TLD ALBEDO DOSIMETER PERFORMANCE ON A Hp(10) NEUTRON DOSE IAEA INTERCOMPARISON

Size: px
Start display at page:

Download "TLD ALBEDO DOSIMETER PERFORMANCE ON A Hp(10) NEUTRON DOSE IAEA INTERCOMPARISON"

Transcription

1 2007 International Nuclear Atlantic Conference - INAC 2007 Santos, SP, Brazil, September 30 to October 5, 2007 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: TLD ALBEDO DOSIMETER PERFORMANCE ON A Hp(10) NEUTRON DOSE IAEA INTERCOMPARISON M. M. Martins 1,2, C. L. P. Maurício 1 and A. X. da Silva 2 1 Instituto de Radioproteção e Dosimetria (IRD / CNEN) Av. Salvador Allende, s/nº - Caixa Postal Rio de Janeiro, RJ marcelo@ird.gov.br; claudia@ird.gov.br 2 Programa de Engenharia Nuclear/COPPE/UFRJ Caixa Postal CEP: Av. Horácio Macedo, 2030, Bloco G, Sala 206 Cidade Universitária CEP: Rio de Janeiro, RJ ademir@con.ufrj.br ABSTRACT A new TLD albedo individual monitor system took part in the International Intercomparison of Personal Dosimeters for Mixed Neutron-Photon Radiation for the Quantity Personal Dose Equivalent, sponsored by IAEA from 2003 to This exercise was performed in two steps: a type test intercomparison and a simulated work place intercomparison. In Part I, the neutron individual monitors were irradiated in selected calibration fields in order to improve the dosimetric procedures of the participants. In Part II, the dosimeters were irradiated in radiation fields similar to those in workplace fields for final check of the performance. The neutron irradiations were performed at the facilities of the PTB, German, and the IRSN, France, with energies ranging from thermal to 5 MeV, on an ISO water slab phantom. The readings reported by the participants were compared with the H p (10) reference neutron values ( msv) derived with primary standards, with an uncertainty of 4.2% (k=2), at the two irradiating laboratories. Using data of Part I to improve algorithm and calibration, the new TLD albedo system has obtained 100% of results within the acceptance limits in the Part II performance test. The albedo individual monitor is also quickly described and the system performance is analyzed. 1. INTRODUCTION The neutron individual monitoring is performed with a wide variety of active and passive detectors. Since 1983, Instituto de Radioproteção e Dosimetria (IRD) runs a thermoluminescent detector (TLD) albedo-based neutron monitoring service using a onecomponent monitor [1]. Recently, a two-component albedo individual monitor has been developed [2]. In addition to the albedo component, it has an incident neutron component that enables correction in its calibration factor. In both components, TLDs are used for neutron and gamma detection. Among other requirements, its development aims a detection limit lower than the Brazilian monthly recording level (H 0 ) of 0.20 msv [3], even for bare 241 Am-Be source, which is not true for the actual routine albedo system. The new TLD based albedo system has been calibrated [2] according to international standard ISO [4]. Nowadays, it is being characterized according to ISO standard [5]. Among the sets of reference neutron radiations described in the international standard ISO [6], those from accelerator (monoenergetic) are difficult to be available. First, the new TLD based albedo system could be calibrated only in neutrons from radionuclide sources

2 because the other neutron radiation qualities are not commonly available. In 2003, a unique opportunity to access these neutron radiation fields, and test its global performance, has appeared at The International Intercomparison of Personal Dosimeters for Mixed Neutron- Photon Radiation for the Quantity Personal Dose Equivalent, sponsored by International Atomic Energy Agency (IAEA) [7]. 2. H p (10) NEUTRON DOSE IAEA INTERCOMPARISON The IAEA International Intercomparison of Personal Dosimeters for Mixed Neutron-Photon Radiation has been proposed not only as a pure performance test of the existing neutron dosimetric service. The three main objectives of this intercomparison were: 1. To assess the capabilities of the dosimetry services in measuring the quantity Hp(10) in mixed neutron-gamma fields; 2. To assist Member States in achieving sufficiently accurate dosimetry and, if necessary; 3. To provide guidelines for improvements. This exercise was performed in two steps: a type test intercomparison (Part I) and a simulated work place intercomparison (Part II). In Part I, the dosimeters were irradiated in selected calibration fields in order to improve the dosimetric procedures of the participants (Table 1). It comprises particular standard irradiation conditions, including monoenergetic beams, in order to investigate the energy and angular dependence for neutrons and to check home calibrations. In Part II, the dosimeters were irradiated in radiation fields similar to those in workplace fields for final check of its performance (Table 2). The irradiations were performed at two European facilities: Physikalisch-Technische Bundensansalt (PTB), in Germany, and Institut de Radioprotection et de Sûrete Nucléaire (IRSN), in France. The irradiation laboratories gave the reference values for neutron radiation H p (10), using wellestablished procedures. At both facilities, the conventionally true value of neutron H p (10) was measured with an uncertainty of 4.2% (k=2). Irradiations were performed on an ISO water slab phantom, except for radiation qualities 15 and 16 [7] on Part I, when individual monitors were attached on an ISO slab phantom. Some monitors were chosen for background control (non-irradiated monitors): In Part I, one monitor to follow the group sent to PTB and another one to IRSN. In Part II, around 3 control monitors are sent for each irradiating laboratory. In order to reduce the total irradiation time, up to four individual monitors were irradiated together, fixed to the surface of the same phantom [4]. 3. RESULTS After being irradiated at PTB and IRSN, IAEA returned the whole individual monitors group to each participant. The TLDs from irradiated and non-irradiated monitors were evaluated following normal IRD routine procedures, in a manual Harshaw 3500 TLD reader together with control TLDs kept in laboratory. At both intercomparison parts, the background control monitors received a small neutron dose from cosmic radiation due to the air transport between each laboratory participant and IAEA. Using results of Part I to improve algorithm and calibration, the new TLD albedo system has passed with 100% of approval in the performance test of Part II [7, 8].

3 3.1. Part I: Type Test Intercomparison Table 1 summarizes the neutron results obtained in Part I. The reference values of neutron H p (10) are given as and the reading values expressed as Mn. The response Rn is defined by equation 1. Mn Rn = (1) Table 1. Albedo response on type test Nº Neutron Radiation Quality Mn Rn* 1 Thermal kev kev kev MeV MeV a Cf, 0º Cf, 45º Cf, 60º AmBe AmBe (+Pb) Cf + 60 Co kev + 60 Co * - Italic values refer to those outside trumpet curves limits (Figure 1) Part II: Simulated Workplace Field Intercomparison The results obtained in Part I were extremely useful to calibrate the albedo monitor system and to improve its algorithm. Albedo monitors (as other neutron individual monitors) have strong energy dependence in the large occupational energy range, which covers from thermal to around 20 MeV [4, 5]. Thus, they always need some information about the neutron field in order to apply the correct calibration factor. When the monitors returned after Part II irradiations, IAEA stated only the application area [8]. Usually, IRD neutron individual monitoring service considers being necessary more data about where and how the albedo monitors were irradiated, like: reactor, radionuclide and others. Even so, the IRD twocomponent albedo system had a good performance, except for radiation quality nº 7, where the monitor returned to IRD without two TLDs, making its evaluation impossible. The ratio from incident to albedo component values was applied in the algorithm to correct the neutron

