GammaUser2014 Spectrum Analysis Exercise

Size: px
Start display at page:

Download "GammaUser2014 Spectrum Analysis Exercise"

Transcription

1 GammaUser2014 Spectrum Analysis Exercise Seppo Klemola

2 Exercise (rather than intercomparison): Analysis of radionuclides and their concentrations in (legacy) air filter spectrum Spectrum provided for analysis in two formats (ORTEC chn + phd ASCII) ICEX1401 at NKS GammaUser2014 GammaWiki web-page: ( Additionally calibration spectrum (CalibN4) and background spectrum (BGRDN4) were provided Setup and calibration data in pdf + MS Excel Sample data: sampling, geometry, etc. Acquisition data: start, live time Detector data: type, dimension, absorbing layers Calibration source data: geometry, reference activities for 10 nuclides Ready-made efficiency calibration as energy efficiency pairs, 59.5 kev kev, with uncertainty and TCS-correction coefficients

3 Air filter sample Sampling start of sampling: :25 end of sampling: :15 5 h 50 min reference time: :20 volume: 1020 m 3 ~ 170 m 3 /h Sample Geometry Beaker material: polystyrene inner diameter: 21 mm, bottom wall: 1.3 mm, side wall: 2.0 mm Sample material: glass-fiber (compressed aerosol filter) sample height: 3.0 mm, sample density: 0.7 g cm -3 sample detector distance: 0.3 mm (beaker bottom to detector window)

4 Measurement Acquisition Start: :16 age of the sample: 4.2 d Live time: min Detector HPGe p-type coaxial (ORTEC GEM P-S, rel. eff.: 39%, FWHM: 1.76 kev) crystal diameter: 57.3 mm; length: 73.4 mm core diameter: 9.8 mm, length: 60.1 mm absorbing layers, mm top side Ge Al Mylar vacuum Al

5 Efficiency calibration with multinuclide source

6 Background spectrum

7 Calibration spectrum

8 Air filter spectrum kev

9 A Sosnovyy Bor Release in 1992 On March 24th :37 AM EET, a nuclear incident occurred in unit 3 of the RBMK reactor in Sosnovyy Bor NPP, in the course of which radionuclides were released in the environment. There had been a breakdown in one of 1700 fuel channels causing a pressure rise in the reactor space and subsequent exceeding of triggering level of the protection system. Steam and gases from the damaged fuel channel flowed to the accident localization system. The system operated normally, but noble gases, iodine, and other radionuclides were released through the cleaning filters. The air masses from the release reached the Finnish coast in about 12 hours.

10 Publications

11 A Sosnovyy Bor Release in 1992 Following the incident several radionuclides were identified in the surface air in south-eastern coast of Finland. STUK conducted sampling of ground level air on three sites in southeastern coast of Finland. The filter collected at Kotka (ca. 130 km east from Helsinki) , was measured over the next weekend, 3 days later. Conclusions The radionuclide concentrations were five orders of magnitude smaller than the concentrations during the Chernobyl accident in The radiological consequences in Finland were insignificant. Even a minor release, across the sea and more than 100 km away, can be detected and important information, including the time of the incident and the composition of the release and the burn-up of the damaged fuel, can be revealed by the most accurate radioactivity measurements.

12 STUK results Nuclide Bq/m 3

13

14

15

16 07492N4.CHN ICEX MEAS. STARTED REFERENCE DATE MEAS.TIME(MIN) AGE(DAYS) CALIB QUANTITY UNIT RHO HEIGHT GAMMA\CALIB n4ic.dat WPS TRESH WIN BSTF ETOL LOCH ICA ON NUCLIDE LIBRARY: ICEX.DAT, 51 NUCLIDES, 489 GAMMA LINES, ALL PEAKS CHECKED. THE FOLLOWING PEAKS ARE ATTRIBUTED TO ISOTOPES NUCLIDE NR ENERGY ERR PEAK LO HI BACKGR CPM RSD ACT.CONC RSD FIT MDC AT COINS KEV KEV IN CH CH CH CPM AT REF.D. ACT NR REF.D CORR. Be ,9 0,0 1429, ,3 0, ,10E ,10E-05 1,00 K ,8 0,1 4382, ,3 0, ,94E ,40E-04 1,00 Co ,9 0,3 360, ,5 0, ,09E ,10E-06 1,00 Co ,0 0,0 405, ,3 0, ,80E ,50E-05 1,00 Co ,6 0,1 1704, ,3 0, ,55E ,70E-02 1,41 Cs ,7 0,0 720, ,8 0, ,69E ,40E-02 1,53 Cs ,1 0,1 1685, ,6 0, ,41E ,00E-04 1,52 Cs ,6 0,1 1704, ,3 0, ,72E ,10E-05 1,52 Cs ,8 0,0 1810, ,8 0, ,50E ,20E-05 1,29 Cs ,9 0,0 2384, ,9 0, ,70E ,30E-05 1,29 Cs ,0 0, ,2 0, ,75E ,00E-05 1,48 Cs ,9 0, ,9 0, ,60E ,80E-04 0,76 Sb ,6 0, ,6 0, ,24E ,00E-03 1,32 Sb ,7 0, ,9 0, ,49E ,50E-04 1,19 Sb ,3 0, ,9 0, ,59E ,80E-03 2,16 Sb ,9 0, ,8 0, ,34E ,60E-05 1,04 Sb ,1 0,0 1745, ,9 0, ,11E ,70E-03 0,94 Sb ,8 0,0 1810, ,8 0, ,20E ,70E-04 1,28 Sb ,2 0, ,8 0, ,74E ,40E-03 1,32 Sb ,7 0,1 1999, ,6 1, ,46E ,10E-03 1,28 Sb ,0 0,1 2051, ,5 0, ,30E ,80E-05 1,01 Sb ,7 0, ,4 0, ,64E ,40E-05 1 Sb ,9 0,0 2444, ,9 0, ,00E ,40E-03 1,28 Sb ,2 0, , ,24E ,10E-03 0,91

17 Cont d NUCLIDE NR ENERGY ERR PEAK LO HI BACKGR CPM RSD ACT.CONC RSD FIT MDC AT COINS KEV KEV IN CH CH CH CPM AT REF.D. ACT NR REF.D CORR. I ,8 0,1 236, ,8 1, ,31E ,50E-04 1,30 I ,0 525, ,5 0, ,84E ,10E-03 1,29 I , ,8 0, ,68E ,00E-04 1,18 I ,3 0,0 880, ,4 0, ,14E ,50E+00 1,37 I ,5 0,0 1088, ,1 2, ,78E ,40E-05 1,00 I ,4 0,0 1208, ,6 0, ,04E ,30E-02 1,26 I ,2 0, ,8 0, ,96E ,40E-04 1,00 I ,8 0,2 783, , ,32E ,70E-03 2,00 I , ,8 0, ,76E ,40E-03 1,80 I ,2 1513, ,2 0, ,62E ,70E-04 1,88 I ,9 0,0 1564, ,6 0, ,74E ,90E-04 1,59 I ,9 0,0 1862, ,1 0, ,12E ,70E-03 1,72 I ,5 0,0 1887, ,2 0, ,77E ,10E-04 1,65 I ,8 0,2 1948, ,1 0, ,49E ,30E-03 1,85 I ,7 0,1 1999, ,6 1, ,75E ,90E-05 1,47 I ,2 0, ,2 0, ,13E ,50E-04 1,55 I ,7 0,0 2011, ,4 0, ,96E ,50E-04 1,87 I ,2 0,1 2178, ,8 0, ,13E ,60E-04 1,88 I ,8 0,0 2315, ,1 1, ,81E ,80E-05 1,47 I ,8 0,0 2339, ,6 0, ,77E ,60E-03 1,72 I ,8 0,0 2426, ,4 0, ,08E ,70E-04 1,66 I ,6 0,0 2434, ,5 0, ,26E ,10E-04 1,54 I ,0 2730, ,6 0, ,72E ,00E-03 1,81 I ,6 0,0 2861, ,7 0, ,62E ,50E-04 1,52 I ,1 0,1 3406, ,9 0, ,96E ,40E-04 1,34 I ,8 0, ,4 0, ,36E ,40E-03 1,20 I ,6 0, ,1 0, ,14E ,40E-04 0,74 I ,3 0, ,6 0, ,25E ,60E-04 0,59 I ,5 0, ,7 0, ,46E ,90E-04 1,51 I ,2 0,1 4194, ,3 0, ,37E ,20E-04 1,40 I ,1 0, ,8 0, ,34E ,60E-04 0,81 Ru ,4 0,0 1845, ,2 0, ,85E ,30E-04 1,26 Ru ,9 0,0 1862, ,1 0, ,91E ,00E-04 1,26 Ru ,8 0,0 3150, ,7 0, ,14E ,70E-04 0,85

