EMRP JRP ENV54 METROLOGY FOR DECOMMISSIONING NUCLEAR FACILITIES (WP2, WP3)

Similar documents
European Project Metrology for Radioactive Waste Management

Characterisation of materials present on decommissioning sites

Sampling based on Bayesian statistics and scaling factors

Publishable JRP Summary Report for JRP IND57 MetroNORM Metrology for processing materials with high natural radioactivity

Evaluation of Radiation Characteristics of Spent RBMK-1500 Nuclear Fuel Storage Casks during Very Long Term Storage

8 th International Summer School 2016, JRC Ispra on Nuclear Decommissioning and Waste Management

Proficiency Test: Non-destructive Assay of 220 liters Waste Drums by Gamma Assay Systems (an ENTRAP initiative)

Clearance Monitoring. Chris Goddard.

ENV54-MetroDecom Creating Impact (WP6)

7 th International Summer School 2015, JRC Ispra: Operational Issues in Radioactive Waste Management and Nuclear Decommissioning

Nucleonica Lab. Case Study: Characterisation of an irradiated fuel sample (UOX) from a PWR. Dr. Joseph Magill, Nucleonica GmbH, Karlsruhe

Methods for radiological characterisation

Applications of MCBEND

Metrology for Molecular Radiotherapy MetroMRT V. Smyth (coordinator) Lena Johansson, Andrew Fenwick, Kelley Ferreira et al.

GRAPHITE GAS REACTORS SLA1 & SLA2 : FROM SAMPLING STRATEGY TO WORKING CONDITIONS

C2-05: Creation of national standards for some emerging pharmaceutical radionuclides to ensure the radioprotection of patients and medical staffs

Ionizing Radiation Metrology at NMIJ/AIST and ENEA-INMRI

Characterization of Large Structures & Components

Research in NDA Techniques for Waste Characterization at the JRC

NGN PhD Studentship Proposal

*Corresponding author,

Final Publishable JRP Summary for ENV57 MetroERM Metrology for radiological early warning networks in Europe

WM2013 Conference, February 24 28, 2013, Phoenix, Arizona, USA

ACTIVATION ANALYSIS OF DECOMISSIONING OPERATIONS FOR RESEARCH REACTORS

Characterising NORM hazards within subsea oil and gas facilities. Daniel Emes SA Radiation

NEW DEVELOPMENTS OF AUTORADIOGRAPHY TECHNIQUE TO IMPROVE ALPHA AND BETA MEASUREMENTS FOR DECOMMISSIONING FACILITIES

Nucleonica Lab : An Overview of the Nuclear Science Portal with hands-on exercises

Consistency and confidence: the role of the National Measurement System

WM 07 Conference, February 25 March 01, 2007, Tucson, AZ

Characterisation of radioactive waste from nuclear decommissioning. Peter Ivanov. Acoustics & Ionising Radiation National Physical Laboratory, UK

SPentfuel characterisation Program for the Implementation of Repositories

Radiological Characterization of Buildings at the Ranstad Uranium Works

TC Thermometry Graham Machin

Question to the class: What are the pros, cons, and uncertainties of using nuclear power?

12/18/2016. Radioanalysis Laboratory Capabilities and Issues. Eleventh Annual Radiation Measurement Cross Calibration Workshop RMCC XI

Method to assess the radionuclide inventory of irradiated graphite from UNGG reactors (Uranium Naturel Graphite Gaz)

MCNP CALCULATION OF NEUTRON SHIELDING FOR RBMK-1500 SPENT NUCLEAR FUEL CONTAINERS SAFETY ASSESMENT

1. General information and technical data of TAPIRO research reactor

Acoustics and Ionising Radiation Formulation and Strategy. 13 November 2008 Alan DuSautoy

CZT Gamma Spectrometry Applied to the In-situ Characterisation of Radioactive Contaminations

DESIGN AND OPERATION OF THE COMBINED TECHNOLOGY AUTOMATED WASTE CHARACTERISATION SYSTEM

EN-TRAP. The European Network of Testing Facilities for the Quality Checking of Radioactive Waste Packages