4 reading. Neutron results of the intercomparison Part II are shown in Table 2. The Canel quality is a reactor neutron spectrum from IRSN. Table 2. Albedo response on simulated workplace field Nº Neutron Radiation Quality Mn 1 Canel / 0º Canel + W250 b / 0º Scattered neutrons behind a cone shadow/ isotropic Cf(moderated)/ 0º + scattered neutrons behind a cone shadow/ isotropic a Rn Cf(moderated)/ 0º Cf(moderated)/ ± 75º Cf(moderated) + Cs / 60º Cf(moderated) + Cs / ± 75º a. Reading not available (TLDs lost). b. W wide X-rays spectra Trumpet Curves Trumpet curves have been proposed to define the limiting interval around the conventional true value or reference value (H ref ) of the individual monitoring quantity in which its measured value should lie [9]. They are a useful tool to visualize the overall response of an individual monitoring system s intercomparison, the dosimetric service performance and others. Due to overall uncertainties and the state-of-the-art associated with neutron individual monitoring, trumpet curves for neutron are wider than for photon [9]. Exclusively in neutron individual monitoring, the upper part of the trumpet is different from the lower part. The upper limit for neutron personal dose equivalent limit is shown in equation 2. The lower limit for neutron personal dose equivalent limit is shown in equation 3, where H 0 is the recording level. = 2 (2) ul ll 1 2. H 0 =. 1 2 H 0 + H ref (3) Together with, Mn and R from the two intercomparison parts, both trumpet limits (upper and lower) are presented in Figure 1.

5 Response Upper Unitary Lower Part I Part II Hp(10) Figure 1. Neutron responses from H p (10) IAEA Intercomparison s Part I and II. 4. CONCLUSIONS In several intercomparisons for neutron or mixed (neutron + gamma) fields throughout the last two decades, albedo monitors have shown excellent performance [10]. The IRD twocomponent TLD albedo system showed a good performance (100% results inside trumpet curve limits) in Part II of the IAEA International Intercomparison of Personal Dosimeters for Mixed Neutron-Photon Radiation for the Quantity Personal Dose Equivalent, where simulated workplace neutron fields are used. Only 20% (6/30) of the participating laboratories showed this same performance [8]. Participation in Part I of its IAEA intercomparison proved to be fundamental for the final characterization of the tested albedo system [2]. A 252 Cf(D 2 O-moderated) calibration factor [6] was applied to 70, 144, 565 kev spectra in Part I, with had result in the 3 points out of trumpet curves limit. Nowadays, in addition due to Part I, IRD has calibration factors for 70, 144, 565 kev, 1.2 and 5 MeV. Without this intercomparison, IRD will never access these calibration fields so quickly. Unfortunately in Part II, two TLDs were lost in the monitor used in radiation quality nº 7, it also would allow evaluating the Canel quality (reactor) in a mixed neutron-photon radiation quality. At present, the authors are employing their best efforts to fulfill all specific ISO [5] performance requirements for thermoluminescence albedo and to allow for this twocomponent TLD albedo individual monitor system to be ready for routine use in IRD.

6 ACKNOWLEDGMENTS The authors are grateful to International Atomic Energy Agency by the invitation and by opportunity in taking part in the intercomparison. REFERENCES 1. S.A. Gonçalves, C.L.P. Maurício, J. Moura Júnior, M.M. Martins, N.F. Meira, R. Diz, R.P.G. Seda, Monitoração Individual de Nêutrons: 18 Anos de Experiência, Proceedings of the 2002 INAC (International Nuclear Atlantic Conference), Rio de Janeiro, August, Paper CD-rom E01_566.pdf (2002). 2. M.M. Martins, C.L.P. Maurício, K.C.S. Patrão, A.X. Silva, Calibration of a TLD Albedo Individual Neutron Monitor, to be presented at this Conference. 3. Comissão Nacional de Energia Nuclear, Restrição de Dose, Níveis de Referência Ocupacionais e Classificação de Áreas, Posição Regulatória 3.01/004 rev. 01, CNEN, Rio de Janeiro (2005). 4. International Organization for Standardization, Reference Neutron Radiations Part 3: Calibration of Area and Personal Dosimeters and the Determination of Their Response as a Function of Neutron Energy and Angle of Incidence, International Standard ISO , ISO, Geneva (1998). 5. International Organization for Standardization, Passive Personal Neutron Dosemeters Performance and Test Requirements, International Standard ISO 21909, ISO, Geneva (2005). 6. International Organization for Standardization, Reference Neutron Radiations Part 1: Characteristics and Methods of Production, International Standard ISO , ISO, Geneva (2001). 7. H. Schuhmacher, R.C. Suáres, J.L. Pochat, Intercomparison on Measurements of the Quantity Personal Dose Equivalent Hp(d) in Mixed (Neutron-Gamma) Fields Analysis of Results from Part 1, IAEA, Vienna (Austria), March (2004). 8. A. Zimbal, H. Schuhmacher, Intercomparison on Measurements of the Quantity Personal Dose Equivalent Hp(10) in Mixed (Neutron-Gamma) Fields Analysis of Results from Phase 2, IAEA, Vienna (Austria), April (2005). 9. J. Böhm, V.N. Lebedev, J.C. McDonald, Performance Test of Dosimetry Services and Its Regulatory Aspects, Radiat. Prot. Dosim., 54, pp (1994). 10. R.E. Swaja, Performance Characteristics of Neutron Personnel Dosemeters Used in the Oak Ridge Intercomparison Studies, Rad. Prot. Dos., 23, pp (1988).

Portuguese Health Physics Society: Calibrating Pen Dosimeters with and without a Phantom

Portuguese Health Physics Society: Calibrating Pen Dosimeters with and without a Phantom Portuguese Health Physics Society: Calibrating Pen Dosimeters with and without a Phantom Fernanda B. C. Nonato, Claudinei T. Cescon and Linda V. E. Caldas, Instituto de Pesquisas Energéticas e Nucleares,

More information

Ionizing Radiation, Czech Republic, CMI (Czech Metrology Institute)

Ionizing Radiation, Czech Republic, CMI (Czech Metrology Institute) Ionizing Radiation, Czech Republic, (Czech Metrology Institute) Calibration or Measurement RADIOACTIVITY 1.0E+00 1.0E+02 Bq cm -2 C-14 1.0E+01 1.0E+02 Bq cm -2 Co-60 1.0E+01 1.0E+02 Bq cm -2 Sr-90 1.0E+01

More information

DOSIMETRIC CHARACTERIZATION OF DYED PMMA SOLID DOSIMETERS FOR GAMMA RADIATION

DOSIMETRIC CHARACTERIZATION OF DYED PMMA SOLID DOSIMETERS FOR GAMMA RADIATION 2005 International Nuclear Atlantic Conference - INAC 2005 Santos, SP, Brazil, August 28 to September 2, 2005 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 85-99141-01-5 DOSIMETRIC CHARACTERIZATION

