Characterization of Large Structures & Components

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

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

Application Note. InSpector 1000-based CZT Package for Nuclear Power Plant Isotope Mix Analysis

Non-Destructive Assay Applications Using Temperature-Stabilized Large Volume CeBr Detectors 14277

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

ISOCS / LabSOCS. Calibration software for Gamma Spectroscopy

RMCC CANBERRA Latest developments

IdentiFINDER Digital Hand Held Spectrometer & Dose Rate Meter for Portable Applications

Application Note. In Situ Gamma Spectroscopy with ISOCS, an In Situ Object Counting System

U & Pu assay Systems and Expertise

Model S573 ISOCS* Calibration Software

IPNDV Working Group 3: Technical Challenges and Solutions Nuclear Material (3) Technology Data Sheet

Applied Nuclear Science Educational, Training & Simulation Systems

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

THE USE OF IN-SITU GERMANIUM GAMMA SPECTROSCOPY TO FIND, IDENTIFY, LOCALIZE, AND QUANTIFY HIDDEN RADIOACTIVITY

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

Frazier L. Bronson CHP Canberra Industries, Inc., Meriden, CT USA ABSTRACT

Characterization Survey Techniques and Some Practical Feedback

THE USE OF THREE DEDICATED NUCLEAR MEASUREMENT TOOLS FOR D & D OPERATIONS IN NUCLEAR FACILITIES

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

In-Situ Characterization of Underwater Radioactive Sludge

Recent improvements in on-site detection and identification of radioactive and nuclear material

RADEAGLET. Lightweight Handheld Radioisotope Identification Device

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

TRAINING IN EXTERNAL DOSIMETRY CALCULATIONS WITH COMPUTATIONAL CODES

PYCKO SCIENTIFIC LIMITED

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

Methods for radiological characterisation

New happenings in gamma spectroscopy data analysis Sylvie Ward Sales Support Specialist

General Overview of Radiation Detection and Equipment

Estimation of Radioactivity and Residual Gamma-ray Dose around a Collimator at 3-GeV Proton Synchrotron Ring of J-PARC Facility

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

NGN PhD Studentship Proposal

NORM Monitor-IS. Performance data

Detection efficiency of a BEGe detector using the Monte Carlo method and a comparison to other calibration methods. Abstract

1. Introduction. Etim I.P. 1, William E. S. 2, Ekwe S.O. 3. Licensed Under Creative Commons Attribution CC BY

FoodScreen Radiological Food Screening System

Geostatistical characterisation of contaminated metals: methodology and illustrations

Distance from the face of the detector to the surface of the item being measured.

Calibration of a Whole Body Counter and In Vivo measurements for Internal Dosimetry Evaluation in Chile, Two years experience.

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

Natural Radiation Map of the Sudan

Journal of Radiation Protection and Research

Practical Solutions to Radioactive Waste Characterization

LAGUNA VERDE NPP DAW DRUMS CLASSIFICATION

Residual activity (contamination) Radiation exposure levels

Gabriele Hampel 1, Uwe Klaus 2

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

PINS3-CF. Portable Chemical and Explosive Identification System

Gamma-Spectrum Generator

Journal of American Science 2013;9(12)

NUCL 3000/5030 Laboratory 2 Fall 2013

An Unmanned Aerial Vehicle-based Radiation Surveillance System. Seungwoo Lee Korea Electronics Technology Institute

1. What would be the dose rate of two curies of 60Co with combined energies of 2500 kev given off 100% of the time?

Applied Nuclear Science Educational, Training & Simulation Systems

1. General information and technical data of TAPIRO research reactor

RADEAGLE. Next Generation Radioisotope Identification Device. Detection and Identification: Fast, Accurate and Easy

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

IDENTIFICATION AND QUANTIFICATION OF RADIONUCLIDES IN HISTORICAL WASTE AT ANSTO

Characterization of radioactive waste and packages

RPR 29 CYCLOTRON RADIOCHEMISTRY LABORATORY

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

Alpha-energies of different sources with Multi Channel Analyzer (Item No.: P )

Renewed whole-body counting chamber in STUK

Ringhals AB. Routines for whole body counting at Ringhals NPP

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

European Project Metrology for Radioactive Waste Management

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

Radioactive Waste Management

Activities at the Laboratory of the Nuclear Engineering Department of the Polytechnic University of Valencia

M E E T I n s t r u m e n t s G.m.b.H.

