A Sensor Based On Plastic Scintillator for Alpha, Beta and Gamma Monitoring in Liquid Effluents A.Tarancón 1, J.F.García 2 and G. Rauret 1 1 Departament.

Slides:



Advertisements
Similar presentations
LOCAL IPP REGULATIONS SEWER USE ORDINANCES Sandra Diorka Director of Public Services Delhi Charter Township.
Advertisements

Liquid Scintillation Counting as multi-nuclide screening method
Liquid Scintillation Counter And Contamination Monitoring Training Presented by: Ali Shoushtarian Office of Risk Management October 2009.
Pagina 1 de 3 CEPSA Química QUIMICA Palos de la Frontera Jul 12 th, 2012 CEPSA QUIMICA PALOS DE LA FRONTERA IPPC DEVELOPMENT.
Supervised Normalized Cut for Detecting, Classifying and Identifying Special Nuclear Materials Yan T. Yang Barak Fishbain Dorit S. Hochbaum Eric B. Norman.
Surface Sensitive Bolometers (SSB): last development MARISA PEDRETTI INFN - Milano.
1 Chapiter 7 (part II-2) Isabelle Majkowski SCK●CEN Isabelle Majkowski, SCK●CEN and chapter 7.
1 Introduction USG – 573 RMDS - Radioactive Material Detector System.
1 Anil Gupta, 2 Sonali Bhade, 2 P. J. Reddy, 1 P. K. Kale, 1 K. Narayanan Kutty, 2 D.A.R. Babu, 1 R. G. Purohit and 1 Dr. P. K. Sarkar 1 Health Physics.
ACADs (08-006) Covered Keywords Efficiency, LLD, CPM, DPM, relative efficiency, absolute efficiency, standard deviation, confidence, count time. Description.
Abstract The Large Underground Xenon (LUX) dark matter detector will use a water shield to reduce background events in the detector. However, a high radon.
Real-Time Activity Monitoring of Inpatients Miguel Reyes, Jordi Vitrià, Petia Radeva and Sergio Escalera Computer Vision Center, Universitat Autònoma de.
The Detection of Radioisotopes Using a Thin Scintillating Fiber in a Spiral Adam Jernigan and Eric Blue Advisor: Dr. Thomas Dooling The University of North.
Screening of Urine Bioassay Samples using a Standard Nuclear Medicine Gamma Camera Chris Martel Director, RSO Brigham & Women’s Hospital Associate in Radiology.
PROCESS INTEGRATED DESIGN WITHIN A MODEL PREDICTIVE CONTROL FRAMEWORK Mario Francisco, Pastora Vega, Omar Pérez University of Salamanca – Spain University.
EXPRESS DETERMINATION OF SR-90 IN DIFFERENT OBJECTS WITH DICYCLOHEXYL-18-CROWN-6 (DCH18C6) EXPRESS DETERMINATION OF SR-90 IN DIFFERENT OBJECTS WITH DICYCLOHEXYL-18-CROWN-6.
MUON FLUX MEASUREMENTS AT THE LSC JRA1-N2 Meeting, Zaragoza, Nov 23 rd 2007 Héctor Gómez Maluenda, University of Zaragoza.
Mechanical and fluidic integration of scintillating microfluidic channels into detector system 1 Davy Brouzet 10 th September 2014.
Korea Hydro & Nuclear Power Company Seulki Kim
Measurement of Kr background in the XMASS experiment ICRR master’s course in physics Keisuke Hieda 1.
Assement of radionuclide concentration in various samples by gamma spectrometry and LSC J. Berzins, D.Riekstina, O. Veveris Institute of Solid State Physics.
IAEA International Atomic Energy Agency Assessment of External and Internal Exposures Michael Hajek Radiation Safety and Monitoring Section Division of.
PV plant in Campardo Landfill how to put together several municipalities in a joint project PVPP linked to the lighting systems Alessandro ing CHIES Veneto.