More information

SHORT-TERM STABILITY TEST FOR URANIUM SOIL CANDIDATE A REFERENCE MATERIAL

SHORT-TERM STABILITY TEST FOR URANIUM SOIL CANDIDATE A REFERENCE MATERIAL X Congreso Regional Latinoamericano IRPA de Protección y Seguridad Radiológica Radioprotección: Nuevos Desafíos para un Mundo en Evolución Buenos Aires, 12 al 17 de abril, 2015 SOCIEDAD ARGENTINA DE RADIOPROTECCIÓN

More information

DOSES TO EYES AND EXTREMITIES OF MEDICAL STAFF DURING INTERVENTIONAL RADIOLOGY PROCEDURES

DOSES TO EYES AND EXTREMITIES OF MEDICAL STAFF DURING INTERVENTIONAL RADIOLOGY PROCEDURES DOSES TO EYES AND EXTREMITIES OF MEDICAL STAFF DURING INTERVENTIONAL RADIOLOGY PROCEDURES Ausra Urboniene, Birute Griciene Lithuania Introduction Medical staff during interventional radiology procedures

More information

IMPROVEMENT OF GAMMA CALIBRATION PROCEDURES WITH COMMERCIAL MANAGEMENT SOFTWARE

IMPROVEMENT OF GAMMA CALIBRATION PROCEDURES WITH COMMERCIAL MANAGEMENT SOFTWARE 2007 International Nuclear Atlantic Conference - INAC 2007 Santos, SP, Brazil, September 30 to October 5, 2007 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-02-1 IMPROVEMENT OF GAMMA

More information

REMOTE SYSTEM FOR MONITORING AND CONTROL OF CONTROLLED AREA OF NUCLEAR INSTALLATION

REMOTE SYSTEM FOR MONITORING AND CONTROL OF CONTROLLED AREA OF NUCLEAR INSTALLATION 2011 International Nuclear Atlantic Conference - INAC 2011 Belo Horizonte,MG, Brazil, October 24-28, 2011 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-04-5 REMOTE SYSTEM FOR MONITORING

More information

Current practice of occupational radiation protection in industrial radiography

Current practice of occupational radiation protection in industrial radiography Current practice of occupational radiation protection in industrial radiography John Le Heron 1, Richard Van Sonsbeek 2, Gonzague Abela 3, Francisco Da Silva 4, Razak Hamzah 5, Thomas Levey 6, Matthias

More information

EFFECTS OF GAMMA IRRADIATION ON ELECTRIC CHARACTERISTICS OF POWER DIODES

EFFECTS OF GAMMA IRRADIATION ON ELECTRIC CHARACTERISTICS OF POWER DIODES 2009 International Nuclear Atlantic Conference - INAC 2009 Rio de Janeiro,RJ, Brazil, September27 to October 2, 2009 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-03-8 EFFECTS OF GAMMA

More information

ENVIRONMENTAL IMPACT ASSESSMENT OF A RADIOLOGICAL UNIT OF ORE PROCESSING, AT CALDAS, MG, BRAZIL

ENVIRONMENTAL IMPACT ASSESSMENT OF A RADIOLOGICAL UNIT OF ORE PROCESSING, AT CALDAS, MG, BRAZIL 2009 International Nuclear Atlantic Conference - INAC 2009 Rio de Janeiro,RJ, Brazil, September27 to October 2, 2009 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-03-8 ENVIRONMENTAL

More information

PERFORMANCE EVALUATION OF THE REFERENCE SYSTEM FOR CALIBRATION OF IPEN ACTIVIMETERS

PERFORMANCE EVALUATION OF THE REFERENCE SYSTEM FOR CALIBRATION OF IPEN ACTIVIMETERS 2011 International Nuclear Atlantic Conference - INAC 2011 Belo Horizonte,MG, Brazil, October 24-28, 2011 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-04-5 PERFORMANCE EVALUATION

More information

DOSE RATES EVALUATION ON ENVIRONMENT AROUND ALMIRANTE ALVARO ALBERTO NUCLEAR POWER STATION AFTER ANGRA 2 NUCLEAR POWER PLANT S OPERATION

DOSE RATES EVALUATION ON ENVIRONMENT AROUND ALMIRANTE ALVARO ALBERTO NUCLEAR POWER STATION AFTER ANGRA 2 NUCLEAR POWER PLANT S OPERATION 2007 International Nuclear Atlantic Conference INAC 2007 Santos, SP, Brazil, September 29 to October 5, 2007 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR ABEN DOSE RATES EVALUATION ON ENVIRONMENT AROUND ALMIRANTE

More information

What is the Radiotherapy Quality Control Program (PQRT) of the National Cancer Institute Rio de Janeiro/Brazil?

What is the Radiotherapy Quality Control Program (PQRT) of the National Cancer Institute Rio de Janeiro/Brazil? Congreso Internacional Conjunto Cancún 2004 LAS/ANS-SNM-SMSR/International Joint Meeting Cancun 2004 LAS/ANS-SNM-SMSR XV Congreso Anual de la SNM y XXII Reunión Anual de la SMSR/XV SNM Annual Meeting and

More information

NATURAL RADIOACTIVITY FROM THE SOIL OF SÃO BERNARDO DO CAMPO

NATURAL RADIOACTIVITY FROM THE SOIL OF SÃO BERNARDO DO CAMPO 2007 International Nuclear Atlantic Conference - INAC 2007 Santos, SP, Brazil, September 30 to October 5, 2007 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-02-1 NATURAL RADIOACTIVITY

More information

Determination of the Effective Energy in X-rays Standard Beams, Mammography Level

Determination of the Effective Energy in X-rays Standard Beams, Mammography Level Determination of the Effective Energy in X-rays Standard Beams, Mammography Level Eduardo de Lima Corrêa 1, Vitor Vivolo 1, Maria da Penha A. Potiens 1 1 Instituto de Pesquisas Energéticas e Nucleares

More information

Qualitätsmanagement-Handbuch

Qualitätsmanagement-Handbuch U r Kalibrier- und Messmöglichkeiten Qualitätsmanagement-Handbuch Relative erweiterte Messunsicherheit, die sich aus der Standardmessunsicherheit durch Multiplikation mit dem Erweiterungsfaktor k = 2 ergibt.

More information

CFD SIMULATION OF IPR-R1 TRIGA SUBCHANNELS FLUID FLOW

CFD SIMULATION OF IPR-R1 TRIGA SUBCHANNELS FLUID FLOW 2013 International Nuclear Atlantic Conference - INAC 2013 Recife, PE, Brazil, November 24-29, 2013 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-05-2 CFD SIMULATION OF IPR-R1 TRIGA

More information

TA3 Dosimetry and Instrumentation. Evaluation of the Field Size in Dental Diagnostic Radiology System ANDRADE PS 1, POTIENS MP 1

TA3 Dosimetry and Instrumentation. Evaluation of the Field Size in Dental Diagnostic Radiology System ANDRADE PS 1, POTIENS MP 1 TA3 Dosimetry and Instrumentation Evaluation of the Field Size in Dental Diagnostic Radiology System ANDRADE PS 1, POTIENS MP 1 1 Instituto de Pesquisas Energéticas e Nucleares, São Paulo, Brazil. ABSTRACT

More information

DEVELOPMENT OF A QUALITY MANAGEMENT SYSTEM FOR BRAZILIAN NUCLEAR INSTALLATIONS

DEVELOPMENT OF A QUALITY MANAGEMENT SYSTEM FOR BRAZILIAN NUCLEAR INSTALLATIONS 2005 International Nuclear Atlantic Conference - INAC 2005 Santos, SP, Brazil, August 28 to September 2, 2005 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 85-99141-01-5 DEVELOPMENT OF A QUALITY

More information

Individual Monitoring Services (IMS) for External and Internal Exposures

Individual Monitoring Services (IMS) for External and Internal Exposures Individual Monitoring Services (IMS) for External and Internal Exposures B. Morelli, C.M. Castellani, P. Battisti ENEA Radiation Protection Institute, Bologna (Italy) Contribution to the Italy in Japan

More information

MAJOR AND TRACE ELEMENTS IN GEOLOGICAL SAMPLES FROM ITINGUSSÚ BASIN IN COROA-GRANDE, R J.