WM2013 Conference, February 24 28, 2013, Phoenix, Arizona USA. Screening and Spectral Summing of LANL Empty Waste Drums 13226

ACTA PHYSICA DEBRECENIENSIS XLI, 29 (2007) ADVANCED METHODS OF RADIATION DETECTION FOR THE SAFETY OPERATION OF NUCLEAR POWER PLANTS.

Rapid Gamma Screening of Shipments of Analytical Samples to Meet DOT Regulations

1 Introduction. 2 Method. Robert Metzger 1,*, Kenneth Van Riper 2, and George Lasche 3

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

Activity Concentrations and Associated Gamma Doses of 238 U and 235 U in Jordan

Clearance Monitoring. Chris Goddard.

Alpha-Energies of different sources with Multi Channel Analyzer

Establishing an ISO-CART Measurement Station to Meet Government Burial Regulations for Radioactive Material

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

RADIOACTIVE WASTE CHARACTERIZATION IN BELGIUM. Tractebel Ariane Avenue, 7 B-1200, Brussels, Belgium ABSTRACT

Materials and waste characterisation Dealing with difficult waste

A Radiation Monitoring System With Capability of Gamma Imaging and Estimation of Exposure Dose Rate

Methodologies and tools developed by CEA/SAS

Radiometric Measurements of Environmental Radioactivity

Geostatistics for radiological characterization: overview and application cases

ACTIVATION ANALYSIS OF DECOMISSIONING OPERATIONS FOR RESEARCH REACTORS

Methods to identify and locate spent radiation sources

Pete Burgess, Nuvia Limited. Clearance and exemption

Mobile Unit for Site Characterization: Results of a Demonstration Event

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

1 General information and technical data of TRIGA RC-1 reactor

Michael G. Stabin. Radiation Protection and Dosimetry. An Introduction to Health Physics. 4) Springer

RADIATION SAFETY. Working Safely with Radiation

Introduction to Environmental Measurement Techniques Radioactivity. Dana Pittauer 1of 48

Virtual Gamma-ray Spectrometry for Template-Matching Nuclear Warhead Verification

WM2012 Conference, February 26 March 1, 2012, Phoenix, Arizona, USA. Segmented Gamma Scanner for Small Containers of Uranium Processing Waste

GT-40/GT-40S Multipurpose Gamma-Ray Spectrometer Ancestors: GS-256 by Geofyzika Brno 1975 GR-256 by Exploranium Canada 1977 GR-320 by Exploranium

ISO INTERNATIONAL STANDARD

Transcription:

Structures & Components KEY BENEFITS Key Drivers: Lack of good knowledge about the position, the identification and the radiological specification of contamination on or inside large components. Significant high global background, within relatively medium activities of components. The identification and estimation of the activity become complex in hot cells, where space is limited and human intervention difficult as per ALARA principles. Achieve accurate measurements, but also activities per radionuclide, and localization of hot spots. Objectives: Identify the activity of hot spots or contaminated surface using gamma imaging and spectroscopy. Perform mobile real-time position measurement. Modeling of many types of contaminated surfaces or components. Control cost and risks of the total project Source-Less calibration with ISOCS Optimized Waste Segregation Immediate, easy and accurate source-less calibration measurements. Reduce costs, time and risks of measurement. Release of structures and components materials without cutting them. TM Expertise for Challenging Measurements CANBERRA can customize the solution based on the unique requirements of the situation. All the solutions offered in this flyer can be thoroughly performed by our Measurements & Expertise (M&E) team, without any purchase of products or systems.

