ENTRY 22507 20180917 22702250700000001 SUBENT 22507001 20180917 22702250700100001 BIB 13 61 2250700100002 TITLE Experimental kerma coefficients and dose distributions 2250700100003 of C, N, O, Mg, Al, Si, Fe, Zr, A-150 plastic, Al2O3, 2250700100004 AlN, SiO2 and ZrO2 for neutron energies up to 66 MeV 2250700100005 AUTHOR (U.J.Schrewe,W.D.Newhauser,H.J.Brede,P.M.DeLuca Jr) 2250700100006 INSTITUTE (2GERPTB) Schrewe, Newhauser, Brede, and experimental 2250700100007 site 2250700100008 (1USAMGH) Newhauser, MGH, Boston, USA 2250700100009 (1USAWIS) DeLuca 2250700100010 (2SWTPSI) Paul Scherrer Institute, experimental site 2250700100011 REFERENCE (J,PMB,45,651,2000) - final publ., corrected data 2250700100012 (C,97TRIEST,2,1643,1997) Prelim. data without 2250700100013 correction on low neutron energy tail at En > 34. MeV 2250700100014 (J,AND,65,37,1997) Details of analysis, gas-to-wall 2250700100015 ratio calculation 2250700100016 REL-REF (M,,R.E.Prael+,R,LA-UR-3014,1989) Code for secondary 2250700100017 charged particles spectra calculation 2250700100018 (M,,M.D.Bethesda+,R,ICRU-63,2000) - A comprehensive 2250700100019 compilation of experimental kerma coefficients 2250700100020 including the results of the present work and an 2250700100021 extensive discussion and comparisons with theoretical 2250700100022 values were presented. 2250700100023 FACILITY (VDG,2GERPTB) .Van de Graaff accelerator for 5, 8, 2250700100024 15.0 and 17 MeV neutrons 2250700100025 (ACCEL,2SWTPSI) .For 34, 45, 66 MeV neutrons 2250700100026 INC-SOURCE (D-D) For producing neutrons with energies 5 MeV and 2250700100027 8 MeV 2250700100028 (D-T) For producing neutrons with energies 15.0 MeV 2250700100029 and 17 MeV 2250700100030 (P-BE) For producing neutrons with energies 34, 45, 2250700100031 66 MeV 2250700100032 METHOD (TOF) 2250700100033 ANALYSIS .Kerma factors are derived from absorbed dose measure- 2250700100034 ments. 2250700100035 DETECTOR (TELES,PROPC) Proton recoil telescope for pulse rate 2250700100036 calibration 2250700100037 (LONGC) Long counter for neutron flux monitoring 2250700100038 (FISCH) U-238 fission foil chamber for neutron flux 2250700100039 monitoring 2250700100040 ERR-ANALYS (ERR-T) total error includes ERR-1, ERR-3 (see 2250700100041 Subents 2-29) and: 2250700100042 (ERR-S,1.8,7.9) uncertainty in counting statistics 2250700100043 (ERR-2) uncertainty in peak fluence 2250700100044 (ERR-4) uncertainty in attenuation and scattering in 2250700100045 the low-pressure proportional counters (LPPC) wall 2250700100046 (ERR-5,0.,4.0) uncertainty in the gas-to-wall 2250700100047 conversion factor 2250700100048 (ERR-6) uncertainty in the ratio of the W value 2250700100049 averaged over the dose distribution of neutron 2250700100050 energy En and the W value of the 'edges' 2250700100051 STATUS (TABLE) Tables 2(a), 2(b) of Phys.Med.Biol.45(2000)651 2250700100052 HISTORY (20031231C) + + J.O.S. 2250700100053 (20040101U) Last checking has been done. 2250700100054 (20060605U) Corrected according to MEMO CP-E/088 2250700100055 (20150831A) SD: ERR-ANALYS, data in all Subents were 2250700100056 updated following final publ. (PMB,45,651,2000) and 2250700100057 SF8=FCT was deleted from REACTION code in Subents 2-26.2250700100058 ERR-T, ERR-2, ERR-3, ERR-4 were added to Subents 2-26. 2250700100059 COMMENT moved to Subent 1.Data units were changed in 2250700100060 Subents 002-031 (GY*M-SQ -> PGY*CM2). 2250700100061 (20180917A) SD: Data units were changed in 2250700100062 Subents 002-031 (PGY*CM2 -> FGY*M2). 2250700100063 ENDBIB 61 0 2250700100064 COMMON 1 3 2250700100065 ERR-6 2250700100066 PER-CENT 2250700100067 3.0 2250700100068 ENDCOMMON 3 0 2250700100069 ENDSUBENT 68 0 2250700199999 SUBENT 22507002 20180917 22702250700200001 BIB 6 19 2250700200002 REACTION (13-AL-CMP(N,TOT),,KER) 2250700200003 SAMPLE .Aluminum nitrate AL-N 2250700200004 Element (mass fraction): Al (0.658); N (0.342) 2250700200005 DETECTOR (PROPC) Proportional counters of nearly identical 2250700200006 design. Walls made of Al-N. 2250700200007 These are commercially available LET-1/2 counters 2250700200008 with cavity diameter 12.7 mm. Counters are operating 2250700200009 with propan-based tissue-equivalent gas mixture 2250700200010 at 90 hPa pressure 2250700200011 INC-SPECT .Monoenergetic neutron beam 2250700200012 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250700200013 (low energy neutron background was not subtracted at 2250700200014 En between 5 and 17 MeV) 2250700200015 HISTORY (20060605A) Sample keyword added 2250700200016 (20150831A) SD: Data were updated following final publ.2250700200017 (PMB,45,651) SF8=FCT was deleted from REACTION code. 2250700200018 SAMPLE updated. En=14.8 -> 15.MeV. Second reaction 2250700200019 code deleted following final publ. 2250700200020 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250700200021 ENDBIB 19 0 2250700200022 COMMON 3 3 2250700200023 ERR-1 ERR-2 ERR-4 2250700200024 PER-CENT PER-CENT PER-CENT 2250700200025 1.5 2.0 3.0 2250700200026 ENDCOMMON 3 0 2250700200027 DATA 3 4 2250700200028 EN DATA ERR-T 2250700200029 MEV FGY*M2 FGY*M2 2250700200030 5.0 0.759 0.047 2250700200031 8.0 0.583 0.037 2250700200032 15.0 1.794 0.105 2250700200033 17.0 2.055 0.138 2250700200034 ENDDATA 6 0 2250700200035 