FIRST LINE INSPECTION: RADIATION DETECTION

NUCLEONICA Overview: A WEB PORTAL FOR THE NUCLEAR SCIENCES

New methodology for source location and activity determination in preparation of repairing or decommissioning activities

TECHNICAL WORKING GROUP ITWG GUIDELINE ON IN-FIELD APPLICATIONS OF HIGH- RESOLUTION GAMMA SPECTROMETRY FOR ANALYSIS OF SPECIAL NUCLEAR MATERIAL

Digital simulation of neutron and gamma measurement devices

19:00 21:30 Registration and reception at Hotel ETAP Altinel. Welcome

SLAC Metal Clearance Program and Progress

Applied Nuclear Science Educational, Training & Simulation Systems

Development of radiochemical analysis strategies for decommissioning activities. Dr. Daniel Zapata-García Environmental radioactivity laboratory, PTB

Characterization of radioactive waste and packages

Calculation of dose rate, decay heat and criticality for verifying compliance with transport limits for steel packages

Commissioning of the Beta Secondary Standard (BSS2)

Assessment of Radioactivity Inventory a key parameter in the clearance for recycling process

The metrology of radioactivity. C. Michotte, BIPM

J. Keightley 1 P. Cassette 2, L. Johansson 1

Uncertainty Analysis for Heat-flux DSC Measurements

WM2013 Conference, February 24 28, 2013, Phoenix, Arizona, USA

NUCLEAR EDUCATION AND TRAINING COURSES AS A COMMERCIAL PRODUCT OF A LOW POWER RESEARCH REACTOR

Design of an Integrated Inspection System For Detection of Explosive and Illicit Materials

RADIOLOGICAL CHARACTERIZATION ACTIVITIES DURING THE PARTIAL DISMANTLING OF THE IRT SOFIA RESEARCH REACTOR FACILITIES

EUROMET PROJECT FINAL REPORT

Verification measurements of alpha active waste

Michigan Small Animal Imaging Resource Center for Molecular Imaging. Department of Radiology. University of Michigan

8 th International Workshop on Radiation Safety at Synchrotron Radiation Sources

Summary of the ICRM Life Sciences Working Group Meeting

Depth Distribution of H-3, C-14 and Co-60 in Decommissioning of the Biological Shielding Concrete of KRR-2

FUSION NEUTRONICS EXPERIMENTS AT FNG: ACHIEVEMENTS IN THE PAST 10 YEARS AND FUTURE PERSPECTIVES

Hands on LUNA: Detector Simulations with Geant4

Nuclear Science Merit Badge Workbook

Cross-section Measurements of Relativistic Deuteron Reactions on Copper by Activation Method

1220 QUANTULUS The Ultra Low Level Liquid Scintillation Spectrometer

Pete Burgess, Nuvia Limited. Clearance and exemption

WM2014 Conference, March 2 6, 2014, Phoenix, Arizona, USA

THE IMPLEMENTATION OF RADIOLOGICAL CHRACTERIZATION FOR REACTOR DECOMMISSIONING. China Nuclear Power Engineering Co. Ltd, Beijing , China

Radioactive Waste Management For The Ignitor Nuclear Fusion Experiment

Neutronics Experiments for ITER at JAERI/FNS

[This is not an article, chapter, of conference paper!]

DIRECT EXPERIMENTAL TESTS AND COMPARISON BETWEEN SUB-MINIATURE FISSION CHAMBERS AND SPND FOR FIXED IN-CORE INSTRUMENTATION OF LWR

Tritiated Waste Management Opportunities Based On The Reduction Of Tritium Activity And Outgassing 15607

Neutron Dose near Spent Nuclear Fuel and HAW after the 2007 ICRP Recommendations

Efficient Utilization of a Low-Power Research Reactor

EFFICIENCY CALIBRATION STUDIES FOR GAMMA SPECTROMETRIC SYSTEMS: THE INFLUENCE OF DIFFERENT PARAMETERS

Safety Assessment on the Storage of Irradiated Graphite Waste Produced from the Decommissioning of KRR-2