ipix Gamma Imager: Real-time Monitoring & Hot Spots Localization ipix is a unique gamma imager that quickly locates low level radioactive sources from a distance while estimating the dose rate at the measurement point in real time. It is the ideal tool to map a radioactive area before entering the zone, thus reducing the dose exposure (ALARA) for the workers. Due to the use of the coded masks, the need for heavy shielding has been eliminated, making it a compact and lightweight (~2.5 kg) system. ipix is an excellent tool to precisely locate the radioactive source position. Knowing the position helps to improve the activity calculation correctly when using ISOCS. Best tool to track low energy emitters. Industrial design for use in harsh environments (IP65). Can be operated remotely minimizing exposure to the operators (ALARA). User friendly, with push button image acquisition. High performance to quickly and precisely locate hot spots. Estimates dose rate at the measurement point. ipix allows localization of radioactive sources in many kind of nuclear plant components, building, pipes, drums, scraps, etc Lead shielding Lightweight unit can be deployed and transported in the field. ISOCS Measurement In Situ Object counting Systems (ISOCS) is commonly used to measure contaminated materials and areas, both in place or after removal from the facilities, also for final status measurement to the clearance. HPGe detectors have the best FWHM resolution in gamma spectroscopy and allow fastest specific nuclide identification, even with complex spectra. NaI detectors have a good efficiency for very low activity determination of simple nuclide mixes. CZT detectors are small but have a better energy resolution than NaI detectors. Key benefits Immediate, accurate, nuclide-specific results for in-situ measurements of any object or surface. Source-Less detector-specific calibrations generated by software as the sample is being calibrated. All calibrated objects/surface are usually plane, cylinder, box, sphere, well/marinelli or pipe. Mobile detector positioning device includes 25 mm, 50 mm collimators (for HPGe detectors) and backshields. It accommodates any detector orientation. Custom-designed collimators can also be used. Complex pipe template allows modeling of complex, multi-layer pipes and drums. Allows modelling of In depth profile contamination. Wide range of detectors (HPGe, NaI, CZT, LaBr) compatible, allowing operation for range of applications and activities. Use of Advanced In-situ Gamma Spectrometry (AIGS) Services to optimize waste segregation by improving assay accuracy (for example when activity is inhomogeneous). Dose rate of 3 msvh NPP Example Setup and Control of Radiobiological Protection Pipelines Unshielded transport container 2

Dose rate measurement + mapping CANBERRA offers dose rate meters for a wide range of users and probes to suit many applications. All CANBERRA Smart Probes can be plugged to CANBERRA s family of Smart survey meters. A GPS survey meter is available to identify the position of measurements and give a real time measurement of dose rate and gamma spectra simultaneously. Up to 7 probes can be wirelessly connected to the same Colibri CSP-COM Colibri COLIBRI Communication ALARA Platform LynxNavi is a software developed for supporting all acquisition modes proposed by the CANBERRA high performance multi-channel analyzers (MCA) using NaI to obtain gamma spectra and with high performance analysis. STTC Energy compensated G-M Detector Wide range H*(10) dose rate equivalent to ICRP-60 LynxNavi used with Osprey CANBERRA uses its unique Time-to-Count technique with many of its Geiger Mueller detectors. CANBERRA supplies many detectors that are appropriate for different levels of dose rate measurement, giving 3D mapping of dose rate and gamma energy on a large surface. Colibri is equipped with a GPS system, giving an accurate mapping of a large surface. 3