MAJOR AND TRACE ELEMENTS IN GEOLOGICAL SAMPLES FROM ITINGUSSÚ BASIN IN COROA-GRANDE, R J. 2005 International Nuclear Atlantic Conference - INAC 2005 Santos, SP, Brazil, August 28 to September 2, 2005 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 85-99141-01-5 MAJOR AND TRACE ELEMENTS

More information

Secondary Neutrons in Proton and Ion Therapy

Secondary Neutrons in Proton and Ion Therapy Secondary Neutrons in Proton and Ion Therapy L. Stolarczyk Institute of Nuclear Physics PAN, Poland on behalf of WG9 EURADOS Acknowledgments EURADOS Workig Group 9 Roger Harrison Jean Marc Bordy Carles

More information

HUMAN FACTORS QUESTIONNAIRE AS A TOOL FOR RISK ASSESSMENT

HUMAN FACTORS QUESTIONNAIRE AS A TOOL FOR RISK ASSESSMENT 009 International Nuclear Atlantic Conference - INAC 009 Rio de Janeiro,RJ, Brazil, September7 to October, 009 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-03-8 HUMAN FACTORS QUESTIONNAIRE

More information

A TRIDENT SCHOLAR PROJECT REPORT

A TRIDENT SCHOLAR PROJECT REPORT A TRIDENT SCHOLAR PROJECT REPORT NO. 253 OPTIMIZATION OF THE PHOTON RESPONSE FOR A LIF THERMOLUMINESCENT DOSIMETER UNITED STATES NAVAL ACADEMY ANNAPOLIS, MARYLAND This document has been approved for public

More information

DEVELOPMENT AND IMPLEMENTATION OF AN AUTOMATED SYSTEM TO EXCHANGE ATTENUATORS OF THE OB85/1 GAMMA IRRADIATOR

DEVELOPMENT AND IMPLEMENTATION OF AN AUTOMATED SYSTEM TO EXCHANGE ATTENUATORS OF THE OB85/1 GAMMA IRRADIATOR 2011 International Nuclear Atlantic Conference - INAC 2011 Belo Horizonte,MG, Brazil, October 24-28, 2011 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-04-5 DEVELOPMENT AND IMPLEMENTATION

More information

Irradiation Field Size: 5cmX5cm 10cmX10cm 15cmX15cm 20cmX20cm. Focus-Surface Distance: 100cm. 20cm Volume of Ion Chamber : 1cmX1cmX1cm

Irradiation Field Size: 5cmX5cm 10cmX10cm 15cmX15cm 20cmX20cm. Focus-Surface Distance: 100cm. 20cm Volume of Ion Chamber : 1cmX1cmX1cm Proceedings of the Ninth EGS4 Users' Meeting in Japan, KEK Proceedings 200-22, p.5-8 MONTE CARLO SIMULATION ANALYSIS OF BACKSCATTER FACTOR FOR LOW-ENERGY X-RAY K. Shimizu, K. Koshida and T. Miyati Department

More information

ABSORBED DOSE DETERMINATION IN EXTERNAL BEAM RADIOTHERAPY

ABSORBED DOSE DETERMINATION IN EXTERNAL BEAM RADIOTHERAPY TECHNICAL REPORTS SERIES No. 398 Absorbed Dose Determination in External Beam Radiotherapy An International Code of Practice for Dosimetry Based on Standards of Absorbed Dose to Water Sponsored by the

More information

Ra, 232 Th and 40 K analysis in sand samples from some beaches of Great Vitória, Espírito Santo, Brazil: Preliminary results.

Ra, 232 Th and 40 K analysis in sand samples from some beaches of Great Vitória, Espírito Santo, Brazil: Preliminary results. 2009 International Nuclear Atlantic Conference - INAC 2009 Rio de Janeiro,RJ, Brazil, September27 to October 2, 2009 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-03-8 226 Ra, and

More information

Introduction to the Monte Carlo method

Introduction to the Monte Carlo method Some history Simple applications Radiation transport modelling Flux and Dose calculations Variance reduction Easy Monte Carlo Pioneers of the Monte Carlo Simulation Method: Stanisław Ulam (1909 1984) Stanislaw

More information

VIRTUAL INSTRUMENTATION ON MOBILE DEVICES FOR DEPLOYMENT IN NUCLEAR INSTALLATIONS

VIRTUAL INSTRUMENTATION ON MOBILE DEVICES FOR DEPLOYMENT IN NUCLEAR INSTALLATIONS 2013 International Nuclear Atlantic Conference - INAC 2013 Recife, PE, Brazil, November 24-29, 2013 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-05-2 VIRTUAL INSTRUMENTATION ON MOBILE

More information

Monte Carlo simulation of a scanning whole body counter and the effect of BOMAB phantom size on the calibration.

Monte Carlo simulation of a scanning whole body counter and the effect of BOMAB phantom size on the calibration. Monte Carlo simulation of a scanning whole body counter and the effect of BOMAB phantom size on the calibration. Gary H. Kramer, Linda C. Burns and Steven Guerriere Human Monitoring Laboratory, Radiation

More information

Performance evaluation and quality assurance of Varian enhanced dynamic wedges

Performance evaluation and quality assurance of Varian enhanced dynamic wedges JOURNAL OF APPLIED CLINICAL MEDICAL PHYSICS, VOLUME 7, NUMBER 1, WINTER 2006 Performance evaluation and quality assurance of Varian enhanced dynamic wedges Parham Alaei and Patrick D. Higgins Department

More information

IMPLEMENTATION OF A MANAGEMENT SYSTEM FOR OPERATING ORGANIZATIONS OF RESEARCH REACTORS

IMPLEMENTATION OF A MANAGEMENT SYSTEM FOR OPERATING ORGANIZATIONS OF RESEARCH REACTORS IMPLEMENTATION OF A MANAGEMENT SYSTEM FOR OPERATING ORGANIZATIONS OF RESEARCH REACTORS Eduardo Kibrit 1, Afonso Rodrigues de Aquino 2 and Désirée Moraes Zouain 3 1 Centro Tecnológico da Marinha em São

More information

REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH. REGULATORY GUIDE 8.4 (Draft was issued as DG-8036, dated April 2010)

REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH. REGULATORY GUIDE 8.4 (Draft was issued as DG-8036, dated April 2010) U.S. NUCLEAR REGULATORY COMMISSION June 2011 Revision 1 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 8.4 (Draft was issued as DG-8036, dated April 2010) PERSONNEL MONITORING

More information

Submitted to Radiation Measurements INVESTIGATION OF OSL SIGNAL OF RESISTORS FROM MOBILE PHONES FOR ACCIDENTAL DOSIMETRY

Submitted to Radiation Measurements INVESTIGATION OF OSL SIGNAL OF RESISTORS FROM MOBILE PHONES FOR ACCIDENTAL DOSIMETRY Submitted to Radiation Measurements INVESTIGATION OF OSL SIGNAL OF RESISTORS FROM MOBILE PHONES FOR ACCIDENTAL DOSIMETRY A. Mrozik, B. Marczewska, P. Bilski, W. Gieszczyk Institute of Nuclear Physics PAN,

More information

Radiation survey meters used for environmental monitoring

Radiation survey meters used for environmental monitoring NKS-257 ISBN 978-87-7893-329-4 Radiation survey meters used for environmental monitoring Hans Bjerke (editor) (1) Thorgeir Sigurdsson, (2) Kurt Meier Pedersen (3) Jan-Erik Grindborg, Linda Persson, (4)

More information

Use of the VALIDATOR Dosimetry System for Quality Assurance and Quality Control of Blood Irradiators

Use of the VALIDATOR Dosimetry System for Quality Assurance and Quality Control of Blood Irradiators Technical Note: 9 Use of the VALIDATOR Dosimetry System for Quality Assurance and Quality Control of Blood Irradiators 1- Introduction The VALIDATOR, model TN-ID-60, is a compact, and stand-alone dosimetry

More information

A Comparison of an HPGe-based and NaI-based Radionuclide Identifier (RID) for Radioactive Materials

A Comparison of an HPGe-based and NaI-based Radionuclide Identifier (RID) for Radioactive Materials Illicit Trafficking, Sub/cross-national threats, Poster presentation A Comparison of an HPGe-based and NaI-based Radionuclide Identifier (RID) for Radioactive Materials Ronald M. Keyser, Timothy R. Twomey,

More information

Improved dosimetry for BNCT by activation foils, modified thermoluminescent detectors and recombination chambers

Improved dosimetry for BNCT by activation foils, modified thermoluminescent detectors and recombination chambers NUKLEONIKA 2004;49(2):51 56 ORIGINAL PAPER Improved dosimetry for BNCT by activation foils, modified thermoluminescent detectors and recombination chambers Paweł Bilski, Natalia Golnik, Paweł Olko, Krzysztof

More information

Introduction. Chapter 15 Radiation Protection. Regulatory bodies. Dose Equivalent. Regulatory bodies. Main Principles of Radiation Protection

Introduction. Chapter 15 Radiation Protection. Regulatory bodies. Dose Equivalent. Regulatory bodies. Main Principles of Radiation Protection Introduction Chapter 15 Radiation Protection Radiation Dosimetry I Text: H.E Johns and J.R. Cunningham, The physics of radiology, 4 th ed. F.M. Khan, The Physics of Radiation Therapy, 4th ed., Chapter

More information

HEALTH PHYSICS LABORATORY

HEALTH PHYSICS LABORATORY HEALTH PHYSICS LABORATORY Report for 2003-2004 Activities: 5.9 TL dosimetry in medicin and radiation protection 5.10 Radiation protection 6.2 Development of therapeutic stand for proton therapy Health

More information

Nuclear data for science & technology: Centres for development

Nuclear data for science & technology: Centres for development Nuclear data for science & technology: Centres for development An update on the IAEA's nuclear data centre, its services, and the contributions to the global network from developing by Hans Lemmel f\ typical

More information

PERSONNEL MONITORING AND DOSIMETRY POLICIES

PERSONNEL MONITORING AND DOSIMETRY POLICIES PERSONNEL MONITORING AND DOSIMETRY POLICIES All individuals who are required to have their exposure to ionizing radiation monitored must be trained prior to using the source(s) of radiation. The radioactive

More information

Cyclotron Centre in Poland and 2D thermoluminescence dosimetry

Cyclotron Centre in Poland and 2D thermoluminescence dosimetry Cyclotron Centre in Poland and 2D thermoluminescence dosimetry Jan Gajewski Institute of Nuclear Physics, Kraków, Poland Department of Radiation Dosimetry Nuclear Physics Institute Academy of Science of

More information

Principles of dosimetry The ionization chamber

Principles of dosimetry The ionization chamber Principles of dosimetry The ionization chamber FYS-KJM 4710 Audun Sanderud Department of Physics Ionometry 1) Ionometry: the measurement of the number of ionizations in substance The number of ionizations

More information

Lecture 2 Macroscopic Interactions. 22.106 Neutron Interactions and Applications Spring 2010

Lecture 2 Macroscopic Interactions. 22.106 Neutron Interactions and Applications Spring 2010 Lecture 2 Macroscopic Interactions 22.106 Neutron Interactions and Applications Spring 2010 Objectives Macroscopic Interactions Atom Density Mean Free Path Moderation in Bulk Matter Neutron Shielding Effective

More information

FACTORS AFFECTING THE RESPONSE OF THE BUBBLE DETECTOR BD-100 AND A COMPARISON OF ITS RESPONSE TO CR-39*

FACTORS AFFECTING THE RESPONSE OF THE BUBBLE DETECTOR BD-100 AND A COMPARISON OF ITS RESPONSE TO CR-39* SLAC PUB 4399,c _ August 1987 FACTORS AFFECTING THE RESPONSE OF THE BUBBLE DETECTOR BD100 AND A COMPARISON OF ITS RESPONSE TO CR39* (W N E IPE, D D BUSICK Stanford Linear Accelerator Center Stanford University,

More information

STUDIES FOR A MULTIPURPOSE RESEARCH REACTOR FOR THE CRCN/CNEN-PE

STUDIES FOR A MULTIPURPOSE RESEARCH REACTOR FOR THE CRCN/CNEN-PE STUDIES FOR A MULTIPURPOSE RESEARCH REACTOR FOR THE CRCN/CNEN-PE Antônio C. O. Barroso*, José R. Maiorino, João M. L. Moreira **, José L. Bastos, José E. R. da Silva, Fernando R. de A. Lima, Mitsuo Yamaguchi,

More information

Atomic and Nuclear Physics Laboratory (Physics 4780)

Atomic and Nuclear Physics Laboratory (Physics 4780) Gamma Ray Spectroscopy Week of September 27, 2010 Atomic and Nuclear Physics Laboratory (Physics 4780) The University of Toledo Instructor: Randy Ellingson Gamma Ray Production: Co 60 60 60 27Co28Ni *

More information

ANNEX E. Occupational radiation exposures

ANNEX E. Occupational radiation exposures ANNEX E Occupational radiation exposures CONTENTS INTRODUCTION... 499 I. DOSEMONITORINGANDRECORDINGPRACTICES... 5 A. QUANTITIESMEASURED... 5 1. Protection quantities... 5 2. Quantities for external radiation

