ENTRY 23434 20180922 22722343400000001 SUBENT 23434001 20180922 22722343400100001 BIB 13 93 2343400100002 TITLE Measurement of kerma factors for carbon and A-150 2343400100003 plastic: neutron energies from 13.9 to 20.0 MeV 2343400100004 AUTHOR (P.Pihet, S.Guldbakke, H.G.Menzel, H.Schuhmacher) 2343400100005 INSTITUTE (2GERPTB) H.Schuhmacher, S.Guldbakke 2343400100006 (2GERSBU) P.Pihet 2343400100007 (2ZZZGEL) H.G.Menzel 2343400100008 REFERENCE (J,PMB,37,1957,1992) 2343400100009 REL-REF (R,,H.G.Menzel+,J,PMB,29,1537,1984) 2343400100010 Ionization yields distributions measured by TEPC 2343400100011 (M,,G.Buehler+,J,RPD,13,13,1985) =R,EUR-9644,13,1985 2343400100012 Neutron interaction data in carbon derived from 2343400100013 measured and calculated ionization yield spectra,Proc. 2343400100014 of 9th Symp. on Microdosimetry (Toulouse,1985) 2343400100015 Ionization yields distributions measured by CPC 2343400100016 (N,,G.Dietze+,R,PTB-N-22,1982) PTB-ND-22,1982 2343400100017 Monte Carlo code NRESP 2343400100018 . J.L.Gammel,The n-p total and differential cross 2343400100019 section in the energy range 0 to 40 MeV, Fast Neutron 2343400100020 Physics, part II: experiments and Theory, 2343400100021 ed. J.B.Marion, J.L.Fowler,New York, pp.2185-226,1960 2343400100022 Empirical formula 2343400100023 (R,,R.S.Caswell+,J,RR,83,217,1980) 2343400100024 Kerma factors for C and A-150 used in correction 2343400100025 (R,,G.Burger+,R,STI/PUB-741,225,1987) 2343400100026 W-values for Wn determination 2343400100027 (R,,M.Drosg+,R,IAEA-TECDOC-273,83,1987) 2343400100028 FACILITY (ACCEL,2GERPTB) 2343400100029 INC-SOURCE (D-T) Air-cooled thin layers of tritiated Ti om 0.5mm 2343400100030 backings of Al (Ed < or = 500keV) or Ag (Ed>500keV). 2343400100031 Neutrons were produced by selecting Ed and the angle 2343400100032 to the deuteron beam direction. 2343400100033 Target type : 2343400100034 T(Ti) - Ti layer 1.05mm/cm2 for Ed 0.2, 0.5, 1.263 MeV 2343400100035 T(Ti)-Ti - Ti layer 1.58mg/cm2 for Ed 2.655, 3.418 MeV 2343400100036 and blank target Ti 2343400100037 Ed,MeV Angle,deg En,MeV deltaE(FWHM),MeV 2343400100038 0.200 105.0 13.9 0.13 2343400100039 0.0 14.8 0.44 2343400100040 0.500 0.0 15.0 0.88 2343400100041 1.263 51.5 16.0 0.26 2343400100042 35.5 16.4 0.32 2343400100043 0.0 17.0 0.38 2343400100044 2.655 58.4 17.0 0.17 2343400100045 49.6 17.5 0.19 2343400100046 39.8 18.4 0.21 2343400100047 27.7 18.4 0.25 2343400100048 0.0 19.0 0.27 2343400100049 3.418 0.0 20.0 0.21 2343400100050 MONITOR (1-H-1(N,TOT),,SIG) For neutron fluence. 2343400100051 From ENDF/B-V. 2343400100052 Differential n-p CS was calculated by empirical 2343400100053 formula of Gamel. 2343400100054 METHOD (PHD) Pulse height distribution was measured to derive 2343400100055 the absorbed dose in the gas. 2343400100056 (PSD) Pulse-shape analysis - to distinguish 2343400100057 photo-induced events from neutron-induced. 2343400100058 (TOF) To determine number of neutron-induced events 2343400100059 above threshold ( corresponding to 28 keV electron 2343400100060 energy). 2343400100061 DETECTOR (TELES) Proton recoil telescope(PRT) to measure neutron2343400100062 fluence. Positioned at r=22.5cm. r**-2 dependence was 2343400100063 used to calculate the fluence at r=30cm, results were 2343400100064 normalized to the deuteron beam charge Q collected by 2343400100065 the target. 