Dose Reconstruction Methods and Source Term Assessment using Data from Monitoring Networks and Mobile Teams A German Approach

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Dose Reconstruction Methods and Source Term Assessment using Data from Monitoring Networks and Mobile Teams A German Approach M. Bleher, U. Stöhlker, F. Gering Federal Office for Radiation Protection (BfS), Germany International Expert s Meeting on Assessment and Prognosis in Response to a Nuclear or Radiological Emergency (IEM9)

Outline German measurement and information system (IMIS) and decision support system RODOS Ground contamination maps and dose reconstruction method Update of the German Measurement Program R+D project: source term reconstruction method Experience with spectrometric dose rate probes

Integrated Measurement and Information System (IMIS) and Decision Support Systems RODOS IMIS Dose rate monitoring (BfS) 1750 monitoring stations Gamma-spectrometry (DWD) 40 monitoring stations Activity in air Activity on ground Amount of precipitation Mobile equipment 6 (BfS) + 16 (Länder) Activity on ground Dose rate RODOS Atmospheric dispersion Deposition and Transfer Activity deposited on ground Activity in food Dose assessment Inhalation, Ingestion External Exposure Affected areas? Radio-nuclides? Contamination?

Decision support system RODOS Pre-Release Source-term, atmospheric dispersion, deposition conditions During cloud passage Source-term, atmospheric dispersion, deposition conditions Measured data: Air activity, dose rate, in situ gamma-spectrometry Atmospheric Dispersion Deposition Aquatic transport Transfer process (food) Dose Module

Decision support system RODOS After cloud passage Finished atmospheric dispersion and deposition process Deposition Dose rate in situ gamma-spectrometry Dose module Prognostic data for activities deposited on ground are replaced by measured data Dose reconstruction method (Data assimilation techniques) Module calculations are used to assess doses (ingestion, external exposure) from the activities deposited on ground

Ground Contamination Tool M1 Deposition mapping by dose rate and in situ gamma spectrometry data Main purpose of the Ground Contamination Tool is the determination of ratios between ADER and relevant radionuclides at those locations where both, ADER and nuclide specific information is available. This allows to estimate the nuclide specific concentration at locations where only ADER is measured. Shortly after cloud passage phase, the method enables large area contamination mapping Step 1: Supporting points (ADER and insitu data from measurements): Net dose rate: ADER Activity on ground for nuclide i (from in situ data): AG(i) Nuclide vector: f(i)= AG(i) / {ADER ADER(BG)} Step 2: Interpolation points (only at locations where ADER data are measured) Spatial interpolation of nuclide vector f(i) Net dose rate: ADER (derived from measured dose rate) Assessment of activity deposited on ground AG(i) = f(i) {ADER ADER(BG)}

Ground Contamination Tool M1 IMIS exercise with simulated data For monitoring stations: Simulated net dose rate For locations with 50 real measurements: Simulated I-131 activity

Ground Contamination Tool M1 IMIS exercise with simulated data Correlation of net dose rate and activity deposited on ground Assessed I-131 Activity I-131: ~100 kbq/µsv/h Cs-137: ~10 kbq/µsv/h The method enables timely large area contamination mapping in the first days after an accidental release event

Ground Contamination Tool M2 Integration of aero gamma data Aero gamma spectrometry (2 BfS Systems) 4 x 4 l NaI-Detectors HPGe detectors Contamination in rural areas About 50 km 2 / flight hour LLD ~ 5 kbq/m 2 Cs-137 Data from C. Strobl, M. Thomas In combination with method M1 applied for: Areas near release or with small scaled contamination patterns (wet deposition)

Ground Contamination Tool M3 Integration of vehicle based dose rate data Vehicle based dose rate measurements (6 BfS Systems) mobile teams with plastic scintillator measured dose rate every second position detection via GPS natural background rejection algorithm Contamination in urban areas About 30 km per unit and hour Dose rate ~ 0.1 µsv/h Activity ~ 20 kbq/m 2 Cs-137 + Cs-134 In combination with method M1 applied for: Urban areas near release or with small scaled contamination patterns (wet deposition) Measurement exercise June 2014: Vehicle based dose rate + in situ gamma spectrometry data