18 Cont d NUCLIDE NR ENERGY ERR PEAK LO HI BACKGR CPM RSD ACT.CONC RSD FIT MDC AT COINS KEV KEV IN CH CH CH CPM AT REF.D. ACT NR REF.D CORR. I ,8 0,2 783, , ,81E ,30E-02 1,44 I ,8 0,1 1266, ,1 0, ,17E ,40E-02 1,23 I ,5 0,1 1587, ,8 0, ,88E ,60E-04 1,01 I ,8 0,2 1666, ,5 0, ,28E ,60E-01 1,31 I ,0 2303, ,3 0, ,53E ,40E-02 1,24 I ,3 0, ,6 0, ,48E ,70E-03 0,95 Cs ,8 0,1 194, ,3 0, ,71E ,10E-04 2 Cs ,2 0, ,3 0, ,63E ,30E-04 1,6 Cs ,3 0,0 454, ,2 0, ,36E ,10E-04 1,45 Cs ,8 0,2 488, ,9 0, ,93E ,70E-04 1,48 Cs ,0 525, ,5 0, ,28E ,80E-05 1 Cs ,1 0,0 552, ,2 0, ,05E ,90E-03 1,84 Cs ,9 0,0 942, ,3 0, ,61E ,50E-02 1,68 Cs ,5 0,0 953, ,9 0, ,65E ,10E-02 1,37 Cs ,6 0, ,1 0, ,51E ,50E-05 1,47 Cs ,8 0,0 2453, , ,88E ,10E-05 1,5 Cs ,1 0,0 3142, ,8 0, ,24E ,70E-05 1,52 Rh ,5 0,0 914, ,1 0, ,27E ,40E-04 1 Rh ,5 0,0 953, ,9 0, ,88E ,20E-04 1 Ba ,5 0, ,9 0, ,77E ,60E-02 1,44 Ba ,7 0,0 395, ,4 0, ,31E ,60E-03 1,15 Ba ,8 0,0 482, ,9 0, ,05E ,10E-04 1,14 Ba ,8 0,0 909, ,1 0, ,16E ,30E-04 1,3 Ba ,8 0,1 1266, ,1 0, ,65E ,80E-04 1,01 Ba ,5 0, ,7 0, ,15E ,60E-04 1 Ba ,3 0,0 1607, ,8 0, ,11E ,90E-05 1,01 Ba ,5 0,1 1647, ,6 0, ,01E ,40E-01 0,86

19 Cont d NUCLIDE NR ENERGY ERR PEAK LO HI BACKGR CPM RSD ACT.CONC RSD FIT MDC AT COINS KEV KEV IN CH CH CH CPM AT REF.D. ACT NR REF.D CORR. La ,6 0,0 981, , ,35E ,90E-04 1,49 La ,6 0,0 1293, ,3 0, ,87E ,70E-03 1,49 La ,1 0, ,9 1, ,09E ,40E-04 1,35 La ,9 0,0 2252, ,1 0, ,46E ,00E-03 1,19 La ,9 0,0 2444, ,9 0, ,82E ,80E-04 1,07 La ,4 0,2 2599, ,6 0, ,01E ,90E-04 1,19 La ,8 0, ,4 0, ,02E ,60E-03 1,06 La ,2 0, , ,81E ,70E-04 1,19 La ,3 0,1 4789, ,2 1, ,95E ,10E-05 1,28 La ,5 0,1 7567, , ,63E ,70E-04 0,90 Ce ,4 0,0 415, ,6 5,6434 0,8 1,01E ,50E-02 1,82 Ce ,3 0, ,9 0, ,77E ,10E-04 1,11 Ce ,7 0,1 1050, ,8 1, ,51E ,70E-03 0,89 Ce ,6 0,0 1293, ,3 0, ,36E ,00E-02 1,29 Mo ,4 0,0 415, ,6 5,6434 0,8 4,53E ,30E-04 1,28 Mo ,2 0,1 538, ,1 0, ,12E ,90E-04 1,23 Mo ,1 0,3 1093, ,4 0, ,68E ,00E-03 1,00 Mo ,6 0,1 2215, ,9 0, ,99E ,30E-04 1,35 Mo ,8 0,1 2330, ,5 0, ,54E ,40E-04 1,00 Tc-99m ,4 0,0 415, ,6 5,6434 0,8 1,79E ,70E-05 1,00 Ce ,8 0,1 236, ,8 1, ,37E ,70E-04 1,00 Ce ,7 0,0 395, ,4 0, ,00E ,60E-05 1,00 Nd ,8 0,1 236, ,8 1, ,75E ,60E+00 1,35 Nd ,1 0,0 267, ,6 0,39 4 1,70E ,50E-05 1,01 Nd ,5 0,3 347, ,6 1, ,73E ,10E-02 1,29 Nd ,4 0,0 355, ,3 0, ,14E ,50E-03 1,51 Nd ,5 0,0 953, ,9 0, ,57E ,70E-04 1,39 Nd ,5 0,1 1587, ,8 0, ,10E ,00E-04 0,99 Nd ,1 2051, ,5 0, ,09E ,50E-04 0,96

20 Cont d NUCLIDE NR ENERGY ERR PEAK LO HI BACKGR CPM RSD ACT.CONC RSD FIT MDC AT COINS KEV KEV IN CH CH CH CPM AT REF.D. ACT NR REF.D CORR. Tl ,7 0, ,5 2, ,69E ,40E-04 1,46 Tl ,1 0,0 1745, ,9 0, ,44E ,80E-05 1,28 Tl ,8 0,2 1948, ,1 0, ,27E ,90E-02 1,60 Tl ,6 0,3 2579, , ,20E ,70E-04 1,09 Tl ,5 0,1 7847, , ,87E ,00E-05 1,36 Pb ,5 0, ,9 0, ,33E ,20E-04 1,29 Pb ,0 525, ,5 0, ,60E ,20E-02 1,31 Pb ,7 0, ,8 0, ,68E ,70E-05 1,00 Pb ,3 0,2 895, ,1 0, ,22E ,40E-04 1,31 Pb ,4 0,0 154, ,2 0, ,80E ,70E-03 1,30 Pb ,8 0, ,4 0, ,33E ,60E-02 1,30 Pb ,7 0,0 720, ,8 0, ,03E ,80E-05 1,01 Pb ,3 0,0 880, ,4 0, ,78E ,90E-05 1,00 Pb ,8 0,0 909, ,1 0, ,38E ,70E-02 1,43 Pb ,7 0,1 1050, ,8 1, ,44E ,60E-05 1,00 Pb ,1 0, ,9 1, ,77E ,70E-03 1,29 Pb ,3 0,0 1607, ,8 0, ,42E ,30E-02 1,31 Ac ,6 0,0 293, ,6 3, ,37E ,20E-04 1,57 Ac ,3 0,0 454, ,2 0, ,02E ,60E-04 1,22 Ac ,9 0,0 624, ,9 1, ,87E ,50E-04 1,14 Ac ,6 0,0 981, , ,53E ,00E-04 1,20 Ac ,6 0, , ,18E ,40E-05 1,03 Ac ,6 0, ,1 0, ,37E ,00E-03 1,44 Ac ,1 0,1 1685, ,6 0, ,57E ,80E-04 1,06 Ac ,2 0,1 2178, ,8 0, ,43E ,40E-03 1,34 Ac ,8 0,0 2315, ,1 1, ,40E ,20E-04 1,34 Ac ,7 0, ,4 0, ,40E ,20E-03 1,15 Ac ,9 0,0 2384, ,9 0, ,43E ,50E-04 1,31 Ac ,0 2730, ,6 0, ,35E ,50E-05 1,06 Ac ,7 0, ,7 0, ,04E ,30E-04 1,12