2343400100066 Consistency of PRT results was checked by calculation 2343400100067 of neutron yield using differential CS of T(d,n)4He 2343400100068 reaction ( Drosg and Schwerer) and taking into account 2343400100069 the fluence attenuation in the target backings - 2343400100070 agree within 2.% . 2343400100071 (PROPC) Low-pressure proportional spherical counters 2343400100072 made of carbon (CPC) and A-150 plastic (TEPC) to 2343400100073 determine kerma. 2343400100074 Wall (c or A-150 plastic) thickness 2.5mm. 2343400100075 Inner diameter 12.7mm. 2343400100076 Filled with propane-based gas at pressure 4.5 kPa. 2343400100077 Located at distance of 30cm from target. 2343400100078 (SCIN) NE213 scintillator of 3.81cm length, 2343400100079 3.81cm height, positioned at 400 cm from the target, 2343400100080 - for spectral neutron fluence. 2343400100081 Efficiency as function of energy was calculated by the 2343400100082 Monte Carlo code NRESP 2343400100083 CORRECTION For contribution of contaminating neutrons to the 2343400100084 measured kerma, correction factor was derived by 2343400100085 weighting neutron fluence with kerma factors of 2343400100086 Caswell+,1980 (see REL-REF) . Correction factor kc 2343400100087 <2% for CPC , <4.5% for TEPC , except at 20 MeV. 2343400100088 ANALYSIS The fluence-mean neutron energies ant their width were2343400100089 calculated from the deuteron energies and the target 2343400100090 thickness. 2343400100091 Kerma factor kf=K/F, 2343400100092 K-kinetic energy released in matter(kerma), 2343400100093 F- fluence measured. 2343400100094 HISTORY (20180922C) M.M. 2343400100095 ENDBIB 93 0 2343400100096 NOCOMMON 0 0 2343400100097 ENDSUBENT 96 0 2343400199999 SUBENT 23434002 20180922 22722343400200001 BIB 7 40 2343400200002 REACTION (6-C-12(N,TOT),,KER) Kerma factor 2343400200003 SAMPLE Graphite as CPC wall 2343400200004 MISC-COL (MISC1) neutron fluence per unit beam charge 2343400200005 (MISC2) absorbed dose per unit beam charge 2343400200006 (MISC3) Wn/Wc - ratio of average W-value for neutrons 2343400200007 to W used for calibration (100keV protons) 2343400200008 Correction factor for attenuation and 2343400200009 scattering in the detector wall and build-up cap - 2343400200010 1.010+-0.001 for En=13.9-18.1 MeV, 2343400200011 1.015+-0.002 for En=18.4-20.0 MeV. 2343400200012 (MISC4) gas-to-wall conversion factor 2343400200013 (MISC5) correction factor for low-energy neutron 2343400200014 contamination 2343400200015 REL-REF (A,,G.Buehler+,R,EUR-9762,309,1985) Proc.of 5th 2343400200016 Symp.on dosimetry, Muenchen,1984 2343400200017 (A,,G.Dietze+,W,DIETZE,1989) 2343400200018 G.Dietze,G.Buehler,H.G.Menzel,H.Schuhmacher private 2343400200019 communication. 2343400200020 (A,,P.M.DeLuca+,R,EUR-9762,309,1985) Proc.of 5th 2343400200021 Symp.on dosimetry, Muenchen,1984 2343400200022 (A,,P.M.DeLuca Jr+,J,NSE,94,192,1986) 2343400200023 (A,,C.S.Wuu+,J,MED,14,1007,1987) 2343400200024 FLAG (1.) T(Ti) neutron source target 2343400200025 (2.) T(Ti)-Ti neutron source target 2343400200026 see INC-SOURCE 2343400200027 ERR-ANALYS (ERR-T) One standard deviation, total 6.6-7.8% 2343400200028 (ERR-1,3.5,5.5) Absorbed dose reading per unit beam 2343400200029 charge 2343400200030 (ERR-2,0.3,1.5) Neutron-gamma discrimination 2343400200031 (ERR-3,0.4,0.9) Background for T(Ti)-Ti technique 2343400200032 (ERR-4,2.9,3.7) Energy required to produce an ion pare,2343400200033 Wn/Wc 2343400200034 (ERR-5,3.3,4.5) Gas-to-wall dose conversion factor 2343400200035 (ERR-6) Attenuation and scattering in the wall 2343400200036 