ENDSUBENT 34 0 2250700299999 SUBENT 22507003 20180917 22702250700300001 BIB 6 17 2250700300002 REACTION (13-AL-27(N,TOT),,KER) 2250700300003 SAMPLE Aluminium 2250700300004 DETECTOR (PROPC) Proportional counters of nearly identical 2250700300005 design. Walls made of Al. 2250700300006 These are commercially available LET-1/2 counters 2250700300007 with cavity diameter 12.7 mm. Counters are operating 2250700300008 with propan-based tissue-equivalent gas mixture 2250700300009 at 90 hPa pressure 2250700300010 INC-SPECT .Monoenergetic neutron beam 2250700300011 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250700300012 (low energy neutron background was not subtracted at 2250700300013 En between 5 and 17 MeV) 2250700300014 HISTORY (20150831A) SD: Data were updated following final publ.2250700300015 (PMB,45,651) SF8=FCT was deleted from REACTION code. 2250700300016 SAMPLE added. En=14.8 -> 15.MeV. Second reaction 2250700300017 code deleted following final publ. 2250700300018 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250700300019 ENDBIB 17 0 2250700300020 COMMON 3 3 2250700300021 ERR-1 ERR-2 ERR-4 2250700300022 PER-CENT PER-CENT PER-CENT 2250700300023 1.5 2.0 3.0 2250700300024 ENDCOMMON 3 0 2250700300025 DATA 3 4 2250700300026 EN DATA ERR-T 2250700300027 MEV FGY*M2 FGY*M2 2250700300028 5.0 0.196 0.014 2250700300029 8.0 0.438 0.028 2250700300030 15.0 1.140 0.065 2250700300031 17.0 1.436 0.102 2250700300032 ENDDATA 6 0 2250700300033 ENDSUBENT 32 0 2250700399999 SUBENT 22507004 20180917 22702250700400001 BIB 6 13 2250700400002 REACTION (7-N-14(N,TOT),,KER,,,DERIV) 2250700400003 ANALYSIS .Derived from data for aluminium and aluminium nitrate 2250700400004 INC-SPECT .Monoenergetic neutron beam 2250700400005 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250700400006 (low energy neutron background was not subtracted at 2250700400007 En between 5 and 17 MeV) 2250700400008 STATUS (DEP,22507002) kerma factor for AlN 2250700400009 (DEP,22507003) kerma factor for Al 2250700400010 HISTORY (20150831A) SD: Data were updated following final publ.2250700400011 (PMB,45,651) SF8=FCT was deleted from REACTION code. 2250700400012 SAMPLE updated. En=14.8 -> 15.MeV. Second reaction 2250700400013 code deleted following final publ. 2250700400014 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250700400015 ENDBIB 13 0 2250700400016 COMMON 3 3 2250700400017 ERR-1 ERR-2 ERR-4 2250700400018 PER-CENT PER-CENT PER-CENT 2250700400019 1.5 2.0 3.0 2250700400020 ENDCOMMON 3 0 2250700400021 DATA 3 4 2250700400022 EN DATA ERR-T 2250700400023 MEV FGY*M2 FGY*M2 2250700400024 5.0 1.844 0.135 2250700400025 8.0 0.863 0.112 2250700400026 15.0 3.054 0.309 2250700400027 17.0 3.247 0.399 2250700400028 ENDDATA 6 0 2250700400029 ENDSUBENT 28 0 2250700499999 SUBENT 22507005 20180917 22702250700500001 BIB 6 17 2250700500002 REACTION (13-AL-OXI(N,TOT),,KER) 2250700500003 SAMPLE .Al2O3, element (mass fraction): Al (0.529); O (0.471) 2250700500004 DETECTOR (PROPC) Proportional counters of nearly identical 2250700500005 design. Walls made of aluminium oxide. 2250700500006 These are commercially available LET-1/2 counters 2250700500007 with cavity diameter 12.7 mm. Counters are operating 2250700500008 with propan-based tissue-equivalent gas mixture 2250700500009 at 90 hPa pressure 2250700500010 INC-SPECT .Monoenergetic neutron beam 2250700500011 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250700500012 (low energy neutron background was not subtracted at 2250700500013 En between 5 and 17 MeV) 2250700500014 HISTORY (20150831A) SD: Data were updated following final publ.2250700500015 (PMB,45,651) SF8=FCT was deleted from REACTION code. 2250700500016 SAMPLE updated. En=14.8 -> 15.MeV. Second reaction 2250700500017 code deleted following final publ. 2250700500018 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250700500019 ENDBIB 17 0 2250700500020 COMMON 3 3 2250700500021 ERR-1 ERR-2 ERR-4 2250700500022 PER-CENT PER-CENT PER-CENT 2250700500023 1.5 2.0 3.0 2250700500024 ENDCOMMON 3 0 2250700500025 DATA 3 4 2250700500026 EN DATA ERR-T 2250700500027 MEV FGY*M2 FGY*M2 2250700500028 5.0 0.402 0.025 2250700500029 8.0 0.641 0.040 2250700500030 15.0 1.753 0.099 2250700500031 17.0 1.915 0.129 2250700500032 ENDDATA 6 0 2250700500033 ENDSUBENT 32 0 2250700599999 SUBENT 22507006 20180917 22702250700600001 BIB 6 17 2250700600002 REACTION (14-SI-OXI(N,TOT),,KER) 2250700600003 SAMPLE .SiO2, Element (mass fraction): Si (0.467) O (0.533) 2250700600004 DETECTOR (PROPC) Proportional counters of nearly identical 2250700600005 design. Walls made of silicon oxide. 