21 Cont d NUCLIDE NR ENERGY ERR PEAK LO HI BACKGR CPM RSD ACT.CONC RSD FIT MDC AT COINS KEV KEV IN CH CH CH CPM AT REF.D. ACT NR REF.D CORR. U ,9 0, ,3 0, ,13E ,30E-02 1,43 U ,4 0,1 172, ,5 0, ,80E ,20E-05 1,30 U ,9 0, ,9 5,4102 0,8 1,48E ,80E-01 1,13 U ,8 0,2 488, ,9 0, ,21E ,80E-04 1,10 U ,2 0,1 619, , ,33E ,80E-05 1,09 Te ,9 0, ,3 0, ,35E ,30E-04 1,32 Te ,2 0, ,9 0, ,98E ,20E-04 1,36 Te ,3 342, ,5 0, ,06E ,40E-04 1,34 Te ,1 0, ,9 6,7904 0,7 2,81E ,30E-05 1,07 U-237X 14 97,2 0, , ,26E ,70E-05 1,00 U-237X ,8 0,1 296, ,2 0, ,61E ,80E-05 1,00 U-237X ,5 0, ,9 0, ,14E ,20E-05 1,00 U-237X ,5 0,3 347, ,6 1, ,12E ,40E-04 1,00 Np ,9 0, ,3 0, ,27E ,30E-02 1,39 Np ,6 0, ,6 0, ,56E ,70E-03 1,30 Np ,8 0,1 194, ,3 0, ,54E ,90E-02 1,37 Np ,3 0,0 313, ,6 6,0451 0,7 9,61E ,70E-05 1,29 Np ,2 0,1 538, ,1 0, ,97E ,70E-02 1,30 Np ,9 0,0 624, ,9 1, ,45E ,60E-04 1,11 Np ,1 0, ,9 6,7904 0,7 3,26E ,60E-04 1,11 Np ,7 0, ,9 0, ,54E ,60E-02 1,03 Np ,7 0, ,5 2, ,11E ,80E-04 1,11 Np , ,8 0, ,84E ,30E-03 1,10 Np ,9 0,0 942, ,3 0, ,15E ,30E-03 0,88 Np ,1 0,0 997, ,4 0, ,13E ,70E-04 0,75 Np-239X 15 99,6 0,0 293, ,6 3, ,62E ,60E-04 1,00 Np-239X ,9 0, ,9 5,4102 0,8 8,52E ,00E-04 1,00 Np-239X ,5 0,3 347, ,6 1, ,63E ,00E-04 1,00 Np-239X ,4 0,0 355, ,3 0, ,03E ,50E-04 1,00 Zr ,3 0,1 2169, ,4 1, ,95E ,10E-05 1,00 Zr ,8 0,0 2267, ,5 1, ,49E ,60E-05 1,00 Zr ,2 0,0 2226, ,6 0, ,27E ,90E-04 1,00 Nb ,8 0,1 2294, ,6 2, ,17E ,30E-06 1,00 Nb ,2 0,1 1971, ,8 0, ,30E ,60E-04 1,00 Ru ,1 0,0 1487, ,4 4,2451 0,8 1,35E ,10E-05 1,00 Ru ,5 0,1 1824, , ,39E ,20E-04 1,00 Cs ,6 0,1 1981, , ,78E ,00E-05 1,00 Ce ,5 0,0 431, ,7 3, ,05E ,10E-05 1,00

22 C THE FOLLOWING ISOTOPES WERE IDENTIFIED NR NUCLIDE CONF.VALACT. CONC. R.S.D. NR NUCLIDE CONF.VALACT. CONC.R.S.D. 1 Be E Cs E K E Cs E Co E Cs E Zr E Ba E Zr E La E Nb E Ce E Nb E Ce E Mo E Ce E Tc-99m E Nd E Ru E Tl E Ru E Pb E Rh E Pb E Sb E Ac E Te E U E I E U-237X E I E Np E I E Np-239X E-03 3

NKS GammaUser

NKS GammaUser Uncertainties Marie-Christine Lépy Laboratoire National Henri Becquerel CEA Saclay, F-91191 Gif-sur-Yvette cedex, France E-mail: marie-christine.lepy@cea.fr NKS GammaUser 2014 Helsinki 6-8 October 2014

More information

Improved Detector Response Characterization Method in ISOCS and LabSOCS

Improved Detector Response Characterization Method in ISOCS and LabSOCS P Improved Detector Response Characterization Method in ISOCS and LabSOCS *1 1 1 1 1 R. VenkataramanP P, F. BronsonP P, V. AtrashkevichP P, M. FieldP P, and B.M. YoungP P. 1 PCanberra Industries, 800 Research

More information

ENDF/B-VII.1 versus ENDFB/-VII.0: What s Different?

ENDF/B-VII.1 versus ENDFB/-VII.0: What s Different? LLNL-TR-548633 ENDF/B-VII.1 versus ENDFB/-VII.0: What s Different? by Dermott E. Cullen Lawrence Livermore National Laboratory P.O. Box 808/L-198 Livermore, CA 94550 March 17, 2012 Approved for public

More information

Activity concentration for exempt material (Bq/g)

Activity concentration for exempt material (Bq/g) 173.436 Exempt material activity concentrations and exempt consignment activity limits for radionuclides. The Table of Exempt material activity concentrations and exempt consignment activity limits for

More information

Micro-Detective. Ultra-Light, High-Fidelity Hand-Held Radioisotope Identifier

Micro-Detective. Ultra-Light, High-Fidelity Hand-Held Radioisotope Identifier Ultra-Light, High-Fidelity Hand-Held Radioisotope Identifier Accurate nuclide identification based on high resolution gamma spectroscopy with confirmatory neutron detection. Definitive detection of illicit

More information

Detective X. Ultra High Resolution HPGe Radioisotope Identification Device. The New Gold Standard for Mission Critical Detection and Identification

Detective X. Ultra High Resolution HPGe Radioisotope Identification Device. The New Gold Standard for Mission Critical Detection and Identification Ultra High Resolution HPGe Radioisotope Identification Device The New Gold Standard for Mission Critical Detection and Identification How do you improve on The Gold Standard for nuclear threat detection

More information

Another Gamma Spectroscopy Innovation from ORTEC

Another Gamma Spectroscopy Innovation from ORTEC ORTEC trans-spec Another Gamma Spectroscopy Innovation from ORTEC High Performance Portable HPGe Gamma Spectrometer REQUIRES NO LIQUID NITROGEN! Rugged, Battery Powered, High-Resolution HPGe Gamma Spectrometer

More information

DEVELOPMENT OF WEB-BASED ENVIRONMENT FOR ATMOSPHERIC DISPERSION MODELING

DEVELOPMENT OF WEB-BASED ENVIRONMENT FOR ATMOSPHERIC DISPERSION MODELING ANS PSA 2013 International Topical Meeting on Probabilistic Safety Assessment and Analysis Columbia, SC, September 22-26, 2013, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2013) DEVELOPMENT