5.8-7.1 % - kerma free-in-air, calculated by 2343400200037 uncertainties listed above 2343400200038 (ERR-7,3.0,3.4) Neutron fluence 2343400200039 (ERR-8) Contaminating neutrons 2343400200040 STATUS (TABLE) Tables 1(EN-ERR), 5 of J.Phys.in Medicine and 2343400200041 Biology,37,1957,1992 2343400200042 ENDBIB 40 0 2343400200043 COMMON 2 3 2343400200044 ERR-6 ERR-8 2343400200045 PER-CENT PER-CENT 2343400200046 0.1 1.0 2343400200047 ENDCOMMON 3 0 2343400200048 DATA 15 12 2343400200049 EN EN-RSL-FW DATA ERR-T FLAG MISC1 2343400200050 MISC1-ERR MISC2 MISC2-ERR MISC3 MISC3-ERR MISC4 2343400200051 MISC4-ERR MISC5 MISC5-ERR 2343400200052 MEV MEV PGY*CM2 PGY*CM2 NO-DIM SEE TEXT 2343400200053 SEE TEXT SEE TEXT SEE TEXT NO-DIM NO-DIM NO-DIM 2343400200054 NO-DIM NO-DIM NO-DIM 2343400200055 13.9 0.13 19.3 1.4 1. 9.24 2343400200056 0.30 220. 8. 1.047 0.037 0.767 2343400200057 0.034 1.000 0.005 2343400200058 14.8 0.44 23.8 1.9 1. 9.86 2343400200059 0.31 289. 13. 1.046 0.039 0.770 2343400200060 0.029 1.000 0.005 2343400200061 15.0 0.88 22.6 1.7 1. 14.7 2343400200062 0.5 410. 17. 1.044 0.037 0.770 2343400200063 0.031 1.000 0.005 2343400200064 16.0 0.26 24.5 1.7 1. 2.22 2343400200065 0.07 67.6 2.4 1.041 0.035 0.772 2343400200066 0.029 0.991 0.005 2343400200067 16.4 0.32 26.6 2.0 1. 2.36 2343400200068 0.07 78.1 3.8 1.040 0.035 0.773 2343400200069 0.029 0.989 0.005 2343400200070 17.0 0.38 27.9 1.9 1. 2.48 2343400200071 0.08 86.7 3.1 1.039 0.033 0.775 2343400200072 0.028 0.983 0.005 2343400200073 17.0 0.17 27.5 2.0 2. 2.05 2343400200074 0.07 69.4 2.8 1.039 0.033 0.775 2343400200075 0.028 1.000 0.005 2343400200076 17.5 0.19 27.0 2.0 2. 2.29 2343400200077 0.07 76.5 3.5 1.037 0.033 0.776 2343400200078 0.028 0.995 0.005 2343400200079 18.1 0.21 31.3 2.3 2. 2.41 2343400200080 0.08 93.9 4.0 1.035 0.032 0.777 2343400200081 0.027 0.990 0.005 2343400200082 18.4 0.25 29.3 2.0 2. 2.87 2343400200083 0.09 104. 4. 1.035 0.032 0.778 2343400200084 0.026 0.995 0.005 2343400200085 19.0 0.27 29.9 2.0 2. 3.45 2343400200086 0.11 128. 5. 1.033 0.031 0.779 2343400200087 0.026 0.989 0.005 2343400200088 20.0 0.21 32.4 2.5 2. 4.06 2343400200089 0.13 171. 9. 1.030 0.031 0.781 2343400200090 0.026 0.942 0.011 2343400200091 ENDDATA 42 0 2343400200092 ENDSUBENT 91 0 2343400299999 SUBENT 23434003 20180922 22722343400300001 BIB 7 31 2343400300002 REACTION (6-C-CMP(N,TOT),,KER) Kerma factor 2343400300003 SAMPLE A-150 plastic (77.7% - carbon, 3.5% - oxygen ) as 2343400300004 TEPC wall 2343400300005 MISC-COL (MISC1) neutron fluence per unit beam charge, 1/cm2/nC,2343400300006 (MISC2) absorbed dose per unit beam charge, pGy/nC , 2343400300007 (MISC3) Wn/Wc - ratio of average W-value for neutrons 2343400300008 to W used for calibration (100keV protons) 2343400300009 (MISC4) correction factor for attenuation and 2343400300010 scattering in the detector wall and build-up cap and 2343400300011 (MISC5) correction factor for low-energy neutron 2343400300012 contamination 2343400300013 . Gas-to-wall conversion factor 1.000+-0.010 2343400300014 REL-REF (D,,H.G.Menzel+,J,PMB,29,1537,1984) 2343400300015 Agree if take into account different Wn/Wc correction.2343400300016 FLAG (1.) T(Ti) neutron source target 2343400300017 (2.) T(Ti)-Ti neutron source target 2343400300018 see INC-SOURCE 2343400300019 ERR-ANALYS (DATA-ERR) One standard deviation, total 3.4-5.5% 2343400300020 (ERR-1,3.4,5.5) Absorbed dose reading per unit beam 2343400300021 charge 2343400300022 (ERR-2,0.2,0.5) Neutron-gamma discrimination 2343400300023 (ERR-3,0.4,0.8) Background for T(Ti)-Ti technique 2343400300024 (ERR-4) Energy required to produce an ion pare, Wn/Wc 2343400300025 (ERR-5) Gas-to-wall dose conversion factor 2343400300026 (ERR-6,0.1,0.7) Attenuation and scattering in the wall 2343400300027 3.9-6.8 % - kerma free-in-air, calculated by 2343400300028 uncertainties listed above 2343400300029 (ERR-7,3.0,3.4) Neutron fluence 2343400300030 (ERR-8,1.0,2.0) Contaminating neutrons 2343400300031 STATUS (TABLE) Tables 1(EN-ERR), 5 of J.Phys.in Medicine and 2343400300032 Biology,37,1957,1992 2343400300033 ENDBIB 31 0 2343400300034 COMMON 2 3 2343400300035 ERR-4 ERR-5 2343400300036 PER-CENT PER-CENT 2343400300037 1.3 1.0 2343400300038 ENDCOMMON 3 0 2343400300039 DATA 15 12 2343400300040 EN EN-RSL-FW DATA DATA-ERR FLAG MISC1 2343400300041 MISC1-ERR MISC2 MISC2-ERR MISC3 MISC3-ERR MISC4 2343400300042 MISC4-ERR MISC5 MISC5-ERR 2343400300043 MEV MEV PGY*CM2 PGY*CM2 NO-DIM SEE TEXT 2343400300044 SEE TEXT SEE TEXT SEE TEXT NO-DIM NO-DIM NO-DIM 2343400300045 NO-DIM NO-DIM NO-DIM 2343400300046 13.9 0.13 61.4 3.1 1. 9.24 2343400300047 0.30 572. 20. 0.982 0.012 1.010 2343400300048 0.001 1.000 0.010 2343400300049 14.8 0.44 70.1 3.5 1. 9.86 2343400300050 0.31 697. 24. 0.983 0.014 1.010 2343400300051 0.001 1.000 0.010 2343400300052 15.0 0.88 69.8 3.7 1. 14.6 2343400300053 0.5 1036. 36. 0.981 0.013 1.010 2343400300054 0.001 0.990 0.010 2343400300055 16.0 0.26 73.0 3.8 1. 2.19 2343400300056 0.07 165. 6. 0.980 0.013 1.010 2343400300057 0.001 0.982 0.010 2343400300058 16.4 0.32 71.2 3.7 1. 2.33 2343400300059 0.07 172. 6. 0.980 0.013 1.011 2343400300060 0.001 0.976 0.010 2343400300061 17.0 0.38 72.2 3.7 1. 2.47 2343400300062 0.08 188. 6. 0.980 0.012 1.014 2343400300063 0.005 0.955 0.010 2343400300064 17.0 0.17 75.7 4.2 2. 2.05 2343400300065 0.07 160. 6. 0.980 0.012 1.014 2343400300066 0.005 0.975 0.020 2343400300067 17.5 0.19 73.7 4.0 2. 2.29 2343400300068 0.07 174. 6. 0.979 0.012 1.014 2343400300069 0.005 0.974 0.019 2343400300070 18.1 0.21 77.5 4.0 2. 2.39 2343400300071 0.08 192. 7. 0.979 0.012 1.014 2343400300072 0.005 0.972 0.010 2343400300073 18.4 0.25 75.5 4.2 2. 2.87 2343400300074 0.09 225. 9. 0.979 0.013 1.017 2343400300075 0.007 0.970 0.019 2343400300076 19.0 0.27 77.0 4.0 2. 3.42 2343400300077 0.11 274. 9. 0.978 0.012 1.017 2343400300078 0.007 0.966 0.010 2343400300079 20.0 0.21 76.0 5.7 2. 4.06 2343400300080 0.13 378. 21. 0.978 0.012 1.017 2343400300081 0.007 0.822 0.030 2343400300082 ENDDATA 42 0 2343400300083 ENDSUBENT 82 0 2343400399999 SUBENT 23434004 20180922 22722343400400001 BIB 5 10 2343400400002 REACTION ((6-C-12(N,TOT),,KER)/(6-C-CMP(N,TOT),,KER)) 2343400400003 Ratio of kerma factors C/A-150 2343400400004 SAMPLE Graphite, 2343400400005 A-150 plastic (77.7% - carbon, 3.5% - oxygen ) 2343400400006 COMMENT Of authors . 2343400400007 Ratio was determined with lower uncertainty, reduced by2343400400008 correlated uncertainties in kerma measurement. 2343400400009 ERR-ANALYS (DATA-ERR) One standard deviation, total 2343400400010 STATUS (TABLE) Text, page 1971 of J.Phys.in Medicine and 2343400400011 Biology,37,1957,1992 2343400400012 ENDBIB 10 0 2343400400013 NOCOMMON 0 0 2343400400014 DATA 3 2 2343400400015 EN DATA DATA-ERR 2343400400016 MEV NO-DIM NO-DIM 2343400400017 14. 0.314 0.022 2343400400018 20. 0.426 0.039 2343400400019 ENDDATA 4 0 2343400400020 ENDSUBENT 19 0 2343400499999 ENDENTRY 4 0 2343499999999