Nuclear data for advanced nuclear systems

ESNII + WP7 Fuel Safety

Building a Robust Numerical Model for Mass Transport Through Complex Porous Media

Activation of Air and Concrete in Medical Isotope Production Cyclotron Facilities

Results of the 2015 national indoor radon intercomparison measurements in Serbia

Verification measurements of alpha active waste

LATE PHASE OF NUCLEAR ACCIDENT IN AGRICULTURE WEAKNESSES IN DECISION MAKING DUE TO LACK OF DATA, KNOWLEDGE AND SKILL AND POSSIBLE INNOVATION

DESIGN, DEVELOPMENT AND TESTING OF AN AUTOMATED SEGMENTED GAMMA SCANNER FOR MEASURING NUCLEAR POWER STATION RADIOACTIVE WASTE

2. TC-IR Roadmap Anthropogenic and Natural Radionuclides in Environment and Industry (Lena Johansson, NPL and Bruno Chauvenet, LNHB)

Nuclear medicine and Radiation technologies

P7 Radioactivity. Student Book answers. P7.1 Atoms and radiation. Question Answer Marks Guidance

Radiation safety of the Danish Center for Proton Therapy (DCPT) Lars Hjorth Præstegaard Dept. of Medical Physics, Aarhus University Hospital

Activities of the neutron standardization. at the Korea Research Institute of Standards and Science (KRISS)

High precision neutron inelastic cross section measurements

The outermost container into which vitrified high level waste or spent fuel rods are to be placed. Made of stainless steel or inert alloy.

Transcription:

EMRP JRP ENV54 METROLOGY FOR DECOMMISSIONING NUCLEAR FACILITIES (WP2, WP3) CMI, CEA, ENEA, IFIN-HH, JRC, LNE, MIKES, NPL, PTB, SCK-CEN, STUK, ANDRA, EDF, ENVINET/NUVIA GROUP, REG(ENVINET) Jiri Suran (JRP ENV54 Coordinator) MetroDecom Workshop, 25-26 November 2015, Trebic, Czech Republic 1

Nuclear decommissioning facts Shutdown reactors and facilities (August 2013): power reactors: 89 EU, 143 worldwide research reactors: 46 EU, 142 worldwide fuel facilities: 31 EU, 96 worldwide Operating reactors and facilities (August 2013): power reactors: 137 EU, 437 worldwide research reactors: 61 EU, 246 worldwide fuel facilities: 76 EU, 332 worldwide More than one third of the 137 reactors currently operating in the EU will need to be shut down by 2025. GlobalData s report shows that the European commercial nuclear decommissioning market value stands at more than 60,000 million EUR. 2

JRP ENV54 MetroDecom benefits The key direct benefit is improvement of capacity, accuracy, reliability and mobility of the measurement, which will result in more reliable decision-making concerning safe release and safe disposal of radioactive wastes into the environment with positive economic impacts. New rapid and precise free release measurement technologies will reduce the quantity of solid waste materials incorrectly sent to repositories (including recyclable) and minimize the disposal costs by about 10%, which would lead to savings of tens of millions of Euros for the decommissioning of a single NPP (1M 3 VLLW, LLW repository = EUR 5,000-30,000). 3

MetroDecom WP2, WP3 tasks Develop traceable measurement methods for the pre-selection of wastes prior to measurement for repository acceptance or possible free release Develop and implement free release measurement technologies 4