More information

Application of MCNP Code in Shielding Design for Radioactive Sources

Application of MCNP Code in Shielding Design for Radioactive Sources Application of MCNP Code in Shielding Design for Radioactive Sources Ibrahim A. Alrammah Abstract This paper presents three tasks: Task 1 explores: the detected number of as a function of polythene moderator

More information

Case Study Core Capabilities in Nuclear Forensics

Case Study Core Capabilities in Nuclear Forensics Nuclear Forensics Workshop, Bangkok, 7 9 December 2011 1 Case Study Core Capabilities in Nuclear Forensics Klaus Mayer Joint Research Centre Institute for Transuranium Elements (ITU) Karlsruhe, Germany

More information

AIR or STACK MONITOR GAS, GROSS BETA-GAMMA PARTICULATE, & IODINE

AIR or STACK MONITOR GAS, GROSS BETA-GAMMA PARTICULATE, & IODINE FEATURES: AIR or STACK MONITOR THREE CHANNEL SIMULTANEOUS MEASUREMENT DETECTOR VERIFICATION CAPABILITY USING GAS & SOLID SOURCES EASY DETECTOR SYSTEM CALIBRATION WITH BUILT-IN CALIBRATION INTERFACE INTERNAL

More information

Modeling the ORTEC EX-100 Detector using MCNP

Modeling the ORTEC EX-100 Detector using MCNP Modeling the ORTEC EX-100 Detector using MCNP MCNP is a general-purpose Monte Carlo radiation transport code for modeling the interaction of radiation with materials based on composition and density. MCNP

More information

Improvement in the calibration techniques of approved dosimetry services in Spanish nuclear power plants of whole body counters with NaI detectors.

Improvement in the calibration techniques of approved dosimetry services in Spanish nuclear power plants of whole body counters with NaI detectors. Improvement in the calibration techniques of approved dosimetry services in Spanish nuclear power plants of whole body counters with NaI detectors. E.Sollet (*), A.Felipe(**), JM.Perez (**), S. De Maria

More information

Micro-Detective-HX Enhanced Capability, Ultra-Light, High-Fidelity Hand-Held Radioisotope Identifier

Micro-Detective-HX Enhanced Capability, Ultra-Light, High-Fidelity Hand-Held Radioisotope Identifier Enhanced Capability, Ultra-Light, High-Fidelity Hand-Held Radioisotope Identifier Wireless Remote Monitoring Remotely control and monitor from a central location. Portable Light weight, long battery life,

More information

Rad Pro Calculator Version History

Rad Pro Calculator Version History Version 1.901 (2-10-2006) Rad Pro Calculator Version History Added P-32 to decay calculation drop-down list, (2-10-2006). Version 1.95 (2-11-2006) Added an inverse square law calculations tab to the desktop

More information

ICP-OES. By: Dr. Sarhan A. Salman

ICP-OES. By: Dr. Sarhan A. Salman ICP-OES By: Dr. Sarhan A. Salman AGENDA -- ICP-OES Overview - Module removal Optical components and gas control overview Module replacement --Continue module replacement Manual optical alignment --Precise

More information

arxiv: v2 [cond-mat.mtrl-sci] 5 Jan 2010

arxiv: v2 [cond-mat.mtrl-sci] 5 Jan 2010 Gamma scattering scanning of concrete block for detection of voids. Shivaramu 1, Arijit Bose 2 and M. Margret 1 1 Radiological Safety Division, Safety Group, IGCAR, Kalpakaam - 63 12 (India) 2 Chennai

More information

A Dosimetry and Visualization Tool for the Fukushima Daiichi Power Plant

A Dosimetry and Visualization Tool for the Fukushima Daiichi Power Plant A Dosimetry and Visualization Tool for the Fukushima Daiichi Power Plant Justin Vazquez, Aiping Ding, Tianyu Liu, Chao Liang, Benjamin Lawrence, Christopher Gaylord, and Lin Su Advisor: Dr. X. George Xu

More information

ISOCS Characterization of Sodium Iodide Detectors for Gamma-Ray Spectrometry

ISOCS Characterization of Sodium Iodide Detectors for Gamma-Ray Spectrometry ISOCS Characterization of Sodium Iodide Detectors for Gamma-Ray Spectrometry Sasha A. Philips, Frazier Bronson, Ram Venkataraman, Brian M. Young Abstract--Activity measurements require knowledge of the

More information

A Lightweight and Compact Solution for Heavyweight Spectroscopic Problems

A Lightweight and Compact Solution for Heavyweight Spectroscopic Problems ORTEC Micro-trans-SPEC TM A Lightweight and Compact Solution for Heavyweight Spectroscopic Problems Amazingly Light 15 lb (6.8 kg) Tough Enclosure, Display, and all connections sealed against moisture

More information

MAESTRO 7. Multichannel Analyzer (MCA) Application Software

MAESTRO 7. Multichannel Analyzer (MCA) Application Software 7 Multichannel Analyzer (MCA) Application Software Advanced Features Windows 7 (32-bit and 64-bit) and Windows XP (32-bit) compatible. ORTEC CONNECTIONS 32- and 64-bit network connectivity: local and remote

More information

WELL COUNTERS AND ACCESSORIES LIST OF CONTENTS:

WELL COUNTERS AND ACCESSORIES LIST OF CONTENTS: LIST OF CONTENTS: CAPRAC -t Wipe Test / Well Counter...2 Captus 700t Well Counting System...4 Captus 700t Well Counting System Printouts.....5 Captus 3000 Well Counting System...6 Captus 3000 Reports.....7

More information

Daedeok-daero, Yuseong-gu, Daejeon , Republic of Korea b Argonne National Laboratory (ANL)

Daedeok-daero, Yuseong-gu, Daejeon , Republic of Korea b Argonne National Laboratory (ANL) MC 2-3/TWODANT/DIF3D Analysis for the ZPPR-15 10 B(n, α) Reaction Rate Measurement Min Jae Lee a*, Donny Hartanto a, Sang Ji Kim a, and Changho Lee b a Korea Atomic Energy Research Institute (KAERI) 989-111

More information

ORTEC. Battery-Powered, Portable HPGe Gamma Spectrometer. In-Situ High Purity Germanium Gamma Spectroscopy in a digital, battery powered instrument.

ORTEC. Battery-Powered, Portable HPGe Gamma Spectrometer. In-Situ High Purity Germanium Gamma Spectroscopy in a digital, battery powered instrument. ORTEC trans-spec-dx-100t Battery-Powered, Portable HPGe Gamma Spectrometer In-Situ High Purity Germanium Gamma Spectroscopy in a digital, battery powered instrument. No LN 2 Miniature, high-reliability,

More information

Limitations in the PHOTON Monte Carlo gamma transport code

Limitations in the PHOTON Monte Carlo gamma transport code Nuclear Instruments and Methods in Physics Research A 480 (2002) 729 733 Limitations in the PHOTON Monte Carlo gamma transport code I. Orion a, L. Wielopolski b, * a St. Luke s/roosevelt Hospital, Columbia

More information

Using the Bruker Tracer III-SD Handheld X-Ray Fluorescence Spectrometer using PC Software for Data Collection

Using the Bruker Tracer III-SD Handheld X-Ray Fluorescence Spectrometer using PC Software for Data Collection Using the Bruker Tracer III-SD Handheld X-Ray Fluorescence Spectrometer using PC Software for Data Collection Scott A Speakman, Ph.D Center for Materials Science and Engineering at MIT For assistance in

More information

NOTES on: An NJOY Processing Caution when Doppler Broadening

NOTES on: An NJOY Processing Caution when Doppler Broadening NOTES on: An NJOY Processing Caution when Doppler Broadening 1. Some references about Doppler Broadening CIELO processing Example of files in JEFF-3.2 Example of files in JENDL4.u 2. NJOY versions Official

