% Release fromfuel & Dissolution
in coolant
NG (Xe, Kr)
I, Cs, Sr (1)
CONTAINMENT ATMOSPHERE
100% Release
CalculatedRelease Fraction
(KTH)
CalculatedRelease Fraction
(KTH) (2)
210Po
7 damagedSA’s
7 damagedSA’s
Activation of Pb andBi impurities
Activation of Pb andBi impurities
ENVIRONMENT
Leakage: 0.1% vol/day
Leakage: 0.1% vol/day
RELEASE MODEL
(2) There are Hg, Tl, Bi, Zn, Ag, In, Cd…isotopes, not covered by this
assessment
(1) There are other FPs, not covered by this
assessment
& Tritium(including
activation of B-10)
CORE
Model for RADTRAD calculation:
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 1111
Activity Released to Environment:Gases Activity released to the environment
1.0E+10
1.0E+11
1.0E+12
1.0E+13
1.0E+14
1.0E+15
1 10 100 1000t (h)
A (B
q)
Xe-133Xe-133mXe-135Kr-85mKr-85Kr-87Kr-88H-3
I, Cs, Sr and Po Activity released to the environment
1.0E+04
1.0E+05
1.0E+06
1.0E+07
1.0E+08
1.0E+09
1.0E+10
1 10 100 1000t (h)
A (B
q)I-131I-132I-133I-134I-135Cs-134Cs-137Sr-90Po-210
True Gases
Lead-soluble FP & AP
~1012-1014 Bq (~100%)
~107-1010 Bq (<0.01%)
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 1212
Whole-body dose
Xenon & Krypton~0.1 mSv after 30 days (~100%)
1.0E-05
1.0E-04
1.0E-03
1.0E-02
1.0E-01
0 100 200 300 400 500 600 700 800
t (h)
Dac
(mSv
)
Kr-85mKr-87Kr-88Xe-133mXe-133Xe-135mXe-135Xe-138Total
88Kr+135Xe+133Xe (84%)
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 1313
Thyroid dose
Iodine & Tritium~0.03 mSv after 30 days (~100%) 131I+3H+133I (99%)
1.0E-07
1.0E-06
1.0E-05
1.0E-04
1.0E-03
1.0E-02
1.0E-01
0 100 200 300 400 500 600 700 800
t (h)
Dac
(mSv
)
I-131I-132I-133I-135H-3Po-210Cs-137Total
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 1414
TEDE
Noble Gases & Tritium~0.1 mSv after 30 days (100%)
Xe-135m, 1%
H-3, 13%
Xe-135, 29%
I-131, 0%I-132, 0%
Xe-133, 16%
Kr-88, 28%
Cs-137, 0%
Cs-135, 0%
Cs-134, 0%
Xe-138, 6%
Xe-133m, 0%Xe-131m, 0%I-135, 0%
I-134, 0%
I-133, 0%
Kr-85m, 2% Kr-83m, 0%
Kr-87, 5%
Kr-85, 0%
ALFRED (LEADER) (J anuary 2013)
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 1515
Doses
Whole-body, Thyroid & TEDE~0.04-0.001% of US NRC limits after 30 days
CalculationWhole-body
(mSv)Thyroid(mSv)
TEDE(mSv)
NG, Sr, Cs, I 9.43E-02 1.58E-02 9.48E-02
3H 1.16E-06 1.42E-02 1.42E-02
210Po 1.93E-13 4.40E-05 4.37E-04
Total 9.43E-02 3.00E-02 1.09E-01
NRC Limit250
(R.G. 1.195)3000
(R.G. 1.195)
250(R.G.1.183)Target: 50
% Limit 0.038 0.0010.044
Target: 0.22
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 1616
Doses – Sensitivity Analysis
Whole-body, Thyroid & TEDEX/Q*10 & leakage*10 Source term 100 times higher
CalculationWhole-body
(mSv)Thyroid(mSv)
TEDE(mSv)
NG, Sr, Cs, I 9.36E+00 1.52E+00 9.41E+00
3H 1.05E-04 1.30E+00 1.30E+00
210Po 1.76E-11 4.02E-03 3.99E-02
Total 9.36E+00 2.82E+00 1.07E+01
NRC Limit250
(R.G. 1.195)3000
(R.G. 1.195)
250(R.G.1.183)Target: 50
% Limit 3.7 0.14.3
Target: 21.5
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 1717
Conclusions
Compliance with present European Licensing Criteria
Conservative assumptions (damage, release, timing…)
No credit to engineered safeguards* (*Leak rate in accordance with non-loss of containment integrity)
~100% of whole-body dose due to Noble Gases
Thyroid dose due to I-131 and H-3 (No retention of tritium in lead)
~13% of TEDE due to Tritium (NO retention in lead)
Target leak rate: 0.1%/d radiologically adequate
Need of on-site meteorological data (X/Q)
Impact of dose methodology not expected to be high (Noble Gases)
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 1818
D18 - Report on Containment Assessment for the ETDR Author: EA
Dates: Rev. 0 – January 2013 (status: for comments)
Rev. 1 – March 2013
WP 5 Safety and Transient AnalysisTask 5.6 Containment and source term assessment for the ETDR
26 Feb 2013, Petten26 Feb 2013, Petten 1919
Thank you!