Analytical capability of neutron sensor incorporated into UNCOSS ROV Project meeting and workshop: Dubrovnik 30th November and 01st December 2011.
AUTOANALYZER T. Elsarnagawy 22/12/ Elsarnagawy, MASH
Printed by The River Falls Cerebral Muon Sensor Project David Schick, James Anderson, Seth Matucheski, Elizabeth Denkinger University.
A screening facility for next generation low-background experiments Tom Shutt Laura Cadonati Princeton University.
The Radionuclides Rule Analytical Issues and Considerations John Griggs U.S. EPA Office of Radiation and Indoor Air National Air and Radiation Environmental.
Nuclear Power Regulatory Overview The Keys To Our Success By Bob Wills RRPT GEL Laboratories, LLC.
Chapter 32 Radiochemical Methods. Introduction… Radiochemical methods tend to be labor intensive and generate liquid waste due to the chemical separations.
Workshop for Underground experiments and astroparticle physics 1 Radon Environment of Underground Experiment and Detection of Radon Lee, Myeong.
The National Standard of the Radionuclides Activity Unit in Poland R. Broda, A. Chyliński, T. Radoszewski, K. Małetka, T. Terlikowska-Droździel Radioisotope.
Developments in Environmental Radiochemistry* Environmental Radioactivity Measurement Facility Department of Oceanography Florida State University Tallahassee,
Distribution of radionuclides in soils in surroundings of Bratislava, capital of the Slovak Republic. II. Man-made radionuclides Mátel Ľ., Rosskopfová.
Mechanical and fluidic integration of scintillating microfluidic channels into detector system 1 Davy Brouzet 10 th September 2014.
IRAD 2371 Week 3.  Very few detectors will count every interaction  Each detector will have its own counting efficiency  Eff=CPM/DPM  Can use efficiency.
Development of a Gamma-Ray Beam Profile Monitor for the High-Intensity Gamma-Ray Source Thomas Regier, Department of Physics and Engineering Physics University.
X. Li, W. LiuICC May 11, 2003A Joint Layer Design Smart Contention Resolution Random Access Wireless Networks With Unknown Multiple Users: A Joint.
KM3NeT Pylos meeting, April, 2007 Some preliminary studies for the positioning calibration of KM3NeT Miguel Ardid Universitat Politècnica de València.
Limit of detection, limit of quantification and limit of blank Elvar Theodorsson.
Medical applications of particle physics General characteristics of detectors (5 th Chapter) ASLI YILDIRIM.
Emission source sampling and monitoring Topic 6 Ms Sherina Kamal May
Double Chooz Near Detector Guillaume MENTION CEA Saclay, DAPNIA/SPP Workshop AAP 2007 Friday, December 14 th, 2007
Linear Programming Water Resources Planning and Management Daene McKinney.
On-line Actinide Quantification with Extractive Scintillating Resins Timothy A. DeVol, James E. Roane, Lara D. Hughes Clemson University Eichrom Users’
HP SURVEY INSTRUMENT CALIBRATION AND SELECTION PRINCIPLES OF RADIATION DETECTION AND QUANTIFICATION CHAPTER 5 – REVIEW AND SUMMARY January 13 – 15, 2016.
A Brief Overview of the Radioprotection Activities in the Joint Research Centre Ispra - Italy Nina JUDGE * and Francesco D’ALBERTI ** * Medical Service.
1 LTR 2004 Sudbury, December 2004 Helenia Menghetti, Marco Selvi Bologna University and INFN Large Volume Detector The Large Volume Detector (LVD)
Chapter 1: Introduction Analytical Chemistry Analytical Chemistry Qualitative analysis Qualitative analysis Quantitative analysis Quantitative analysis.
Heterogeneous photocatalytic TiO 2 process was selected to study the degradation of the pharmaceutical pollutants sulfamethoxazole and ibuprofen. TiO 2.