More information

SINAC Simulator Software for Interactive Modelling of Environmental Consequences of Nuclear Accidents (Second Generation)

SINAC Simulator Software for Interactive Modelling of Environmental Consequences of Nuclear Accidents (Second Generation) SINAC Simulator Software for Interactive Modelling of Environmental Consequences of Nuclear Accidents (Second Generation) Péter Szántó, Sándor Deme, Edit Láng, István Németh, Tamás Pázmándi Hungarian Academy

More information

SHIELDING DEPTH DETERMINATION OF COBALT PHOTON SHOWER THROUGH LEAD, ALUMINUM AND AIR USING MONTE CARLO SIMULATION

SHIELDING DEPTH DETERMINATION OF COBALT PHOTON SHOWER THROUGH LEAD, ALUMINUM AND AIR USING MONTE CARLO SIMULATION Research Article SHIELDING DEPTH DETERMINATION OF COBALT PHOTON SHOWER THROUGH LEAD, ALUMINUM AND AIR USING MONTE CARLO SIMULATION 1 Ngadda, Y. H., 2 Ewa, I. O. B. and 3 Chagok, N. M. D. 1 Physics Department,

More information

Type DAD Technical Manual Modbus Communication

Type DAD Technical Manual Modbus Communication Type DAD 141.1 Technical Manual Modbus Communication Firmware Version 141.181.v.1.06 or higher Hardware Version 141.10x.v.1.01 Document No. E223-1 Rev. 2.2 EN DAD 141.1 Technical Manual Modbus Communication,

More information

ORTEC ISO-CART. A Complete In-Situ NDA Gamma-Ray Analysis for a Wide Variety of Samples. Mobile Assay System

ORTEC ISO-CART. A Complete In-Situ NDA Gamma-Ray Analysis for a Wide Variety of Samples. Mobile Assay System ORTEC ISO-CART A Complete In-Situ NDA Gamma-Ray Analysis for a Wide Variety of Samples Measures all common geometries: pipes, cylinders, floors, ceilings, walls, drums, boxes, and soils Easy-roll cart

More information

Total Measurement Uncertainty Estimation For Tomographic Gamma Scanner R.Venkataraman 1, S.Croft 1, M.Villani 1, R.D. McElroy 1, and R.J.

Total Measurement Uncertainty Estimation For Tomographic Gamma Scanner R.Venkataraman 1, S.Croft 1, M.Villani 1, R.D. McElroy 1, and R.J. Total Measurement Uncertainty Estimation For Tomographic Gamma Scanner R.Venkataraman 1, S.Croft 1, M.Villani 1, R.D. McElroy 1, and R.J. Estep 2 1 Canberra Industries, Inc., 800 Research Parkway, Meriden,

More information

JRP EMRP ENV09: MetroERM. Exploitation plan D4.3.1

JRP EMRP ENV09: MetroERM. Exploitation plan D4.3.1 1 st June 2014 31 th May 2017 JRP EMRP ENV09: MetroERM Metrology for radiological early warning networks in Europe Exploitation plan D4.3.1 Exploitation plan Deliverable Number: Deliverable Type: Lead

More information

NEW PRODUCTS FROM ORTEC. Shane Toal Sales Engineer

NEW PRODUCTS FROM ORTEC. Shane Toal Sales Engineer NEW PRODUCTS FROM ORTEC Shane Toal Sales Engineer PTE Workshop NPL Teddington 22 nd March 2012 1 Agenda DSpec-50 and DSpec-502 The Alpha Suite Detective-200 2 But first - Why DSP? 3 DSP MCA 4 DSP Filters

More information

IDM-200 -V. Interchangeable HPGe Detector Module (IDM) for Systems Integrators

IDM-200 -V. Interchangeable HPGe Detector Module (IDM) for Systems Integrators IDM-200 -V Interchangeable HPGe Detector Module (IDM) for Systems Integrators Free from liquid nitrogen, free from maintenance, free from integration complexities. Convenient-to-mount, all-in-one integrated

More information

TLC SCANNER. Model ~ HY-3 TRACER METHODOLOGY IN PET LABS, BIOCHEMISTRY, BIOMED AND CLINICAL LAB, RADIOPHARMACY & NUCLEAR MEDICINE

TLC SCANNER. Model ~ HY-3 TRACER METHODOLOGY IN PET LABS, BIOCHEMISTRY, BIOMED AND CLINICAL LAB, RADIOPHARMACY & NUCLEAR MEDICINE FEATURES ACCEPTS PAPER CHROMATOGRAMS, TLC PLATES, & ELECTROPHORESES ULTRA SENSITIVE SCANS UP TO SIX TRACES SIMULTANEOUSLY THREE DETECTOR TYPES FOR ANY NUCLIDE GM OR GAS FLOW OR SCINITLLATION DETECTORS

More information

ims MICRO-SIZED COMMUNICATING SOLUTIONS FOR REMOTE DETECTION & IDENTIFICATION OF RADIOACTIVE & NUCLEAR MATERIAL innovation & measurement systems

ims MICRO-SIZED COMMUNICATING SOLUTIONS FOR REMOTE DETECTION & IDENTIFICATION OF RADIOACTIVE & NUCLEAR MATERIAL innovation & measurement systems ims innovation & measurement systems MICRO-SIZED COMMUNICATING SOLUTIONS FOR REMOTE DETECTION & IDENTIFICATION OF RADIOACTIVE & NUCLEAR MATERIAL ims offers radioprotection and radiation measurements solutions

More information

Row 1 This is data This is data

Row 1 This is data This is data mpdf TABLES CSS Styles The CSS properties for tables and cells is increased over that in html2fpdf. It includes recognition of THEAD, TFOOT and TH. See below for other facilities such as autosizing, and

More information

Row 1 This is data This is data. This is data out of p This is bold data p This is bold data out of p This is normal data after br H3 in a table

Row 1 This is data This is data. This is data out of p This is bold data p This is bold data out of p This is normal data after br H3 in a table mpdf TABLES CSS Styles The CSS properties for tables and cells is increased over that in html2fpdf. It includes recognition of THEAD, TFOOT and TH. See below for other facilities such as autosizing, and

More information

PSG2 / Serpent a Monte Carlo Reactor Physics Burnup Calculation Code. Jaakko Leppänen

PSG2 / Serpent a Monte Carlo Reactor Physics Burnup Calculation Code. Jaakko Leppänen PSG2 / Serpent a Monte Carlo Reactor Physics Burnup Calculation Code Jaakko Leppänen Outline Background History The Serpent code: Neutron tracking Physics and interaction data Burnup calculation Output

More information

Annexure: 1 SPECIFICATION FOR HPGE DETECTOR AND ACCESSORIES

Annexure: 1 SPECIFICATION FOR HPGE DETECTOR AND ACCESSORIES Annexure: 1 SPECIFICATION FOR HPGE DETECTOR AND ACCESSORIES The items should be complete with all required accessories as per the detailed specification mentioned below. Sl.No. Item and specification details

More information

Advanced Gamma-Spectrometry Software. Efficiency Calculations for Semiconductor and Scintillation Detectors

Advanced Gamma-Spectrometry Software. Efficiency Calculations for Semiconductor and Scintillation Detectors ORTEC ANGLE 4 Advanced Gamma-Spectrometry Software Efficiency Calculations for Semiconductor and Scintillation Detectors Printed in U.S.A. ORTEC Part No. 931077 0616 Manual Revision C Advanced Measurement

More information

ORTEC MAESTRO -32 v6.08

ORTEC MAESTRO -32 v6.08 ORTEC MAESTRO -32 v6.08 Advanced Software for Multichannel Analyzer (MCA) Applications Integrated control of a wide range of spectroscopy hardware Instant live display of acquiring data on up to eight