Expected dose rate range and nuclides Simulated dose rate using RODOS and German release scenarios Release Bq I-131 Cs-137 after h FKA 3 10 17 3 10 16 21 FKF 2 10 16 3 10 14 57 FKI, FKH 3 10 15 3 10 11 57 Maximal dose rate [msv/h] Weather Source term Wind direction 106 m 285 m 1010 m 2040 m 1 m/s B FKA 657 327 71 26 FKF 5,9 3,9 1,2 0,57 FKI 0,62 0,59 0,39 0,30 5 m/s C FKA 3,0 46 29 12 FKF 0,18 2,90 2,0 0,77 FKI 0,01 0,12 0,69 0,42 3 detectors in the vicinity of NPP to get early spectrometric information see R&D project DETECT

EP+R exercise Core-2014 RODOS: Effective dose (7d) Realistic weather conditions Filtered venting scenario Simulated net dose rate Operational Zones: 2, 10, 25 km intervention levels Countermeasures (OIL) for dose rate: Evacuation: 5 km zone 1000 µsv/h Shielding 100 µsv/h Pre-distribution of stable Iodine Net dose rate: Cloud passage Deposition Excess dose

EP+R exercise RODOS: Effective dose msv NNP Grohnde, real weather from Severe core melting accident 2015-04-08 08:00 FKA scenario Locations of monitoring station (blue) Central and middle zone (5 + 20 km) Inhabitants of towns (red) Additional: FKI and FKF scenario

Source term reconstruction method Data assimilation & inverse Modelling R+D project: Principle of the method Input Data Weather data in the environment of the nuclear facility (past for inverse calculation and future for prognosis). A priori source term: Rough estimation of a source term with bandwidth, using information about the plant and the incident, if available (so called a priori data). Time dependent measurements of dose rates or nuclide specific activity concentrations in the atmosphere or on ground in the environment of the radioactivity emitting nuclear facility. Bayes method Output: A posteriori source term

Source term reconstruction method Data assimilation & inverse Modelling R+D project: Principle of the method Status: Module for calculating the a priori source term Method for radionuclide concentrations (dose rate) Module for analyzing the a posteriori source term Sensitivity studies by use of simulated source term Spectrometric probes in the vicinity of NPP to get early information

Spectrometric probes: General requirements Sensitivity (LLD) 1kBq/m 2 : dose rate: ~1nSv/h above background Energy resolution: Fukushima like spectra: energy resolution < 2.0 % @ Cs-137 Maximum dose rate: From RODOS simulations ADER in the vicinity of NPP up to 1000 msv/h CdZnTe 2 CdZnTe detectors LaBr3 Maximum dose rate range of microspec (CdZnTe) Volume Max ADER Peak/ mm3 msv/h Compton 1500 4 8.3 1000 8 7.5 500 12 6.6 60 100 5.3 14 400 4.4 5 900 4.3 1 3500 2.6

Calibration experiment SSDL Neuherberg LaBr3 probe (Saphymo) CdZnTe probe (Prototype BfS) Cs-137: 0,1 to 1000 µsv/h µsv/h CS1 0,119 CS2 1,293 CS3 12,27 CS4 121,81 CS5 1098

Introduction of spectrometric ADER detectors at BfS LaBr3 detector 4 km from French NPP Fessenheim 3/2015 LaBr3 System Field test with up to 6 CdZnTe protoypes

Comparison of different spectroscopy ADER probes during RANET-2014 Workshop in Fukushima A B C F D E

Comparison between insitu (HPGe) and spectroscopy ADER (LaBr3) probes RANET-2014 Workshop Fukushima

Ground Contamination Tool RANET-2014 Workshop Fukushima Ground Contamination Tool applied for Cs-137 and Cs- 137 in the Fukushima Daichi area

Ground Contamination Tool RANET-2014 Workshop Fukushima Ratio Cs-137/ADER = 210363 Bq/m 2 / msv/h (relaxation length 1cm)

Summary and outlook Combination of dose rate data and spectrometric information is very helpful For dose reconstruction methods in the early phase For source term reconstruction methods Combination data from stationary systems and from mobile teams is needed Spectrometric dose rate probes with energy resolution of 2 % have the potential to improve the needs of emergency preparedness BfS is able to share experience with spectrometric dose rate probes

Thank you! INTERCAL Long term inter-comparison experiment Mount Schauinsland near Freiburg Questions? mbleher@bfs.de