More information

THE RESTRUCTURING OF THE QUALITY MANAGEMENT SYSTEM OF CDTN

THE RESTRUCTURING OF THE QUALITY MANAGEMENT SYSTEM OF CDTN 2011 International Nuclear Atlantic Conference - INAC 2011 Belo Horizonte,MG, Brazil, October 24-28, 2011 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-04-5 THE RESTRUCTURING OF THE

More information

Aviation Route Dose Calculation and its Numerical Basis

Aviation Route Dose Calculation and its Numerical Basis Aviation Route Dose Calculation and its Numerical Basis H.Schraube 1, W.Heinrich 2, G.Leuthold 1, V.Mares 3 and S.Roesler 4 1 GSF - National Research Center for Environment and Health, D-85758 Neuherberg,

More information

How To Understand Light And Color

How To Understand Light And Color PRACTICE EXAM IV P202 SPRING 2004 1. In two separate double slit experiments, an interference pattern is observed on a screen. In the first experiment, violet light (λ = 754 nm) is used and a second-order

More information

An Innovative Method for Dead Time Correction in Nuclear Spectroscopy

An Innovative Method for Dead Time Correction in Nuclear Spectroscopy An Innovative Method for Dead Time Correction in Nuclear Spectroscopy Upp, Daniel L.; Keyser, Ronald M.; Gedcke, Dale A.; Twomey, Timothy R.; and Bingham, Russell D. PerkinElmer Instruments, Inc. ORTEC,

More information

Test Section for Experimental Simulation of Loss of Coolant Accident in an Instrumented Fuel Assembly Irradiated in the IEA-R1 Reactor

Test Section for Experimental Simulation of Loss of Coolant Accident in an Instrumented Fuel Assembly Irradiated in the IEA-R1 Reactor 2013 International Nuclear Atlantic Conference - INAC 2013 Recife, PE, Brazil, November 24-29, 2013 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-05-2 Test Section for Experimental

More information

CALCULATION METHODS OF X-RAY SPECTRA: A COMPARATIVE STUDY

CALCULATION METHODS OF X-RAY SPECTRA: A COMPARATIVE STUDY 243 CALCULATION METHODS OF X-RAY SPECTRA: A COMPARATIVE STUDY B. Chyba, M. Mantler, H. Ebel, R. Svagera Technische Universit Vienna, Austria ABSTRACT The accurate characterization of the spectral distribution

More information

OBJECTIVE OUTLINE PHOTONEUTRON PRODUCTION

OBJECTIVE OUTLINE PHOTONEUTRON PRODUCTION NEUTRON SHIELDING DESIGN AND EVALUATIONS Nisy E. Ipe, Ph.D. Consultant, Shielding Design, Dosimetry & Radiation Protection San Carlos, CA, U.S.A. Email: nisy@comcast.net http://www.shieldingconsultant.com/

More information

DETERMINATION OF THE EFFECTIVE VOLUME OF AN EXTRAPOLATION CHAMBER FOR X-RAY DOSIMETRY

DETERMINATION OF THE EFFECTIVE VOLUME OF AN EXTRAPOLATION CHAMBER FOR X-RAY DOSIMETRY X Congreso Regional Latinoamericano IRPA de Protección y Seguridad Radiológica Radioprotección: Nuevos Desafíos para un Mundo en Evolución Buenos Aires, 12 al 17 de abril, 2015 SOCIEDAD ARGENTINA DE RADIOPROTECCIÓN

More information

LA-UR- Title: Author(s): Submitted to: Approved for public release; distribution is unlimited.

LA-UR- Title: Author(s): Submitted to: Approved for public release; distribution is unlimited. LA-UR- Approved for public release; distribution is unlimited. Title: Author(s): Submitted to: Los Alamos National Laboratory, an affirmative action/equal opportunity employer, is operated by the University

More information

ON-STREAM XRF ANALYSIS OF HEAVY METALS AT PPM CONCENTRATIONS

ON-STREAM XRF ANALYSIS OF HEAVY METALS AT PPM CONCENTRATIONS Copyright JCPDS - International Centre for Diffraction Data 2004, Advances in X-ray Analysis, Volume 47. 130 ABSTRACT ON-STREAM XRF ANALYSIS OF HEAVY METALS AT PPM CONCENTRATIONS G Roach and J Tickner

More information

90 degrees Bremsstrahlung Source Term Produced in Thick Targets by 50 MeV to 10 GeV Electrons

90 degrees Bremsstrahlung Source Term Produced in Thick Targets by 50 MeV to 10 GeV Electrons SLAC-PUB-7722 January 9 degrees Bremsstrahlung Source Term Produced in Thick Targets by 5 MeV to GeV Electrons X. S. Mao et al. Presented at the Ninth International Conference on Radiation Shielding, Tsukuba,

More information

EXPERIMENTAL CONDITIONS FOR CROSS SECTION MEASUREMENTS FOR ANALYTICAL PURPOSES. L. Csedreki 1. Abstract. I. Introduction

EXPERIMENTAL CONDITIONS FOR CROSS SECTION MEASUREMENTS FOR ANALYTICAL PURPOSES. L. Csedreki 1. Abstract. I. Introduction ACTA PHYSICA DEBRECINA XLVI, 25 (2012) EXPERIMENTAL CONDITIONS FOR CROSS SECTION MEASUREMENTS FOR ANALYTICAL PURPOSES L. Csedreki 1 1 Institute of Nuclear Research of the Hungarian Academy of Sciences,

More information

EXTERNAL DOSE RATES IN COASTAL URBAN ENVIRONMENTS IN BRASIL

EXTERNAL DOSE RATES IN COASTAL URBAN ENVIRONMENTS IN BRASIL X Congreso Regional Latinoamericano IRPA de Protección y Seguridad Radiológica Radioprotección: Nuevos Desafíos para un Mundo en Evolución Buenos Aires, 12 al 17 de abril, 2015 SOCIEDAD ARGENTINA DE RADIOPROTECCIÓN

More information

Postgraduate Educational Course in Radiation Protection and the Safety of Radiation Sources Standard Syllabus

Postgraduate Educational Course in Radiation Protection and the Safety of Radiation Sources Standard Syllabus TRAINING COURSE SERIES No. 18 Postgraduate Educational Course in Radiation Protection and the Safety of Radiation Sources Standard Syllabus INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 2002 The originating

More information

Proficiency testing schemes on determination of radioactivity in food and environmental samples organized by the NAEA, Poland

Proficiency testing schemes on determination of radioactivity in food and environmental samples organized by the NAEA, Poland NUKLEONIKA 2010;55(2):149 154 ORIGINAL PAPER Proficiency testing schemes on determination of radioactivity in food and environmental samples organized by the NAEA, Poland Halina Polkowska-Motrenko, Leon

More information

National Laboratory for Metrology of Ionizing Radiation (LNMRI) 1

National Laboratory for Metrology of Ionizing Radiation (LNMRI) 1 National Laboratory for Metrology of Ionizing Radiation (LNMRI) 1 1. Introduction. The Institute for Radiation Protection and Dosimetry (IRD) has its origin in a small dosimetry Laboratory set up in the

More information

Effects of Cosmic Radiation in Aircrafts: A Discussion about Aircrew over South America

Effects of Cosmic Radiation in Aircrafts: A Discussion about Aircrew over South America doi: 10.5028/jatm.2012.04021012 Effects of Cosmic Radiation in Aircrafts: A Discussion about Aircrew over South America Claudio Antonio Federico 1,*, Odair Lélis Gonçalez 1, Gian Maria Agostino Angelo

More information

ACCELERATORS AND MEDICAL PHYSICS 2

ACCELERATORS AND MEDICAL PHYSICS 2 ACCELERATORS AND MEDICAL PHYSICS 2 Ugo Amaldi University of Milano Bicocca and TERA Foundation EPFL 2-28.10.10 - U. Amaldi 1 The icone of radiation therapy Radiation beam in matter EPFL 2-28.10.10 - U.