More information

DEVELOPMENT AND CHARACTERISATION OF A HEAD CALIBRATION PHANTOM FOR IN VIVO MEASUREMENTS OF ACTINIDES

DEVELOPMENT AND CHARACTERISATION OF A HEAD CALIBRATION PHANTOM FOR IN VIVO MEASUREMENTS OF ACTINIDES DEVELOPMENT AND CHARACTERISATION OF A HEAD CALIBRATION PHANTOM FOR IN VIVO MEASUREMENTS OF ACTINIDES 1 G. Gualdrini, 1 P. Battisti, 2 R. Biagini, 2 P. De Felice, 2 A. Fazio, 3 P. Ferrari 1; Ente Nazionale

More information

Thermo Scientific Automatic 60 mm Sample Changer FHT 770 G-60 Technical Specification ZT-215E-1202

Thermo Scientific Automatic 60 mm Sample Changer FHT 770 G-60 Technical Specification ZT-215E-1202 Thermo Scientific Automatic 60 mm Sample Changer FHT 770 G-60 Technical Specification ZT-215E-1202 Thermo Fisher Scientific Messtechnik GmbH Frauenauracher Straße 96 91056 Erlangen Germany www.thermo.com

More information

Falcon Portable HPGe-Based Radionuclide Identifier. Radiation Safety. Amplified. KEY FEATURES DESCRIPTION.

Falcon Portable HPGe-Based Radionuclide Identifier. Radiation Safety. Amplified. KEY FEATURES DESCRIPTION. Radiation Safety. Amplified. Falcon 5000 Portable HPGe-Based Radionuclide Identifier KEY FEATURES Fast and easy to deploy LN 2 -free HPGe nuclide identifier Wide energy range covering all field situations

More information

Gamma spectroscopic measurements using the PID350 pixelated CdTe radiation detector

Gamma spectroscopic measurements using the PID350 pixelated CdTe radiation detector Gamma spectroscopic measurements using the PID350 pixelated CdTe radiation detector K. Karafasoulis, K. Zachariadou, S. Seferlis, I. Papadakis, D. Loukas, C. Lambropoulos, C. Potiriadis Abstract Spectroscopic

More information

MVP-BURN: Burn-up Calculation Code Using. A Continuous-energy Monte Carlo Code MVP

MVP-BURN: Burn-up Calculation Code Using. A Continuous-energy Monte Carlo Code MVP Draft report for JAEA-Data/Code (to be submitted in 2006) Last update 28. Jan. 2005 MVP-BURN: Burn-up Calculation Code Using A Continuous-energy Monte Carlo Code MVP (tentative title) Keisuke OKUMURA,

More information

BEAVRS benchmark calculations with Serpent-ARES code sequence

BEAVRS benchmark calculations with Serpent-ARES code sequence BEAVRS benchmark calculations with Serpent-ARES code sequence Jaakko Leppänen rd International Serpent User Group Meeting Berkeley, CA, Nov. 6-8, Outline Goal of the study The ARES nodal diffusion code

More information

inspire A Users Guide integrated Software Platform for Interactive REview Version Mar. 2018

inspire A Users Guide integrated Software Platform for Interactive REview Version Mar. 2018 inspire integrated Software Platform for Interactive REview A Users Guide Version 1.0.0 02 Mar. 2018 CTBTO/ IDC Division/ Software Applications Section Document Version History: Version Date Author Comments

More information

Format of the files used by Pepita

Format of the files used by Pepita Format of the files used by Pepita 1) Data Files (extension:.xl,.csv or.txt) Stores raw data counts per seconds (or counts) in the measured time slices for each isotope. Extension:.XL or.csv (comma delimited

More information

EXERCISE 3: CALCULATION OF RADON TRANSPORT IN THE ATMOSPHERE FROM URANIUM TAILING SITE AND RESULTING INHALATION DOSES TO REFERENCE INDIVIDUALS

EXERCISE 3: CALCULATION OF RADON TRANSPORT IN THE ATMOSPHERE FROM URANIUM TAILING SITE AND RESULTING INHALATION DOSES TO REFERENCE INDIVIDUALS EXERCISE 3: CALCULATION OF RADON TRANSPORT IN THE ATMOSPHERE FROM URANIUM TAILING SITE AND RESULTING INHALATION DOSES TO REFERENCE INDIVIDUALS 1. General description of problem In this exercise we use

More information

Crosstalk Analysis of ATC2 and impurity measurements

Crosstalk Analysis of ATC2 and impurity measurements Crosstalk Analysis of ATC2 and impurity measurements Institute for nuclear physics University of Cologne March 29 B. Birkenbach, B. Bruyneel, J. Eberth, H.Hess, D. Lersch, G. Pascovici, P. Reiter, A. Wiens,

More information

Click to edit Master title style

Click to edit Master title style New features in Serpent 2 for fusion neutronics 5th International Serpent UGM, Knoxville, TN, Oct. 13-16, 2015 Jaakko Leppänen VTT Technical Research Center of Finland Click to edit Master title Outline

More information

ISSN: ISO 9001:2008 Certified International Journal of Engineering and Innovative Technology (IJEIT) Volume 3, Issue 7, January 2014

ISSN: ISO 9001:2008 Certified International Journal of Engineering and Innovative Technology (IJEIT) Volume 3, Issue 7, January 2014 Influence of Cell Phone Waves on the Performance of HPGe Detector N. A. Mansour, E.I. Khalil, M. Fayez-Hassan* Zagazig University, Faculty of Science, Physics Department, Zagazig Egypt * Experimental Nuclear

More information

Instruction Manual. External Output Manual. Liquid Scintillation System LSC Model

Instruction Manual. External Output Manual. Liquid Scintillation System LSC Model Instruction Manual External Output Manual Liquid Scintillation System Model LSC-8000 Thank you for purchasing this product. The instruction manual of this product consists of the Operation Manual the External

More information

Measurement of 85 Kr in the environment by liquid scintillation counting

Measurement of 85 Kr in the environment by liquid scintillation counting Measurement of 85 Kr in the environment by liquid scintillation counting N. Momoshima, F. Inoue, S. Sugihara OUTLINE 1. Introduction 2. Purpose 3. Description of analytical flow 4. Analytical system 5.

More information

State of the art of Monte Carlo technics for reliable activated waste evaluations

State of the art of Monte Carlo technics for reliable activated waste evaluations State of the art of Monte Carlo technics for reliable activated waste evaluations Matthieu CULIOLI a*, Nicolas CHAPOUTIER a, Samuel BARBIER a, Sylvain JANSKI b a AREVA NP, 10-12 rue Juliette Récamier,

More information

Chapter 7: Geometrical Optics

Chapter 7: Geometrical Optics Chapter 7: Geometrical Optics 7. Reflection at a Spherical Surface L.O 7.. State laws of reflection Laws of reflection state: L.O The incident ray, the reflected ray and the normal all lie in the same

More information

CALCULATION OF THE ACTIVITY INVENTORY FOR THE TRIGA REACTOR AT THE MEDICAL UNIVERSITY OF HANNOVER (MHH) IN PREPARATION FOR DISMANTLING THE FACILITY

CALCULATION OF THE ACTIVITY INVENTORY FOR THE TRIGA REACTOR AT THE MEDICAL UNIVERSITY OF HANNOVER (MHH) IN PREPARATION FOR DISMANTLING THE FACILITY CALCULATION OF THE ACTIVITY INVENTORY FOR THE TRIGA REACTOR AT THE MEDICAL UNIVERSITY OF HANNOVER (MHH) IN PREPARATION FOR DISMANTLING THE FACILITY Gabriele Hampel, Friedemann Scheller, Medical University

More information

ORTEC MAESTRO -32 v6.08

ORTEC MAESTRO -32 v6.08 ORTEC MAESTRO -32 v6.08 Advanced Software for Multichannel Analyzer (MCA) Applications Integrated control of a wide range of spectroscopy hardware Instant live display of acquiring data on up to eight