PLASTIC SCINTILLATOR SOLUTION, RADOS RTM 644 5

PLASTIC SCINTILLATOR SOLUTION, VF FRM-02 6

IGNALINA NPP FREE RELEASE MEASUREMENT FACILITY (FRMF) 7

PLASTIC SCINTILLATOR SOLUTION, VF FRM-02B, IGNALINA NPP (FRMF) 8

GAMMA SPECTROMETRIC SOLUTION, ENVINET, IGNALINA NPP (FRMF) 9

MetroDecom waste measurement system Progress beyond the state of the art New components: Special, new, patented shielding material in the form of modular, unified, reusable, ecological segments from concrete having low natural radionuclide content thus facilitating the easy and economical creation of large, site-optimized low-background facilities (chambers, tunnels); Integrated modular detection arrays: Stirling cycle cooled gamma spectrometric compact modules, plastic scintillators total gamma modules and neutron BF3 modules that collectively facilitate site-optimized detection solutions with high sensitivity, homogeneity scanning and transportability; Integrated collimated gamma irradiator for improved scanning of wastes with heterogeneous composition and density; Special holders that enable the use of various site-specific containers and drums; Universal transport and measurement IP1 and IP2 containers optimized for safe transport and low absorption during measurement, thus eliminating waste reloading; New, universally applicable certified calibration/testing standards and reference materials that facilitate accurate, traceable measurement. 10

MetroDecom waste measurement system Progress beyond the state of the art Improved features: A standardized modular, transportable, reusable, site-optimizationenabling concept High throughput (up to 5 t/hr, 10 m3/hr) Individual detection arrays, high sensitivity and wide detection range Adaptation for segregation or free-release measurement purposes Adjustable measurement geometry (optimization for low- and highdensity materials) Comprehensive homogeneity scanning Flow through, without movable doors configuration (high throughput, safety, affordability) Radon daughters background and internal contamination reduction 11

METRORWM FRMF EXPERIMENTAL FACILITY - COMPLETED 12

METRORWM FRMF EXPERIMENTAL FACILITY - CONSTRUCTION 13

METRORWM FRMF EXPERIMENTAL FACILITY - CONSTRUCTION DETAILS 14

METRORWM AND METRODECOM SPECIAL BRICKS (OLD AND NEW TYPE) 15

METRORWM FRMF FOUR IDM-1 HPGE DETECTOR ASSEMBLY 16

METRODECOM HPGE DETECTOR IDM-200V 17

METRORWM EXPERIMENTAL FACILITY - INTERNAL DOSE RATE, VALIDATED BY PTB 18

METRORWM EXPERIMENTAL FACILITY OUT / IN SPECTRA COMPARISON 19

METRORWM EXPERIMENTAL FACILITY BACKGROUND COMPARISON 20

METRODECOM MEASUREMENT SYSTEM CONCEPT (INDUSTRIAL FACILITY) spectrometric without lead modular transportable flow through without doors adjustable detectors radon free IP1/2 containers 21

METRODECOM MEASUREMENT SYSTEM CONCEPT (INDUSTRIAL FACILITY) 22

METRODECOM MEASUREMENT SYSTEM CONCEPT (JRC ISPRA FACILITY) 23

METRODECOM MEASUREMENT SYSTEM DESIGN (SPECIAL BRICKS SHIELDING ) 24

METRODECOM DESIGN WITH METRODECOM CONTAINER AND 200L DRUM 25

METRODECOM DESIGN WITH JRC ISPRA CONTAINER AND 200L DRUM 26

METRODECOM DESIGN WITH TWO METRODECOM CONTAINERS (1M 3 TOTAL) 27

METRODECOM DESIGN, INTERNAL STRUCTURE 28

METRODECOM DESIGN, DETECTION ARRAY (4xHPGE, 4xPLASTIC, 3xNEUTRON) 29

METRODECOM WASTE MEASUREMENT SYSTEM CONSTRUCTION, TREBIC (ENVINET ) 30

METRODECOM WASTE MEASUREMENT SYSTEM MODEL 31

METRODECOM WASTE MEASUREMENT SYSTEM, JRC ISPRA (ISF BUILDING) 32

IP-1 METRODECOM CONTAINER 100x120x60CM (~0,5 M3) 33

IP-2 METRODECOM CONTAINER 100x120x60CM (~0,5 M3) 34

JRC ISPRA CONTAINER AND 200L DRUM HOLDERS 35

Scanning irradiation module design 36

MC optimization of shielding tunnel Goal: Optimization of shielding tunnel and detectors configuration chamber floor thickness thickness of shielding below conveyor belt thickness of shielding wall length of shielding wall shape of shielding wall Visualizations of the Monte Carlo model. 37