More information

Air-crew exposure to cosmic radiation on board of Polish passenger aircraft

Air-crew exposure to cosmic radiation on board of Polish passenger aircraft NUKLEONIKA 2004;49(2):77 83 ORIGINAL PAPER Air-crew exposure to cosmic radiation on board of Polish passenger aircraft Paweł Bilski, Paweł Olko, Tomasz Horwacik Abstract To establish the need for individual

More information

RN-222 RELEASE TO THE ENVIRONMENT: COMPARISON BETWEEN DIFFERENT GRANITE SOURCES

RN-222 RELEASE TO THE ENVIRONMENT: COMPARISON BETWEEN DIFFERENT GRANITE SOURCES EG0600055 Proceedings of the Environmental Physics Conference, 24-28 Feb. ~, -...,., - OJr - RN-222 RELEASE TO THE ENVIRONMENT: COMPARISON BETWEEN DIFFERENT GRANITE SOURCES A. Mamoon and Salah M. Kamal

More information

emission process Fundação Universidade Federal do Vale do São Francisco - UNIVASF, C. Postal 309, 48900-000, Juazeiro - BA, Brazil;

emission process Fundação Universidade Federal do Vale do São Francisco - UNIVASF, C. Postal 309, 48900-000, Juazeiro - BA, Brazil; CBPF-NF-1/9 1 O resonant structure evaluated by two-proton emission process T. N. Leite 1, N. Teruya, A. Dimarco 3, S. B. Duarte 4, O. A. P. Tavares 4 and M. Gonçalves 5 1 Colegiado de Engenharia Civil,

More information

Tutorial 4.6 Gamma Spectrum Analysis

Tutorial 4.6 Gamma Spectrum Analysis Tutorial 4.6 Gamma Spectrum Analysis Slide 1. Gamma Spectrum Analysis In this module, we will apply the concepts that were discussed in Tutorial 4.1, Interactions of Radiation with Matter. Slide 2. Learning

More information

centre for radiation protection

centre for radiation protection centre for radiation protection To excel in radiation science so as to: enforce and promote the radiation safety of workers, the public and the environment; ensure that irradiating apparatus and nuclear

More information

W. C. Reinig. Savannah River Laboratory E. I. du Pent de Nemours and Company Aiken, South Carolina 298o1

W. C. Reinig. Savannah River Laboratory E. I. du Pent de Nemours and Company Aiken, South Carolina 298o1 .*. *.-a /dp73j/3~ DP-MS-68-48 calforn1um-252: A NEW SOTOPC SOUR(!EFOR NEUTRON RADOGRAPHY by W. C. Reinig Savannah River Laboratory E.. du Pent de Nemours and Company Aiken, South Carolina 298o1. SRL7

More information

Worldwide Quality Assurance networks for radiotherapy dosimetry

Worldwide Quality Assurance networks for radiotherapy dosimetry Worldwide Quality Assurance networks for radiotherapy dosimetry Joanna Izewska Dosimetry and Medical Radiation Physics Section dosimetry@iaea.org Audit in radiotherapy dosimetry Objectives to enhance confidence

More information

Report on heat production during preliminary tests on the Rossi Ni-H reactor.

Report on heat production during preliminary tests on the Rossi Ni-H reactor. Report on heat production during preliminary tests on the Rossi Ni-H reactor. Dr. Giuseppe Levi In this first and preliminary document are reported the heat production measures done during two short tests

More information

REMEDIATION STRATEGIES AFTER NUCLEAR OR RADIOLOGICAL ACCIDENTS: PART 1 DATABASE DEVELOPMENT

REMEDIATION STRATEGIES AFTER NUCLEAR OR RADIOLOGICAL ACCIDENTS: PART 1 DATABASE DEVELOPMENT 2009 International Nuclear Atlantic Conference - INAC 2009 Rio de Janeiro,RJ, Brazil, September27 to October 2, 2009 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-03-8 REMEDIATION

More information

STUDY OF MAGNETISM IN GDTIN (T = NI, PD, CU) COMPOUNDS BY PERTURBED GAMMA-GAMMA ANGULAR CORRELATION SPECTROSCOPY

STUDY OF MAGNETISM IN GDTIN (T = NI, PD, CU) COMPOUNDS BY PERTURBED GAMMA-GAMMA ANGULAR CORRELATION SPECTROSCOPY 2005 International Nuclear Atlantic Conference - INAC 2005 Santos, SP, Brazil, August 28 to September 2, 2005 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 85-99141-01-5 STUDY OF MAGNETISM IN GDTIN

More information

Main properties of atoms and nucleus

Main properties of atoms and nucleus Main properties of atoms and nucleus. Atom Structure.... Structure of Nuclei... 3. Definition of Isotopes... 4. Energy Characteristics of Nuclei... 5. Laws of Radioactive Nuclei Transformation... 3. Atom

More information

Status of Radiation Safety System at

Status of Radiation Safety System at Status of Radiation Safety System at Taiwan Photon Source Joseph C. Liu Radiation and Operation Safety Division National Synchrotron Radiation Research Center, Taiwan NSRRC layout 1.5 GeV, 120m, 400 ma

More information

GAMMA-RAY SPECTRA REFERENCES

GAMMA-RAY SPECTRA REFERENCES GAMMA-RAY SPECTRA REFERENCES 1. K. Siegbahn, Alpha, Beta and Gamma-Ray Spectroscopy, Vol. I, particularly Chapts. 5, 8A. 2. Nucleonics Data Sheets, Nos. 1-45 (available from the Resource Centre) 3. H.E.

More information

Reduction of Electron Contamination Using a Filter for 6MV Photon Beam

Reduction of Electron Contamination Using a Filter for 6MV Photon Beam J. Korean Soc Ther Radiol Oncol : Vol. 15, No. 2, June, 1997 Reduction of Electron Contamination Using a Filter for 6MV Photon Beam Choul Soo Lee, MPH., Myung Jin Yoo, Ph.D. and Ha Yong Yum, M.D. Department

More information

Dedicated computer software to radiation dose optimization for the staff performing nuclear medicine procedures

Dedicated computer software to radiation dose optimization for the staff performing nuclear medicine procedures NUKLEONIKA 2012;57(4):497 502 ORIGINAL PAPER Dedicated computer software to radiation dose optimization for the staff performing nuclear medicine procedures Katarzyna Matusiak, Jakub Kosek Abstract. Nuclear

More information

Safety and Radiation Protection Office Working with X-Ray Equipment

Safety and Radiation Protection Office Working with X-Ray Equipment Safety and Radiation Protection Office Working with X-Ray Equipment Radiation Safety Rules May 2016 Radiation Safety Rules X-Ray Equipment General Rules for the protection of persons exposed to ionising

More information

Recognition. Radiation Survey Objectives. Objectives. Part 1 Documentation Radiation Source Survey Objectives Radiation Detectors Techniques

Recognition. Radiation Survey Objectives. Objectives. Part 1 Documentation Radiation Source Survey Objectives Radiation Detectors Techniques Recognition I will take this opportunity to recognize and thank the following people s contributions to this presentation. Considerations for: Diagnostic Radiology, Nuclear Medicine and, Oncology M. S.