More information

PCGAP: Users Guide and Algorithm Description

PCGAP: Users Guide and Algorithm Description INEEL/EXT-2000-00908 PCGAP: Users Guide and Algorithm Description E. W. Killian J. K. Hartwell September 2000 Idaho National Engineering and Environmental Laboratory Bechtel BWXT Idaho, LLC INEEL/EXT-2000-00908

More information

Atmospheric correction of hyperspectral ocean color sensors: application to HICO

Atmospheric correction of hyperspectral ocean color sensors: application to HICO Atmospheric correction of hyperspectral ocean color sensors: application to HICO Amir Ibrahim NASA GSFC / USRA Bryan Franz, Zia Ahmad, Kirk knobelspiesse (NASA GSFC), and Bo-Cai Gao (NRL) Remote sensing

More information

Breaking Through the Barriers to GPU Accelerated Monte Carlo Particle Transport

Breaking Through the Barriers to GPU Accelerated Monte Carlo Particle Transport Breaking Through the Barriers to GPU Accelerated Monte Carlo Particle Transport GTC 2018 Jeremy Sweezy Scientist Monte Carlo Methods, Codes and Applications Group 3/28/2018 Operated by Los Alamos National

More information

Comparison of Shutdown Dose Rate Results using MCNP6 Activation Capability and MCR2S

Comparison of Shutdown Dose Rate Results using MCNP6 Activation Capability and MCR2S APPLIED RADIATION PHYSICS GROUP TECHNICAL NOTE ARP-097 July 2014 Comparison of Shutdown Dose Rate Results using MCNP6 Activation Capability and MCR2S A. Turner 1, Z. Ghani 1, J. Shimwell 2 1: CCFE, Culham

More information

IEEE Nuclear Power Engineering Standards Collection VuSpec - Active Only

IEEE Nuclear Power Engineering Standards Collection VuSpec - Active Only IEEE Nuclear Power Engineering Standards Collection VuSpec - Active Only Includes 117 Active IEEE Standards, Guides, Recommended Practices, Errata and Interpretations in PDF Format (for viewing on-screen

More information

Neutronics Analysis of TRIGA Mark II Research Reactor. R. Khan, S. Karimzadeh, H. Böck Vienna University of Technology Atominstitute

Neutronics Analysis of TRIGA Mark II Research Reactor. R. Khan, S. Karimzadeh, H. Böck Vienna University of Technology Atominstitute Neutronics Analysis of TRIGA Mark II Research Reactor R. Khan, S. Karimzadeh, H. Böck Vienna University of Technology Atominstitute 23-03-2010 TRIGA Mark II reactor MCNP radiation transport code MCNP model

More information

Middle East Technical University Mechanical Engineering Department ME 413 Introduction to Finite Element Analysis Spring 2015 (Dr.

Middle East Technical University Mechanical Engineering Department ME 413 Introduction to Finite Element Analysis Spring 2015 (Dr. Middle East Technical University Mechanical Engineering Department ME 413 Introduction to Finite Element Analysis Spring 2015 (Dr. Sert) COMSOL 1 Tutorial 2 Problem Definition Hot combustion gases of a

More information

Introduction. Warning: The instrument is equipped with a scintillation detector. Avoid strong mechanical and temperature shocks!

Introduction. Warning: The instrument is equipped with a scintillation detector. Avoid strong mechanical and temperature shocks! User Guide v 1.2 2 Introduction...5 Control Unit...6 Power Supply...7 Battery Charging...7 Connections...8 Probe Connection...8 GPS Receiver Connection...8 Connection to PC...8 Basic Operation of the Instrument...9

More information

D.1 Radon Model Emanation Analysis

D.1 Radon Model Emanation Analysis D.1 Radon Model Emanation Analysis This appendix presents the radon emanation analyses performed in support of the EE/CA for the Ross-Adams Mine Site. The radon emanation analyses were used to determine

More information

Novel Technologies for In-field Gamma Spectrometry

Novel Technologies for In-field Gamma Spectrometry Novel Technologies for In-field Gamma Spectrometry Harri Toivonen HT Nuclear Ltd, Finland Coordinator of ERNCIP Radiological and Nuclear Thematic Group NKS Seminar, Roskilde, Denmark, 19-20 Sep 2017 This

More information

A Further Study on Large Size LSO and LYSO Crystal Samples

A Further Study on Large Size LSO and LYSO Crystal Samples October 25, 2005 IEEE NSS, N12-6, Puerto-Rico 1 A Further Study on Large Size LSO and LYSO Crystal Samples Jianming Chen, Liyuan Zhang, Ren-yuan Zhu California Institute of Technology BGO, LSO & LYSO Samples

More information

Lecture 09. Lidar Simulation and Error Analysis Overview (1)

Lecture 09. Lidar Simulation and Error Analysis Overview (1) Lecture 09. Lidar Simulation and Error Analysis Overview (1) Introduction Lidar Modeling via Lidar Simulation & Error Analysis Functions of Lidar Simulation and Error Analysis How to Build up Lidar Simulation?

More information

LA ICP MS Analysis with

LA ICP MS Analysis with LA ICP MS Analysis with V 1.0.4 04.06.2008 Software written by Murray Allan at Die Eidgenössische Technische Hochschule Zürich, CH and the University of Leeds, UK Additional Software writing: Dimitri Meier

More information

CONCEPTUAL DATA MODELING OF THE INTEGRATED DATABASE FOR THE RADIOACTIVE WASTE MANAGEMENT

CONCEPTUAL DATA MODELING OF THE INTEGRATED DATABASE FOR THE RADIOACTIVE WASTE MANAGEMENT CONCEPTUAL DATA MODELING OF THE INTEGRATED DATABASE FOR THE RADIOACTIVE WASTE MANAGEMENT ABSTRACT H.S Park, J.S Shon, K.J Kim, J.H Park, K.P Hong, S.H, Park Korea Atomic Energy Research Institute 150 Dukjin-dong,

More information

Extremely Fast Detector for 511 kev Gamma

Extremely Fast Detector for 511 kev Gamma Extremely Fast Detector for 511 kev Gamma V. Sharyy, D. Yvon, G. Tauzin, E.Delagnes, Ph. Abbon, J P. Bard, M. Kebbiri, M. Alokhina, C. Canot IRFU, CEA D. Breton, J. Maalmi LAL,IN2P3 Journée 2015 du Labex

More information

1/4 Specifications Hidex 300 SL automatic TDCR liquid scintillation counter

1/4 Specifications Hidex 300 SL automatic TDCR liquid scintillation counter 1/4 Specification Hidex 300 SL 100-240V AC and 24 V DC. Features Model (425-201) Automatic TDCR Liquid Scintillation Counter General Description Hidex 300SL automatic TDCR liquid scintillation counter

More information

Full 3D scan of an AGATA crystal using the PSCS technique

Full 3D scan of an AGATA crystal using the PSCS technique Full 3D scan of an AGATA crystal using the PSCS technique M. Ginsz (PhD),, F. Didierjean, M.-H. Sigward, M. Filliger IPHC, Strasbourg, France 1 Gamma-ray tracking Ge spectrometers 2 PSCS technique at IPHC

More information

Lecture 24. Lidar Simulation

Lecture 24. Lidar Simulation Lecture 24. Lidar Simulation q Introduction q Lidar Modeling via Lidar Simulation & Error Analysis q Functions of Lidar Simulation and Error Analysis q How to Build up Lidar Simulation? q Range-resolved

More information

VTT Centre for Nuclear Safety. Safir 2014 Final Seminar Hanasaari, March 19-20, 2015 Wade Karlsen

VTT Centre for Nuclear Safety. Safir 2014 Final Seminar Hanasaari, March 19-20, 2015 Wade Karlsen VTT Centre for Nuclear Safety Safir 2014 Final Seminar Hanasaari, March 19-20, 2015 Wade Karlsen Reactor materials testing and research VTT has been hosting the national hot laboratory infrastructure since