2250700600006 These are commercially available LET-1/2 counters 2250700600007 with cavity diameter 12.7 mm. Counters are operating 2250700600008 with propan-based tissue-equivalent gas mixture 2250700600009 at 90 hPa pressure 2250700600010 INC-SPECT .Monoenergetic neutron beam 2250700600011 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250700600012 (low energy neutron background was not subtracted at 2250700600013 En between 5 and 17 MeV) 2250700600014 HISTORY (20150831A) SD: Data were updated following final publ.2250700600015 (PMB,45,651) SF8=FCT was deleted from REACTION code. 2250700600016 SAMPLE updated. En=14.8 -> 15.MeV. Second reaction 2250700600017 code deleted following final publ. 2250700600018 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250700600019 ENDBIB 17 0 2250700600020 COMMON 3 3 2250700600021 ERR-1 ERR-2 ERR-4 2250700600022 PER-CENT PER-CENT PER-CENT 2250700600023 1.5 2.0 3.0 2250700600024 ENDCOMMON 3 0 2250700600025 DATA 3 4 2250700600026 EN DATA ERR-T 2250700600027 MEV FGY*M2 FGY*M2 2250700600028 5.0 0.406 0.026 2250700600029 8.0 0.757 0.048 2250700600030 15.0 1.914 0.137 2250700600031 17.0 2.048 0.143 2250700600032 ENDDATA 6 0 2250700600033 ENDSUBENT 32 0 2250700699999 SUBENT 22507007 20180917 22702250700700001 BIB 6 17 2250700700002 REACTION (14-SI-0(N,TOT),,KER) 2250700700003 SAMPLE Silicon 2250700700004 DETECTOR (PROPC) Proportional counters of nearly identical 2250700700005 design. Walls made of silicon 2250700700006 these are commercially available LET-1/2 counters 2250700700007 with cavity diameter 12.7 mm. Counters are operating 2250700700008 with propan-based tissue-equivalent gas mixture 2250700700009 at 90 hPa pressure 2250700700010 INC-SPECT .Monoenergetic neutron beam 2250700700011 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250700700012 (low energy neutron background was not subtracted at 2250700700013 En between 5 and 17 MeV) 2250700700014 HISTORY (20150831A) SD: Data were updated following final publ.2250700700015 (PMB,45,651) SF8=FCT was deleted from REACTION code. 2250700700016 SAMPLE updated. En=14.8 -> 15.MeV. Second reaction 2250700700017 code deleted following final publ. STATUS 'DEP' deleted2250700700018 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250700700019 ENDBIB 17 0 2250700700020 COMMON 3 3 2250700700021 ERR-1 ERR-2 ERR-4 2250700700022 PER-CENT PER-CENT PER-CENT 2250700700023 1.5 2.0 3.0 2250700700024 ENDCOMMON 3 0 2250700700025 DATA 3 4 2250700700026 EN DATA ERR-T 2250700700027 MEV FGY*M2 FGY*M2 2250700700028 5.0 0.175 0.011 2250700700029 8.0 0.812 0.054 2250700700030 15.0 1.436 0.124 2250700700031 17.0 1.571 0.136 2250700700032 ENDDATA 6 0 2250700700033 ENDSUBENT 32 0 2250700799999 SUBENT 22507008 20180917 22702250700800001 BIB 6 16 2250700800002 REACTION (8-O-16(N,TOT),,KER,,,DERIV) 2250700800003 ANALYSIS .Derived from pairs of aluminium oxide/aluminium and 2250700800004 silicon oxide/ silicon 2250700800005 INC-SPECT .Monoenergetic neutron beam 2250700800006 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250700800007 (low energy neutron background was not subtracted at 2250700800008 En between 5 and 17 MeV) 2250700800009 STATUS (DEP,22507030) kerma factor obtained from 2250700800010 pair of Si and SiO2 2250700800011 (DEP,22507031) kerma factor obtained from 2250700800012 pair of Al and AlO2 2250700800013 HISTORY (20150831A) SD: Data were updated following final publ.2250700800014 (PMB,45,651), SF8=FCT was deleted from REACTION code. 2250700800015 En=14.8 -> 15.MeV. Second reaction code deleted 2250700800016 following final publ. 2250700800017 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250700800018 ENDBIB 16 0 2250700800019 COMMON 3 3 2250700800020 ERR-1 ERR-2 ERR-4 2250700800021 PER-CENT PER-CENT PER-CENT 2250700800022 1.5 2.0 3.0 2250700800023 ENDCOMMON 3 0 2250700800024 DATA 3 4 2250700800025 EN DATA ERR-T 2250700800026 MEV FGY*M2 FGY*M2 2250700800027 5.0 0.620 0.037 2250700800028 8.0 0.798 0.066 2250700800029 15.0 2.403 0.170 2250700800030 17.0 2.460 0.200 2250700800031 ENDDATA 6 0 2250700800032 ENDSUBENT 31 0 2250700899999 SUBENT 22507009 20180917 22702250700900001 BIB 6 17 2250700900002 REACTION (12-MG-0(N,TOT),,KER) 2250700900003 SAMPLE Magnesium 2250700900004 DETECTOR (PROPC) Proportional counters of nearly identical 2250700900005 design. Walls made of magnesium 2250700900006 these are commercially available LET-1/2 counters 2250700900007 with cavity diameter 12.7 mm. Counters are operating 2250700900008 with propan-based tissue-equivalent gas mixture 2250700900009 at 90 hPa pressure 2250700900010 INC-SPECT .Monoenergetic neutron beam 2250700900011 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250700900012 (low energy neutron background was not subtracted at 2250700900013 En between 5 and 17 MeV) 2250700900014 HISTORY (20150831A) SD: Data were updated following final publ.2250700900015 (PMB,45,651) SF8=FCT was deleted from REACTION code. 2250700900016 SAMPLE updated. En=14.8 -> 15.MeV. Second reaction 2250700900017 code deleted following final publ. 2250700900018 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250700900019 ENDBIB 17 0 2250700900020 COMMON 3 3 2250700900021 ERR-1 ERR-2 ERR-4 2250700900022 PER-CENT PER-CENT PER-CENT 2250700900023 1.5 2.0 3.0 2250700900024 ENDCOMMON 3 0 2250700900025 DATA 3 4 2250700900026 EN DATA ERR-T 2250700900027 MEV FGY*M2 FGY*M2 2250700900028 5.0 0.229 0.015 2250700900029 8.0 0.716 0.048 2250700900030 15.0 1.382 0.082 2250700900031 17.0 1.661 0.103 2250700900032 ENDDATA 6 0 2250700900033 ENDSUBENT 32 0 2250700999999 SUBENT 22507010 20180917 22702250701000001 BIB 6 17 2250701000002 REACTION (6-C-12(N,TOT),,KER) 2250701000003 SAMPLE graphite 2250701000004 DETECTOR (PROPC) Proportional counters of nearly identical 2250701000005 design. Walls made of carbon 2250701000006 these are commercially available LET-1/2 counters 2250701000007 with cavity diameter 12.7 mm. Counters are operating 2250701000008 