Kinetic Methods. Rates In order to use a reaction for analytical purposes, the reaction must have a rate slow enough to measure but fast enough to get.
Nuclear Medicine Instrumentation 242 NMT 1 Dr. Abdo Mansour Assistant Professor of radiology
Monitoring of phosphate in natural waters by using an automated multi-pumping pulsed flow system with spectrophotometric detection Marta F. T. Ribeiro.
1 Alushta 2016 CROSS SECTION OF THE 66 Zn(n,α) 63 Ni REACTION at CROSS SECTION OF THE 66 Zn(n, α) 63 Ni REACTION at E n = 4.0, 5.0 and 6.0 MeV I. Chuprakov,
Copyright INVESTIGATION THE FLOW BEHAVIOR OF CONTINUOUS PULPING DIGESTER USING RADIOTRACER TECHNIQUE TO OPTIMIZE THE OPERATING CONDITIONS (Paper.
Low background Alpha/Beta Product Line
Svitek Jaroslav, Bohunice NPP, Slovak Republic
Fast neutron flux measurement in CJPL
SoLid: Recent Results and Future Prospects
M.I. Abbas - Alexandria University - EGYPT.
Thermo RadEye GX, SX, and PX with Various Detectors
Medical Electronics - K.Srinivasamoorthi
David Orr Assessing Radon Exposures from Materials Containing Naturally Occurring Radioactive Material (NORM) David Orr
大強度
Using ultrasonic liquid extraction for estrogens analysis in sludge by HPLC with fluorescence detection Vitória Lourosa, Diana Limab, Jorge Leitãoc, Valdemar.
Nuclear Power Regulatory Overview
Elsarnagawy, MASH Autoanalyzer T. Elsarnagawy 22/12/1432.
Recent check of calibration across detectors
Korea Hydro & Nuclear Power Company Seulki Kim
Radiochemical Methods
Presentation transcript:

A Sensor Based On Plastic Scintillator for Alpha, Beta and Gamma Monitoring in Liquid Effluents A.Tarancón 1, J.F.García 2 and G. Rauret 1 1 Departament de Química Analítica, Facultat de Química. Universitat de Barcelona. Av/ Diagonal 647, Barcelona 2 Departament de Pintura, Facultat de Belles Arts. Universitat de Barcelona. C/ Pau Gargallo 4, Barcelona (Spain) Channels SENSOR SIGNAL CARACTERIZATION (B-A) Parameter is obtained by applying the second derivate to the signal profile: δ 2 Bq/δV 2 =0 SIGNAL PROFILE (0.2, 1, 4, 10, 14 and 20ml) SPECTRA Different pulse volumes (P.V.) (0.2ml to 60ml) of 90 Sr90Y, 134 Cs and 240 Pu were loaded into the sensor (flow = 0.5ml/min) QUALITY PARAMETERS Time (s) Eff(%) or Counts(Bq) LIMIT OF DETECTION (L.O.D) WILL IMPROVE DRASTICALLY IF ALPHA-BETA DETECTOR AND GAMMA DETECTOR ARE MEASURED IN COINCIDENCE ACKNOWLEDGEMENTS: The authors thanks the CICYT for Financial support: PPQ BIBLIOGRAPHY - Patent Applications nº P : Sensor Radioquímico para fluidos. A. Tarancón, J.F. García y G. Rauret - Development of a radiochemical sensor for liquid effluents. Part I. A. Tarancón, J.F. García y G. Rauret. Analytica Chimica Acta 538 (2005) Development of a radiochemical sensor for liquid effluents. Part II. A. Tarancón, A. Padró, J.F. García y G.Rauret. Analytica Chimica Acta 538 (2005) CONCLUSIONS The radiochemical sensor can be applied to the DETERMINATION ON- LINE, REMOTELY, AND CONTINUOUSLY OF ALPHA, BETA, AND BETA-GAMMA RADIONUCLIDES included in liquid effluents. Relative errors for 90 Sr/ 90 Y and 134 Cs in the alpha-beta receptor are lower than 10% for contamination volumes higher than 5 ml. For 240 Pu relative errors