More information

Detective X. Ultra High Resolution HPGe Radioisotope Identification Device. The New Gold Standard for Mission Critical Detection and Identification

Detective X. Ultra High Resolution HPGe Radioisotope Identification Device. The New Gold Standard for Mission Critical Detection and Identification Detective X Ultra High Resolution HPGe Radioisotope Identification Device The New Gold Standard for Mission Critical Detection and Identification Detective X How do you improve on The Gold Standard for

More information

SabreISC Operations Manual

SabreISC Operations Manual SabreISC Operations Manual SabreISC Operations Manual Documentation version 1.1 August 2016 Copyright Notice Copyright 2004, Bladewerx LLC. All Rights Reserved. Any technical documentation that is made

More information

DOSE CALIBRATOR LIST OF CONTENTS: CRC -55tR Dose Calibrator 2 CRC -55tWDose Calibrator/Well Counter.5. CRC -55tPETDose Calibrator 9

DOSE CALIBRATOR LIST OF CONTENTS: CRC -55tR Dose Calibrator 2 CRC -55tWDose Calibrator/Well Counter.5. CRC -55tPETDose Calibrator 9 LIST OF CONTENTS: DOSE CALIBRATOR CRC -55tR Dose Calibrator 2 CRC -55tWDose Calibrator/Well Counter.5 CRC -55tPETDose Calibrator 9 CRC -25RDose Calibrator.12 CRC -25RSoftware. 14 CRC -25R PC Series Communications

More information

Muon imaging for innovative tomography of large volume and heterogeneous cemented waste packages

Muon imaging for innovative tomography of large volume and heterogeneous cemented waste packages Muon imaging for innovative tomography of large volume and heterogeneous cemented waste packages This project has received funding from the Euratom research and training programme 2014-2018 under grant

More information

Progress of the Thomson Scattering Experiment on HSX

Progress of the Thomson Scattering Experiment on HSX Progress of the Thomson Scattering Experiment on HSX K. Zhai, F.S.B. Anderson, D.T. Anderson HSX Plasma Laboratory, UW-Madison Bill Mason PSL, UW-Madison, The Thomson scattering system being constructed

More information

Radiography and Tomography Lab 2: Computing Radiographs

Radiography and Tomography Lab 2: Computing Radiographs Radiography and Tomography Lab 2: Computing Radiographs An Abbreviated View of Radiography Transmission Radiography is the process of measuring and recording changes in a high-energy particle beam (X-rays,

More information

Exercise 16: Magnetostatics

Exercise 16: Magnetostatics Exercise 16: Magnetostatics Magnetostatics is part of the huge field of electrodynamics, founding on the well-known Maxwell-equations. Time-dependent terms are completely neglected in the computation of

More information

An Investigation into the Limitations of Tomographic Scanning for Quantitative Nondestructive Gamma-ray Measurements of High Density Radioactive Waste

An Investigation into the Limitations of Tomographic Scanning for Quantitative Nondestructive Gamma-ray Measurements of High Density Radioactive Waste An Investigation into the Limitations of Tomographic Scanning for Quantitative Nondestructive Gamma-ray Measurements of High Density Radioactive Waste S.C. Kane 1, S. Croft 1, P. McClay 1, W.F. Mueller

More information

PHYS2002 Spring 2012 Practice Exam 3 (Chs. 25, 26, 27) Constants

PHYS2002 Spring 2012 Practice Exam 3 (Chs. 25, 26, 27) Constants PHYS00 Spring 01 Practice Exam 3 (Chs. 5, 6, 7) Constants m m q q p e ε = 8.85 o o p e = 1.67 = 9.11 7 9 7 31 = + 1.60 = 1.60 μ = 4π k = 8.99 g = 9.8 m/s 1 kg 19 19 C kg T m/a N m C / N m C / C 1. A convex

More information

Medical Imaging BMEN Spring 2016

Medical Imaging BMEN Spring 2016 Name Medical Imaging BMEN 420-501 Spring 2016 Homework #4 and Nuclear Medicine Notes All questions are from the introductory Powerpoint (based on Chapter 7) and text Medical Imaging Signals and Systems,

More information

FX- FX i FX- FX i - W

FX- FX i FX- FX i - W FX-i FX-iWP Series Realizing Compact, Increasing Functions! We have developed a Miniaturized SHS (Super Hybrid Sensor) to achieve a highly compact precision balance, which is 40% lighter and 47% smaller

More information

COMPUTATIONAL SIMULATION OF BLAST LOADING IN AN OPEN CYLINDER MODEL USING ANSYS AND LS-DYNA

COMPUTATIONAL SIMULATION OF BLAST LOADING IN AN OPEN CYLINDER MODEL USING ANSYS AND LS-DYNA COMPUTATIONAL SIMULATION OF BLAST LOADING IN AN OPEN CYLINDER MODEL USING ANSYS AND LS-DYNA Ramprashad Prabhakaran Graduate Student Department of Mechanical Engineering University of Nevada, Las Vegas

More information

Genie 2000 Basic Spectroscopy Software

Genie 2000 Basic Spectroscopy Software Features Integrated data acquisition and analysis Independent support for over 250 detector inputs Networking for distributed MCA operation and centralized data management Comprehensive and flexible user

More information

illumia Plus Light Measurement Sphere Systems

illumia Plus Light Measurement Sphere Systems illumia Plus Light Measurement Sphere Systems Flexible, modular solutions with centralized data management Build a system that meets your needs Labsphere illumia Plus Light Measurement Systems offer flexibility

More information

STATISTICAL CALIBRATION: A BETTER APPROACH TO INTEGRATING SIMULATION AND TESTING IN GROUND VEHICLE SYSTEMS.

STATISTICAL CALIBRATION: A BETTER APPROACH TO INTEGRATING SIMULATION AND TESTING IN GROUND VEHICLE SYSTEMS. 2016 NDIA GROUND VEHICLE SYSTEMS ENGINEERING and TECHNOLOGY SYMPOSIUM Modeling & Simulation, Testing and Validation (MSTV) Technical Session August 2-4, 2016 - Novi, Michigan STATISTICAL CALIBRATION: A

More information

Steam Generator Replacement of the Belgian Doel 1 unit: follow-up and on site dosimetry

Steam Generator Replacement of the Belgian Doel 1 unit: follow-up and on site dosimetry Steam Generator Replacement of the Belgian Doel 1 unit: follow-up and on site dosimetry B. Walschaerts*, J. Defloor**, R. Wyckmans** * Radwaste management Decommissioning Radiation protection, Tractebel

More information

illumia plus Light Measurement Systems

illumia plus Light Measurement Systems illumia plus Light Measurement Systems Flexible, modular solutions with centralized data management FLEXIBILITY Introducing Labsphere illumia plus light measurement systems flexibility to meet your most

More information

Code characteristics

Code characteristics The PENELOPE Computer code M.J. Anagnostakis Nuclear Engineering Department National Technical University of Athens The PENELOPE code system PENetration and Energy LOss of Positrons and Electrons in matter

More information

Efficiency. Utility for registration efficiency calculation Efficiency. User s manual.

Efficiency. Utility for registration efficiency calculation Efficiency. User s manual. Efficiency Utility for registration efficiency calculation Efficiency. User s manual. ii 2015 Contacts: Baltic Scientific Instruments, Ltd. Ganibu dambis 26, Riga, Latvia. LV-1005 WWW: http://www.bsi.lv

More information

HygroClip DIGITAL Humidity and temperature probe

HygroClip DIGITAL Humidity and temperature probe HygroClip DIGITAL Humidity and temperature probe 2016 ROTRONIC AG Bassersdorf Switzerland Contents 1 Overview... 3 1.1 Hardware and software compatibility... 3 2 Variants... 4 3 General information...

More information