with propan-based tissue-equivalent gas mixture 2250701000009 at 90 hPa pressure 2250701000010 INC-SPECT .Monoenergetic neutron beam 2250701000011 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250701000012 (low energy neutron background was not subtracted at 2250701000013 En between 5 and 17 MeV) 2250701000014 HISTORY (20150831A) SD: Data were updated following final publ.2250701000015 (PMB,45,651) SF8=FCT was deleted from REACTION code. 2250701000016 SAMPLE updated. En=14.8 -> 15.MeV. Second reaction 2250701000017 code deleted following final publ. 2250701000018 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250701000019 ENDBIB 17 0 2250701000020 COMMON 3 3 2250701000021 ERR-1 ERR-2 ERR-4 2250701000022 PER-CENT PER-CENT PER-CENT 2250701000023 1.5 2.0 3.0 2250701000024 ENDCOMMON 3 0 2250701000025 DATA 3 4 2250701000026 EN DATA ERR-T 2250701000027 MEV FGY*M2 FGY*M2 2250701000028 5.0 0.489 0.032 2250701000029 8.0 1.103 0.071 2250701000030 15.0 2.191 0.126 2250701000031 17.0 2.909 0.202 2250701000032 ENDDATA 6 0 2250701000033 ENDSUBENT 32 0 2250701099999 SUBENT 22507011 20180917 22702250701100001 BIB 6 17 2250701100002 REACTION (26-FE-0(N,TOT),,KER) 2250701100003 SAMPLE Iron 2250701100004 DETECTOR (PROPC) Proportional counters of nearly identical 2250701100005 design. Walls made of iron 2250701100006 these are commercially available LET-1/2 counters 2250701100007 with cavity diameter 12.7 mm. Counters are operating 2250701100008 with propan-based tissue-equivalent gas mixture 2250701100009 at 90 hPa pressure 2250701100010 INC-SPECT .Monoenergetic neutron beam 2250701100011 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250701100012 (low energy neutron background was not subtracted at 2250701100013 En between 5 and 17 MeV) 2250701100014 HISTORY (20150831A) SD: Data were updated following final publ.2250701100015 (PMB,45,651) SF8=FCT was deleted from REACTION code. 2250701100016 SAMPLE updated. En=14.8 -> 15.MeV. Second reaction 2250701100017 code deleted following final publ. 2250701100018 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250701100019 ENDBIB 17 0 2250701100020 COMMON 3 3 2250701100021 ERR-1 ERR-2 ERR-4 2250701100022 PER-CENT PER-CENT PER-CENT 2250701100023 1.5 2.0 3.0 2250701100024 ENDCOMMON 3 0 2250701100025 DATA 3 4 2250701100026 EN DATA ERR-T 2250701100027 MEV FGY*M2 FGY*M2 2250701100028 5.0 0.144 0.009 2250701100029 8.0 0.304 0.019 2250701100030 15.0 0.537 0.036 2250701100031 17.0 0.759 0.061 2250701100032 ENDDATA 6 0 2250701100033 ENDSUBENT 32 0 2250701199999 SUBENT 22507012 20180917 22702250701200001 BIB 6 17 2250701200002 REACTION (40-ZR-0(N,TOT),,KER) 2250701200003 SAMPLE ZrO2; Element (mass fraction) Zr (0.740); O (0.260) 2250701200004 DETECTOR (PROPC) Proportional counters of nearly identical 2250701200005 design. Walls made of zirconium 2250701200006 these are commercially available LET-1/2 counters 2250701200007 with cavity diameter 12.7 mm. Counters are operating 2250701200008 with propan-based tissue-equivalent gas mixture 2250701200009 at 90 hPa pressure 2250701200010 INC-SPECT .Monoenergetic neutron beam 2250701200011 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250701200012 (low energy neutron background was not subtracted at 2250701200013 En between 5 and 17 MeV) 2250701200014 HISTORY (20150831A) SD: Data were updated following final publ.2250701200015 (PMB,45,651) SF8=FCT was deleted from REACTION code. 2250701200016 SAMPLE updated. En=14.8 -> 15.MeV. Second reaction 2250701200017 code deleted following final publ. 2250701200018 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250701200019 ENDBIB 17 0 2250701200020 COMMON 3 3 2250701200021 ERR-1 ERR-2 ERR-4 2250701200022 PER-CENT PER-CENT PER-CENT 2250701200023 1.5 2.0 3.0 2250701200024 ENDCOMMON 3 0 2250701200025 DATA 3 4 2250701200026 EN DATA ERR-T 2250701200027 MEV FGY*M2 FGY*M2 2250701200028 5.0 0.102 0.006 2250701200029 8.0 0.145 0.009 2250701200030 15.0 0.287 0.019 2250701200031 17.0 0.313 0.025 2250701200032 ENDDATA 6 0 2250701200033 ENDSUBENT 32 0 2250701299999 SUBENT 22507013 20180917 22702250701300001 BIB 6 18 2250701300002 REACTION (6-C-CMP(N,TOT),,KER) 2250701300003 SAMPLE A-150 plastic (76.8% - carbon) 2250701300004 DETECTOR (PROPC) Proportional counters of nearly identical 2250701300005 design. Walls made of a-150 = tissue- equivalent 2250701300006 plastic 2250701300007 these are commercially available LET-1/2 counters 2250701300008 with cavity diameter 12.7 mm. Counters are operating 2250701300009 with propan-based tissue-equivalent gas mixture 2250701300010 at 90 hPa pressure 2250701300011 INC-SPECT .Monoenergetic neutron beam 2250701300012 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250701300013 (low energy neutron background was not subtracted at 2250701300014 En between 5 and 17 MeV) 2250701300015 HISTORY (20150831A) SD: Data were updated following final publ.2250701300016 (PMB,45,651) SF8=FCT was deleted from REACTION code. 2250701300017 SAMPLE updated. En=14.8 -> 15.MeV. Second reaction 2250701300018 code deleted following final publ. 2250701300019 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250701300020 ENDBIB 18 0 2250701300021 COMMON 3 3 2250701300022 ERR-1 ERR-2 ERR-4 2250701300023 PER-CENT PER-CENT PER-CENT 2250701300024 1.5 2.0 3.0 2250701300025 ENDCOMMON 3 0 2250701300026 DATA 3 4 2250701300027 EN DATA ERR-T 2250701300028 MEV FGY*M2 FGY*M2 2250701300029 5.0 4.546 0.323 2250701300030 8.0 5.364 0.372 2250701300031 15.0 6.732 0.517 2250701300032 17.0 7.505 0.588 2250701300033 ENDDATA 6 0 2250701300034 ENDSUBENT 33 0 2250701399999 SUBENT 22507014 20180917 22702250701400001 BIB 7 20 2250701400002 REACTION (40-ZR-OXI(N,TOT),,KER) 2250701400003 not corrected for low neutron energy tail 2250701400004 SAMPLE ZrO2, Element (mass fraction): Zr (0.740); O (0.260) 2250701400005 DETECTOR (PROPC) Proportional counters of nearly identical 2250701400006 design. Walls made of zirconium oxide. 