are less than 15%. For 134 Cs in the gamma receptor similar values were obtained. RESULTS WILL IMPROVE WITH NEW DESIGNS ADAPTED TO SPECIFIC PROBLEMS Counts(Bq) ACTIVITY QUANTIFICATION Activity 25 Bq/ml Activity 141 Bq/ml Activity 338 Bq/ml Relative Error (%) 7 ml 12 ml 7 ml ACTIVITY QUANTIFICATION Activity 97 Bq/ml Activity 262 Bq/ml Activity 282 Bq/ml Relative Error (%) 12 ml ACTIVITY QUANTIFICATION Activity 12 Bq/ml Activity 21 Bq/ml Relative Error (%) 8 ml 14 ml 3 Bq/ml 90 Sr 90 Y in the ALPHA-BETA DETECTOR 134 Cs in the GAMMA DETECTOR 134 Cs in the ALPHA-BETA DETECTOR 240 Pu in the ALPHA-BETA DETECTOR ACTIVITY QUANTIFICATION Activity 94 Bq/ml Activity 383 Bq/ml Activity 542 Bq/ml Relative Error (%) 7 ml 12 ml The Sensor was calibrated to modelize the relationship between detection efficiency and the volume loaded (P.V.) versus de (B-A) parameter. Then it was applied to quantify the activity an the volume of a serie of unknown contamination pulses of different volume and activity ACTIVITY DETERMINATION OF UNKNOWN SAMPLES Relative errors increase when pulses lower than 5ml are quantified. VOLUME QUANTIFICATION Activity 97 Bq/ml Activity 262 Bq/ml Activity 282 Bq/ml Relative Error (%) 7 ml 12 ml VOLUME QUANTIFICATION Activity 95 Bq/ml Activity 383 Bq/ml Activity 542 Bq/ml Relative Error (%) 7 ml 12 ml VOLUME QUANTIFICATION Activity 141 Bq/ml Activity 338 Bq/ml Relative Error (%) 7 ml 12 ml 25 Bq/ml VOLUME QUANTIFICATION Activity 3 Bq/ml Activity 12 Bq/ml Activity 21 Bq/ml Relative Error (%) 8 ml 14 ml P.V. (ml) Time (s) Efficiency (%) Background (Bq) L.O.D. (Bq/ml) 90 SR 90 Y in ALPHA- BETA DETECTOR · Pu in ALPHA- BETA DETECTOR Cs in GAMMA DETECTOR INTRODUCTION On-line radioactivity monitoring in liquid effluents is an increasing need according to the present international regulations. Classical activity determination procedures include the sequence of sampling, chemical treatment, measurement and data treatment. These steps are man-power consuming, generate a great amount of waste and introduce an important delay between the potential pollution event and its detection and quantification. To overcome these limitations, we have developed a RADIOCHEMICAL SENSOR (PATENT PENDING Nº:P ) for liquid effluents capable to send information about the specific activity and volume of a contamination episode to a remote position, on line and continuously. The sensor developed is capable to detect and quantify the contamination pulses of alpha, beta and gamma emitters of different volumes and activity levels included in a continuous stream. SENSOR DESCRIPTION AND OPERATION The sensor patented is composed of two parts: Receptor and Transductor. Receptor is made of plastic scintillator. It is divided in two concentric cylinders: the internal ALFA-BETA DETECTOR and the external GAMMA DETECTOR. A modified 1414 Liquid Scintillation detector was used as transducer. A peristaltic pump introduce the effluent into the sensor. Two bundles of optical fibers connect each part of the sensor with the transducer. Both detector were not measured simultaneously. SIGNAL DETECTED IN THE ALFA- BETA DETECTOR: BKG+ γ +β + α SIGNAL DETECTED IN THE GAMMA DETECTOR: BKG+ γ