GammaUser2014 Spectrum Analysis Exercise
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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
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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
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