2250701400007 These are commercially available LET-1/2 counters 2250701400008 with cavity diameter 12.7 mm. Counters are operating 2250701400009 with propan-based tissue-equivalent gas mixture 2250701400010 at 90 hPa pressure 2250701400011 INC-SPECT .Polyenergetic neutron beam 2250701400012 MISC-COL (MISC) Factors correcting the measured absorbed doses 2250701400013 for the contributions of non-peak energy neutrons 2250701400014 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250701400015 energy' neutron background 2250701400016 (ERR-3) uncertainty in attenuation in build-up caps - 2250701400017 only at 34-66 MeV 2250701400018 HISTORY (20150831A) SD: Data were updated following final publ.2250701400019 (PMB,45,651) SF8=RAW/FCT was deleted from REACTION 2250701400020 code. SAMPLE added. 2250701400021 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250701400022 ENDBIB 20 0 2250701400023 NOCOMMON 0 0 2250701400024 DATA 7 1 2250701400025 EN DATA ERR-T ERR-2 ERR-3 ERR-4 2250701400026 MISC 2250701400027 MEV FGY*M2 FGY*M2 PER-CENT PER-CENT PER-CENT 2250701400028 NO-DIM 2250701400029 44. 2.10 0.21 6.4 2.0 2.0 2250701400030 0.66 2250701400031 ENDDATA 6 0 2250701400032 ENDSUBENT 31 0 2250701499999 SUBENT 22507015 20180917 22702250701500001 BIB 7 19 2250701500002 REACTION (14-SI-OXI(N,TOT),,KER) 2250701500003 SAMPLE SiO2, Element (mass fraction): Si (0.467); O (0.533) 2250701500004 DETECTOR (PROPC) Proportional counters of nearly identical 2250701500005 design. Walls made of silicon oxide. 2250701500006 These are commercially available LET-1/2 counters 2250701500007 with cavity diameter 12.7 mm. Counters are operating 2250701500008 with propan-based tissue-equivalent gas mixture 2250701500009 at 90 hPa pressure 2250701500010 INC-SPECT .Polyenergetic neutron beam 2250701500011 MISC-COL (MISC) Factors correcting the measured absorbed doses 2250701500012 for the contributions of non-peak energy neutrons 2250701500013 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250701500014 energy' neutron background 2250701500015 (ERR-3) uncertainty in attenuation in build-up caps - 2250701500016 only at 34-66 MeV 2250701500017 HISTORY (20150831A) SD: Data were updated following final publ.2250701500018 (PMB,45,651) SF8=RAW/FCT was deleted from REACTION 2250701500019 code. SAMPLE added. 2250701500020 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250701500021 ENDBIB 19 0 2250701500022 COMMON 2 3 2250701500023 ERR-3 ERR-4 2250701500024 PER-CENT PER-CENT 2250701500025 2.0 2.0 2250701500026 ENDCOMMON 3 0 2250701500027 DATA 5 3 2250701500028 EN DATA ERR-T ERR-2 MISC 2250701500029 MEV FGY*M2 FGY*M2 PER-CENT NO-DIM 2250701500030 34. 3.62 0.29 5.4 0.69 2250701500031 44. 3.99 0.34 6.4 0.62 2250701500032 66. 4.77 0.42 7.2 0.56 2250701500033 ENDDATA 5 0 2250701500034 ENDSUBENT 33 0 2250701599999 SUBENT 22507016 20180917 22702250701600001 BIB 7 19 2250701600002 REACTION (13-AL-OXI(N,TOT),,KER) 2250701600003 SAMPLE .Al2O3, Element (mass fraction): Al (0.529); O (0.471) 2250701600004 DETECTOR (PROPC) Proportional counters of nearly identical 2250701600005 design. Walls made of aluminium oxide. 2250701600006 These are commercially available LET-1/2 counters 2250701600007 with cavity diameter 12.7 mm. Counters are operating 2250701600008 with propan-based tissue-equivalent gas mixture 2250701600009 at 90 hPa pressure 2250701600010 INC-SPECT .Polyenergetic neutron beam 2250701600011 MISC-COL (MISC) Factors correcting the measured absorbed doses 2250701600012 for the contributions of non-peak energy neutrons 2250701600013 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250701600014 energy' neutron background 2250701600015 (ERR-3) uncertainty in attenuation in build-up caps - 2250701600016 only at 34-66 MeV 2250701600017 HISTORY (20150831A) SD: Data were updated following final publ.2250701600018 (PMB,45,651) SF8=RAW/FCT was deleted from REACTION 2250701600019 code. SAMPLE added. 2250701600020 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250701600021 ENDBIB 19 0 2250701600022 COMMON 2 3 2250701600023 ERR-3 ERR-4 2250701600024 PER-CENT PER-CENT 2250701600025 2.0 2.0 2250701600026 ENDCOMMON 3 0 2250701600027 DATA 5 3 2250701600028 EN DATA ERR-T ERR-2 MISC 2250701600029 MEV FGY*M2 FGY*M2 PER-CENT NO-DIM 2250701600030 34. 3.31 0.26 5.4 0.70 2250701600031 44. 3.77 0.32 6.4 0.64 2250701600032 66. 4.85 0.43 7.2 0.57 2250701600033 ENDDATA 5 0 2250701600034 ENDSUBENT 33 0 2250701699999 SUBENT 22507017 20180917 22702250701700001 BIB 6 19 2250701700002 REACTION (13-AL-CMP(N,TOT),,KER) 2250701700003 SAMPLE .Aluminum nitrate AL-N 2250701700004 Element (mass fraction): Al (0.658); N (0.342) 2250701700005 DETECTOR (PROPC) Proportional counters of nearly identical 2250701700006 design. Walls made of aluminium nitrate. 