MC optimization of segregation detector array Total detection efficiency calculation for different configurations of plastic scintillators for given segregation system tunnel dimensions 4, 8, 12 detectors 3 widths of the detectors 6 different measured materials (steel, wood,...) Examples of different modelled detectors configurations 38

MC optimization of scanning irradiation module Optimize of shielding and collimator for given source-to-detector geometry of the scanning facility SELECTED open position MC model of the final design of the source shielding and a collimator. closed position Detector is in the upper part (blue), collimator and shielding in the lower part. Scanned material is in the middle (yellow). Colours: red steel blue lead green air cyan source yellowcontainer 39

MC validation of HPGe IDM-200V detector model Development of MC model and validation by comparison using 3 pcs of the detector Relative difference between measured (3 pcs of detector) and simulated detection efficiencies. 40

How to ensure benefits for stakeholders and end users? What MetroDecom WP2, WP3 outcomes offer: Improvement of capacity, accuracy, reliability and mobility of the measurement with positive economic impact Opportunities: To launch a new generation of radioactive waste monitors with special shielding in the market To take advantage of FRMF prototype and MetroDecom outcomes for establishment of training and workshop centre for EU waste management stakeholders in JRC Ispra, Italy 41

The guaranty of the correctness of the clearance process is important for all stakeholders and end users in the utilisation of radionuclides and nuclear energy.

EMRP JRP ENV54 MetroDecom ENV54 objectives and corresponding working packages cover radioactive waste metrology at all stages of the post-operational cycle, from the characterization of solid wastes, to pre-selection, free release, and monitoring within the waste repository. WP No Work Package Name Active JRP-Participants (WP leader in bold) WP1 WP2 WP3 Characterisation of materials present on decommissioning sites Measurement facility for waste segregation Implementation of free release measurement facility on decommissioning site NPL, CEA, CMI, ENEA, IFIN-HH, PTB, SCK-CEN, STUK NUVIA ENVINET, CMI, JRC, PTB, REG(NUVIA ENVINET) CMI, ENEA, NUVIA ENVINET, IFIN-HH, JRC, NPL, REG(NUVIA ENVINET) WP4 Radioactive waste repositories monitoring NPL, ANDRA, EDF, ENEA, LNE, MIKES WP5 Development of reference materials and standard sources PTB, CMI, ENEA, IFIN-HH, JRC, NPL WP6 Creating Impact ENEA, All WP7 JRP management and Coordination CMI, All 43

EMRP JRP ENV54 MetroDecom JRP Title and JRP-Coordinator contact details JRP Number JRP Short Name Full JRP Title Coordinating Organisation JRP-Coordinator ENV54 MetroDecom Metrology for decommissioning nuclear facilities Cesky Metrologicky Institut Brno Jiri Suran Address Czech Metrology Institute Inspectorate for Ionizing Radiation, Radiova 1, 102 00 Prague 10, Czech Republic Phone: +420 602366771 Email: jsuran@cmi.cz Key Dates Start date End date Duration JRP 01.09.2014 31.08.2017 36 months REG(ENVINET) 01.09.2014 31.08.2017 36 months 44

EMRP JRP ENV54 MetroDecom Financial resources Total eligible costs ( ) EURAMET contribution ( ) Unfunded JRP-Partner contribution (months) Integral REG contribution (months) 4 892 781,11 2 201 751,50 28,0 30,0 45

Radionuclide vectors & scaling factors Radionuclide vector general term, univocal definition is missing usually averaged percentage ratio of activity of radionuclides determined by analysis of waste streams samples (sometimes weighted by clearance levels and normalized) Radionuclide vectors calculated without casual correlation analysis (among radionuclides) are not representative if composition of wastes is not stable often used incorrectly for counting rate/activity conversion (non spectrometric devices) during free release measurement Scaling factor ratio between gamma emiting key radionuclides and casually related radionuclides defined by ISO standard 21238:2007 based on correlation between fissile radionuclides and activation radionuclides spectrometric measurement is necessary (activity of key radionuclides determination) IAEA Nuclear Energy Series MW-T-1.18 Determination and Use of Scaling Factors for Waste Characterization in NPPs Scaling factors spectrometric measurement 46