Plant components contamination Object internal surface contamination by simulation: dose rate probe + ISOCS + MERCURAD + MCNP codes Objectives: Characterization of high dose rate contaminated surface (on the pipes, tanks, walls, etc ) in limited access areas inside a plant. Characterization of waste level of components to define the best dismantling scenarios and safety analysis. Method: Step 1 Assessment of the status of the areas or objects. Review the plant s operational history. Evaluate where the potential contamination areas or hot-spots are located. Step 2 After evaluation of the dose rate, depending on accessibility, drill holes or directly use the suitable detectors (GM, CZT, etc ) in different positions, thus accurately obtain the dose rate. Step 3 ipix deployment to locate the positions of hot spots. Step 4 Simulation of the whole detection system and the components or areas using ISOCS or MERCURAD* and MCNP software, insert the dose measurement data to evaluate the activity of the contaminated hot-spots. Case study: La Hague reprocessing plant This project covered a very large range of dose rates from 100nGy/h to 100Gy/h. To reduce cost, save time, minimize dose and avoid opening hot cells and cutting tanks, systems at La Hague reprocessing plant were evaluated by simulation code to determine the positions of contaminated areas. The objective of this project was totally achieved. We proved that more than 50% of the tanks could be considered as very low level waste. It drastically changed the previously envisaged decontaminating and dismantling process. * MERCURAD software, offers a practical solution to meet the complex dose calculation requirements of health physics specialists, shielding calculation engineers, and staff involved with nuclear facility maintenance and nuclear installation dismantling projects. 4

Surface contamination Activity measurement: Method Locate the contaminated source (using gamma imaging system and/or Geiger Muller detectors). Use spectrometer (HPGe, CZT, NaI or LaBr, etc.) to obtain gamma spectrum of the hot spot(s). Use ISOCS template to obtain the geometry detection efficiency (Gamma attenuation calculation code). The gamma spectrum will be analyzed using spectroscopy code (Genie 2000), combining the detection efficiency from the ISOCS template and eventually deducing the activities of the contamination / source(s). Advanced In-situ Gamma Spectrometry (AIGS) Services can greatly improve the accuracy of activity results based on ISOCS. Overview of the activity calculation Geometry of the scene Location of sources Gamma attenuation calculation code Geometrical efficiency Ge Spectrum Activities Detector efficiency Measurement Model HPGe detector Final Result AIGS (Advanced In-situ Gamma Spectrometry) Services It allows testing the sensitivity of model s parameters, such as geometry, material, shapes, etc and optimizing these to fit available measurement data. For example it allows fitting of source geometry to match multiple measurements, thereby improving accuracy if source distribution is unknown. 5

Surface contamination Case Study: Bulk Waste Characterization with ISOCS, and Verification with samples having well-known activities Figure 1 shows the measurement of contaminated soil from a shutdown nuclear power plant. A container full of soil sample was measured using a HPGe detector which was inserted inside a lead collimator. The detector efficiency was calculated with ISOCS template as shown in figure 2. The ISOCS in-situ measurement of this sample was obtained, and compared to the sample dose rate as shown in the figure 3. The blue points represent the ratio between the two values, and the data match very well. Figure 1 Figure 2 Figure 3 6

Plant components contamination CANBERRA has the expertise to successfully characterize large surfaces and plant components. These projects have been achieved leading to costs and time reductions for customers. Characterization of heat exchangers for free release at Seabrook NPP (USA). Using ISOCS to characterize a crane in nuclear plant in US, demonstrating the capability to characterize massive objects. Characterization of pipes and tubes in nuclear plant components. 7

Successful achievements Characterization of different small irregular objects using ISOCS. CANBERRA has successfully characterized a large area full of metal scrap piles with steel tubes using ISOCS system. For more information, review the complete case study on our website: www.canberra.com/measurements-expertise Characterization of Rocky Flats Environmental Technology Site through paint Sampling and rapid gamma Spectroscopy.(C40863) Decommissioning of a medical cyclotron using ISOCS. (C48088) Large Area mapping using ISOCS and Geostatistics. (C48136) ORCADE-DV D&D Project in La Hague Reprocessing Plant, France (*C48360) Radiation Safety. Amplified. www.canberra.com C49116 06/2016