2250701700007 These are commercially available LET-1/2 counters 2250701700008 with cavity diameter 12.7 mm. Counters are operating 2250701700009 with propan-based tissue-equivalent gas mixture 2250701700010 at 90 hPa pressure 2250701700011 INC-SPECT .Polyenergetic neutron beam 2250701700012 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250701700013 energy' neutron background 2250701700014 (ERR-3) uncertainty in attenuation in build-up caps - 2250701700015 only at 34-66 MeV 2250701700016 HISTORY (20060605U) Sample keyword added 2250701700017 (20150831A) SD: Data were updated following final publ.2250701700018 (PMB,45,651) SF8=RAW/FCT was deleted from REACTION 2250701700019 code. SAMPLE added. 2250701700020 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250701700021 ENDBIB 19 0 2250701700022 COMMON 2 3 2250701700023 ERR-3 ERR-4 2250701700024 PER-CENT PER-CENT 2250701700025 2.0 2.0 2250701700026 ENDCOMMON 3 0 2250701700027 DATA 5 3 2250701700028 EN DATA ERR-T ERR-2 MISC 2250701700029 MEV FGY*M2 FGY*M2 PER-CENT NO-DIM 2250701700030 34. 3.33 0.26 5.4 0.70 2250701700031 44. 3.93 0.31 6.4 0.64 2250701700032 66. 4.57 0.41 7.2 0.56 2250701700033 ENDDATA 5 0 2250701700034 ENDSUBENT 33 0 2250701799999 SUBENT 22507018 20180917 22702250701800001 BIB 7 20 2250701800002 REACTION (6-C-CMP(N,TOT),,KER) 2250701800003 SAMPLE A-150 plastic (76.8% - carbon) 2250701800004 DETECTOR (PROPC) Proportional counters of nearly identical 2250701800005 design. Walls made of a-150 = tissue-equivalent 2250701800006 plastic 2250701800007 these are commercially available LET-1/2 counters 2250701800008 with cavity diameter 12.7 mm. Counters are operating 2250701800009 with propan-based tissue-equivalent gas mixture 2250701800010 at 90 hPa pressure 2250701800011 INC-SPECT .Polyenergetic neutron beam 2250701800012 MISC-COL (MISC) Factors correcting the measured absorbed doses 2250701800013 for the contributions of non-peak energy neutrons 2250701800014 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250701800015 energy' neutron background 2250701800016 (ERR-3) uncertainty in attenuation in build-up caps - 2250701800017 only at 34-66 MeV 2250701800018 HISTORY (20150831A) SD: Data were updated following final publ.2250701800019 (PMB,45,651) SF8=RAW/FCT was deleted from REACTION 2250701800020 code. SAMPLE added. 2250701800021 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250701800022 ENDBIB 20 0 2250701800023 COMMON 2 3 2250701800024 ERR-3 ERR-4 2250701800025 PER-CENT PER-CENT 2250701800026 2.0 2.0 2250701800027 ENDCOMMON 3 0 2250701800028 DATA 5 3 2250701800029 EN DATA ERR-T ERR-2 MISC 2250701800030 MEV FGY*M2 FGY*M2 PER-CENT NO-DIM 2250701800031 34. 8.67 0.74 5.4 0.57 2250701800032 44. 8.07 0.79 6.4 0.49 2250701800033 66. 7.95 0.74 7.2 0.44 2250701800034 ENDDATA 5 0 2250701800035 ENDSUBENT 34 0 2250701899999 SUBENT 22507019 20180917 22702250701900001 BIB 6 17 2250701900002 REACTION (40-ZR-0(N,TOT),,KER) 2250701900003 SAMPLE Zirconium 2250701900004 DETECTOR (PROPC) Proportional counters of nearly identical 2250701900005 design. Walls made of zirconium 2250701900006 these are commercially available LET-1/2 counters 2250701900007 with cavity diameter 12.7 mm. Counters are operating 2250701900008 with propan-based tissue-equivalent gas mixture 2250701900009 at 90 hPa pressure 2250701900010 INC-SPECT .Polyenergetic neutron beam 2250701900011 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250701900012 energy' neutron background 2250701900013 (ERR-3) uncertainty in attenuation in build-up caps - 2250701900014 only at 34-66 MeV 2250701900015 HISTORY (20150831A) SD: Data were updated following final publ.2250701900016 (PMB,45,651) SF8=RAW/FCT was deleted from REACTION 2250701900017 code. SAMPLE added. 2250701900018 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250701900019 ENDBIB 17 0 2250701900020 COMMON 2 3 2250701900021 ERR-3 ERR-4 2250701900022 PER-CENT PER-CENT 2250701900023 2.0 2.0 2250701900024 ENDCOMMON 3 0 2250701900025 DATA 5 3 2250701900026 EN DATA ERR-T ERR-2 MISC 2250701900027 MEV FGY*M2 FGY*M2 PER-CENT NO-DIM 2250701900028 34. 0.80 0.06 5.4 0.77 2250701900029 44. 1.27 0.11 6.4 0.71 2250701900030 66. 1.76 0.17 7.2 0.64 2250701900031 ENDDATA 5 0 2250701900032 ENDSUBENT 31 0 2250701999999 SUBENT 22507020 20180917 22702250702000001 BIB 7 19 2250702000002 REACTION (26-FE-0(N,TOT),,KER) 2250702000003 SAMPLE Iron 2250702000004 DETECTOR (PROPC) Proportional counters of nearly identical 2250702000005 design. Walls made of iron 2250702000006 these are commercially available LET-1/2 counters 2250702000007 with cavity diameter 12.7 mm. Counters are operating 2250702000008 with propan-based tissue-equivalent gas mixture 2250702000009 at 90 hPa pressure 2250702000010 INC-SPECT .Polyenergetic neutron beam 2250702000011 MISC-COL (MISC) Factors correcting the measured absorbed doses 2250702000012 for the contributions of non-peak energy neutrons 2250702000013 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250702000014 energy' neutron background 2250702000015 (ERR-3) uncertainty in attenuation in build-up caps - 2250702000016 only at 34-66 MeV 2250702000017 HISTORY (20150831A) SD: Data were updated following final publ.2250702000018 (PMB,45,651) SF8=RAW/FCT was deleted from REACTION 2250702000019 code. SAMPLE added. 