More information

VoxelDose: A SOFTWARE FOR DOSIMETRIC EVALUATIONS IN X-RAY DIAGNOSES

VoxelDose: A SOFTWARE FOR DOSIMETRIC EVALUATIONS IN X-RAY DIAGNOSES 2007 International Nuclear Atlantic Conference - INAC 2007 Santos, SP, Brazil, September 30 to October 5, 2007 Associação Brasileira de Energia Nuclear - ABEN ISBN: 978-85-99141-02-1 VoxelDose: A SOFTWARE

More information

THE RESULTS OF THE LITHUANIAN RADON SURVEY. Gendrutis Morkunas 1, Gustav Akerblom 2

THE RESULTS OF THE LITHUANIAN RADON SURVEY. Gendrutis Morkunas 1, Gustav Akerblom 2 Radon in the Living Environment, 008 THE RESULTS OF THE LITHUANIAN RADON SURVEY Gendrutis Morkunas 1, Gustav Akerblom 2 1 Radiation Protection Centre, Kalvariju 153, LT-2042, Vilnius, Lithuania Tel. 3702

More information

RADIATION PROTECTION AND EXPOSURE MONITORING OF NUCLEAR FACILITY WORKERS

RADIATION PROTECTION AND EXPOSURE MONITORING OF NUCLEAR FACILITY WORKERS RADIATION PROTECTION AND EXPOSURE MONITORING OF NUCLEAR FACILITY WORKERS 1 Introduction 5 2 Scope of application 5 3 Occupational radiation protection 6 4 Operation of the radiation protection organisation

More information

Environmental Radiation Monitoring in Taiwan

Environmental Radiation Monitoring in Taiwan Environmental Radiation Monitoring in Taiwan Introduction: Ching-Chung Huang Radiation Monitoring Center, Atomic Energy Council 823, Cherng-Ching Road, Kaohsiung, Taiwan cchuang @ trmc.aec.gov.tw Chemical,

More information

Eye lens dose measurements in Interventional Cardiology

Eye lens dose measurements in Interventional Cardiology Eye lens dose measurements in Interventional Cardiology Poster No.: 479 Congress: ESCR 2014 Type: Scientific Poster Authors: N. Kollaros 1, E. Carinou 2, C. Plemmenos 1, I. Stathopoulos 1, V. Keywords:

More information

Improvement and storage of conventional mammography images using techniques of digital image processing

Improvement and storage of conventional mammography images using techniques of digital image processing BJRS BRAZILIAN JOURNAL OF RADIATION SCIENCES 03-1A (2015) 01-13 Improvement and storage of conventional mammography images using techniques of digital image processing M. M. A. Silva a ; J. W. Vieira b,c

More information

Appendix A. An Overview of Monte Carlo N-Particle Software

Appendix A. An Overview of Monte Carlo N-Particle Software Appendix A. An Overview of Monte Carlo N-Particle Software A.1 MCNP Input File The input to MCNP is an ASCII file containing command lines called "cards". The cards provide a description of the situation

More information

A MTR FUEL ELEMENT FLOW DISTRIBUTION MEASUREMENT PRELIMINARY RESULTS

A MTR FUEL ELEMENT FLOW DISTRIBUTION MEASUREMENT PRELIMINARY RESULTS A MTR FUEL ELEMENT FLOW DISTRIBUTION MEASUREMENT PRELIMINARY RESULTS W. M. Torres, P. E. Umbehaun, D. A. Andrade and J. A. B. Souza Centro de Engenharia Nuclear Instituto de Pesquisas Energéticas e Nucleares

More information

Nuclear applications at the Hellenic Centre for Marine Research (HCMR): Radioactivity in the marine environment

Nuclear applications at the Hellenic Centre for Marine Research (HCMR): Radioactivity in the marine environment Nuclear applications at the Hellenic Centre for Marine Research (HCMR): Radioactivity in the marine environment Dr. Christos Tsabaris Institute of Oceanography Hellenic Centre of Marine Research Motivation

More information

Testing of Kaonetics Devices at BNL

Testing of Kaonetics Devices at BNL BNL-95365-2011-IR Testing of Kaonetics Devices at BNL A. Bolotnikov, G. Smith and R. James June 2011 Nonproliferation and National Security Department Brookhaven National Laboratory U.S. Department of

More information

Examination of National and International Impacts of Adoption of ICRP Recommendations

Examination of National and International Impacts of Adoption of ICRP Recommendations Examination of National and International Impacts of Adoption of ICRP Recommendations Introduction The U.S. Nuclear Regulatory Commission (NRC) staff has engaged in multiple domestic and international

More information

A methodological approach for sediment core dating

A methodological approach for sediment core dating Radioprotection - Colloques, volume 37, Cl (2002) Cl-1009 A methodological approach for sediment core dating R. Ocone, M. Belli, L. Schiozzi 1 and A. Fazio 2 ANPA, Agenzia Nazionale perla Protezione dell'ambiente,

More information

IAEA-TECDOC-1447 Optimization of the radiological protection of patients: Image quality and dose in mammography (coordinated research in Europe)

IAEA-TECDOC-1447 Optimization of the radiological protection of patients: Image quality and dose in mammography (coordinated research in Europe) IAEA-TECDOC-1447 Optimization of the radiological protection of patients: Image quality and dose in mammography (coordinated research in Europe) Results of the Coordinated Research Project on Optimization

More information

Let s consider a homogeneous medium characterized by the extinction coefficient β ext, single scattering albedo ω 0 and phase function P(µ, µ').

Let s consider a homogeneous medium characterized by the extinction coefficient β ext, single scattering albedo ω 0 and phase function P(µ, µ'). Lecture 22. Methods for solving the radiative transfer equation with multiple scattering. Part 4: Monte Carlo method. Radiative transfer methods for inhomogeneous ouds. Objectives: 1. Monte Carlo method.

More information

Azam Niroomand-Rad, PhD Georgetown University Medical Center Washington D.C. AAPM 41st Annual Meeting Continuing Education Courses

Azam Niroomand-Rad, PhD Georgetown University Medical Center Washington D.C. AAPM 41st Annual Meeting Continuing Education Courses AAPM 41st Annual Meeting Continuing Education Courses Special Dosimetry Measurements-3 Two Dimensional Radiation Field Mapping Using Radiochromic Film Wednesday, July 28, 1999 7:30 AM - 8:30 AM Azam Niroomand-Rad,

More information