2250702000020 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250702000021 ENDBIB 19 0 2250702000022 COMMON 2 3 2250702000023 ERR-3 ERR-4 2250702000024 PER-CENT PER-CENT 2250702000025 2.0 2.0 2250702000026 ENDCOMMON 3 0 2250702000027 DATA 5 3 2250702000028 EN DATA ERR-T ERR-2 MISC 2250702000029 MEV FGY*M2 FGY*M2 PER-CENT NO-DIM 2250702000030 34. 1.64 0.12 5.4 0.77 2250702000031 44. 2.21 0.25 6.4 0.72 2250702000032 66. 2.74 0.25 7.2 0.65 2250702000033 ENDDATA 5 0 2250702000034 ENDSUBENT 33 0 2250702099999 SUBENT 22507021 20180917 22702250702100001 BIB 7 19 2250702100002 REACTION (14-SI-0(N,TOT),,KER) 2250702100003 SAMPLE Silicon 2250702100004 DETECTOR (PROPC) Proportional counters of nearly identical 2250702100005 design. Walls made of silicon 2250702100006 these are commercially available LET-1/2 counters 2250702100007 with cavity diameter 12.7 mm. Counters are operating 2250702100008 with propan-based tissue-equivalent gas mixture 2250702100009 at 90 hPa pressure 2250702100010 INC-SPECT .Polyenergetic neutron beam 2250702100011 MISC-COL (MISC) Factors correcting the measured absorbed doses 2250702100012 for the contributions of non-peak energy neutrons 2250702100013 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250702100014 energy' neutron background 2250702100015 (ERR-3) uncertainty in attenuation in build-up caps - 2250702100016 only at 34-66 MeV 2250702100017 HISTORY (20150831A) SD: Data were updated following final publ.2250702100018 (PMB,45,651) SF8=RAW/FCT was deleted from REACTION 2250702100019 code. SAMPLE added. 2250702100020 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250702100021 ENDBIB 19 0 2250702100022 COMMON 2 3 2250702100023 ERR-3 ERR-4 2250702100024 PER-CENT PER-CENT 2250702100025 2.0 2.0 2250702100026 ENDCOMMON 3 0 2250702100027 DATA 5 3 2250702100028 EN DATA ERR-T ERR-2 MISC 2250702100029 MEV FGY*M2 FGY*M2 PER-CENT NO-DIM 2250702100030 34. 2.75 0.22 5.4 0.70 2250702100031 44. 3.05 0.34 6.4 0.64 2250702100032 66. 3.84 0.33 7.4 0.58 2250702100033 ENDDATA 5 0 2250702100034 ENDSUBENT 33 0 2250702199999 SUBENT 22507022 20180917 22702250702200001 BIB 7 19 2250702200002 REACTION (13-AL-27(N,TOT),,KER) 2250702200003 SAMPLE Aluminium 2250702200004 DETECTOR (PROPC) Proportional counters of nearly identical 2250702200005 design. Walls made of aluminium 2250702200006 these are commercially available LET-1/2 counters 2250702200007 with cavity diameter 12.7 mm. Counters are operating 2250702200008 with propan-based tissue-equivalent gas mixture 2250702200009 at 90 hPa pressure 2250702200010 INC-SPECT .Polyenergetic neutron beam 2250702200011 MISC-COL (MISC) Factors correcting the measured absorbed doses 2250702200012 for the contributions of non-peak energy neutrons 2250702200013 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250702200014 energy' neutron background 2250702200015 (ERR-3) uncertainty in attenuation in build-up caps - 2250702200016 only at 34-66 MeV 2250702200017 HISTORY (20150831A) SD: Data were updated following final publ.2250702200018 (PMB,45,651) SF8=RAW/FCT was deleted from REACTION 2250702200019 code. SAMPLE added. 2250702200020 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250702200021 ENDBIB 19 0 2250702200022 COMMON 2 3 2250702200023 ERR-3 ERR-4 2250702200024 PER-CENT PER-CENT 2250702200025 2.0 2.0 2250702200026 ENDCOMMON 3 0 2250702200027 DATA 5 3 2250702200028 EN DATA ERR-T ERR-2 MISC 2250702200029 MEV FGY*M2 FGY*M2 PER-CENT NO-DIM 2250702200030 34. 2.40 0.19 5.4 0.73 2250702200031 44. 2.82 0.24 6.4 0.66 2250702200032 66. 3.82 0.40 7.4 0.58 2250702200033 ENDDATA 5 0 2250702200034 ENDSUBENT 33 0 2250702299999 SUBENT 22507023 20180917 22702250702300001 BIB 7 19 2250702300002 REACTION (12-MG-0(N,TOT),,KER) 2250702300003 SAMPLE Magnesium 2250702300004 DETECTOR (PROPC) Proportional counters of nearly identical 2250702300005 design. Walls made of magnesium 2250702300006 these are commercially available LET-1/2 counters 2250702300007 with cavity diameter 12.7 mm. Counters are operating 2250702300008 with propan-based tissue-equivalent gas mixture 2250702300009 at 90 hPa pressure 2250702300010 INC-SPECT .Polyenergetic neutron beam 2250702300011 MISC-COL (MISC) Factors correcting the measured absorbed doses 2250702300012 for the contributions of non-peak energy neutrons 2250702300013 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250702300014 energy' neutron background 2250702300015 (ERR-3) uncertainty in attenuation in build-up caps - 2250702300016 only at 34-66 MeV 2250702300017 HISTORY (20150831A) SD: Data were updated following final publ.2250702300018 (PMB,45,651) SF8=RAW/FCT was deleted from REACTION 2250702300019 code. SAMPLE added. 2250702300020 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250702300021 ENDBIB 19 0 2250702300022 COMMON 2 3 2250702300023 ERR-3 ERR-4 2250702300024 PER-CENT PER-CENT 2250702300025 2.0 2.0 2250702300026 ENDCOMMON 3 0 2250702300027 DATA 5 3 2250702300028 EN DATA ERR-T ERR-2 MISC 2250702300029 MEV FGY*M2 FGY*M2 PER-CENT NO-DIM 2250702300030 34. 3.00 0.23 5.4 0.68 2250702300031 44. 3.36 0.29 6.4 0.64 2250702300032 66. 4.35 0.40 7.4 0.57 2250702300033 ENDDATA 5 0 2250702300034 ENDSUBENT 33 0 2250702399999 SUBENT 22507024 20180917 22702250702400001 BIB 7 19 2250702400002 REACTION (6-C-12(N,TOT),,KER) 2250702400003 SAMPLE Graphite 2250702400004 DETECTOR (PROPC) Proportional counters of nearly identical 2250702400005 design. Walls made of carbon 2250702400006 these are commercially available LET-1/2 counters 2250702400007 with cavity diameter 12.7 mm. Counters are operating 2250702400008 with propan-based tissue-equivalent gas mixture 2250702400009 at 90 hPa pressure 2250702400010 INC-SPECT .Polyenergetic neutron beam 2250702400011 MISC-COL (MISC) Factors correcting the measured absorbed doses 2250702400012 for the contributions of non-peak energy neutrons 2250702400013 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250702400014 energy' neutron background 2250702400015 (ERR-3) uncertainty in attenuation in build-up caps - 2250702400016 only at 34-66 MeV 2250702400017 HISTORY (20150831A) SD: Data were updated following final publ.2250702400018 (PMB,45,651) SF8=RAW/FCT was deleted from REACTION 2250702400019 code. SAMPLE added. 2250702400020 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250702400021 ENDBIB 19 0 2250702400022 COMMON 2 3 2250702400023 ERR-3 ERR-4 2250702400024 PER-CENT PER-CENT 2250702400025 2.0 2.0 2250702400026 ENDCOMMON 3 0 2250702400027 DATA 5 3 2250702400028 EN DATA ERR-T ERR-2 MISC 2250702400029 MEV FGY*M2 FGY*M2 PER-CENT NO-DIM 2250702400030 34. 4.38 0.35 5.4 0.69 2250702400031 44. 4.80 0.41 6.4 0.61 2250702400032 66. 5.76 0.56 7.4 0.53 2250702400033 ENDDATA 5 0 2250702400034 ENDSUBENT 33 0 2250702499999 SUBENT 22507025 20180917 22702250702500001 BIB 6 13 2250702500002 REACTION (7-N-14(N,TOT),,KER,,,DERIV) 2250702500003 ANALYSIS .Derived from data for aluminium and aluminium nitrate 2250702500004 INC-SPECT .Polyenergetic neutron beam 2250702500005 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250702500006 energy' neutron background 2250702500007 (ERR-3) uncertainty in attenuation in build-up caps - 2250702500008 only at 34-66 MeV 2250702500009 STATUS (DEP,22507017) kerma factor for AlN 2250702500010 (DEP,22507022) kerma factor for Al 2250702500011 HISTORY (20150831A) SD: Data were updated following final publ.2250702500012 (PMB,45,651) SF8=RAW/FCT was deleted and SF9=DERIV 2250702500013 was added to REACTION code. 2250702500014 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250702500015 ENDBIB 13 0 2250702500016 COMMON 2 3 2250702500017 ERR-3 ERR-4 2250702500018 PER-CENT PER-CENT 2250702500019 2.0 2.0 2250702500020 ENDCOMMON 3 0 2250702500021 DATA 4 3 2250702500022 EN DATA ERR-T ERR-2 2250702500023 MEV FGY*M2 FGY*M2 PER-CENT 2250702500024 34. 5.13 0.66 5.4 2250702500025 44. 6.07 0.72 6.4 2250702500026 66. 6.02 1.00 7.4 2250702500027 ENDDATA 5 0 2250702500028 ENDSUBENT 27 0 2250702599999 SUBENT 22507026 20180917 22702250702600001 BIB 6 15 2250702600002 REACTION (8-O-16(N,TOT),,KER,,,DERIV) 2250702600003 ANALYSIS .Derived from data for aluminium, aluminium oxide 2250702600004 INC-SPECT .Polyenergetic neutron beam 2250702600005 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250702600006 energy' neutron background 2250702600007 (ERR-3) uncertainty in attenuation in build-up caps - 2250702600008 only at 34-66 MeV 2250702600009 STATUS (DEP,22507016) kerma factor for Al2O3 2250702600010 (DEP,22507022) kerma factor for Al 2250702600011 (COREL,22507027) 2250702600012 (COREL,22507028) 2250702600013 HISTORY (20150831A) SD: Data were updated following final publ.2250702600014 (PMB,45,651) SF8=RAW/FCT was deleted and SF9=DERIV 2250702600015 was added to REACTION code. 2250702600016 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250702600017 ENDBIB 15 0 2250702600018 COMMON 2 3 2250702600019 ERR-3 ERR-4 2250702600020 PER-CENT PER-CENT 2250702600021 2.0 2.0 2250702600022 ENDCOMMON 3 0 2250702600023 DATA 4 3 2250702600024 EN DATA ERR-T ERR-2 2250702600025 MEV FGY*M2 FGY*M2 PER-CENT 2250702600026 34. 4.33 0.48 5.4 2250702600027 44. 4.84 0.56 6.4 2250702600028 66. 6.01 0.76 7.4 2250702600029 ENDDATA 5 0 2250702600030 ENDSUBENT 29 0 2250702699999 SUBENT 22507027 20180917 22702250702700001 BIB 6 13 2250702700002 REACTION (8-O-16(N,TOT),,KER,,,DERIV) 2250702700003 ANALYSIS .Derived from data for silicon and silicon oxide 2250702700004 INC-SPECT .Polyenergetic neutron beam 2250702700005 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250702700006 energy' neutron background 2250702700007 (ERR-3) uncertainty in attenuation in build-up caps - 2250702700008 only at 34-66 MeV 2250702700009 STATUS (DEP,22507015) kerma factor for SiO2 2250702700010 (DEP,22507021) kerma factor for Si 2250702700011 (COREL,22507026) 2250702700012 (COREL,22507028) 2250702700013 HISTORY (20150831C) SD 2250702700014 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250702700015 ENDBIB 13 0 2250702700016 COMMON 2 3 2250702700017 ERR-3 ERR-4 2250702700018 PER-CENT PER-CENT 2250702700019 2.0 2.0 2250702700020 ENDCOMMON 3 0 2250702700021 DATA 4 3 2250702700022 EN DATA ERR-T ERR-2 2250702700023 MEV FGY*M2 FGY*M2 PER-CENT 2250702700024 34. 4.39 0.49 5.4 2250702700025 44. 4.81 0.58 6.4 2250702700026 66. 5.60 0.62 7.4 2250702700027 ENDDATA 5 0 2250702700028 ENDSUBENT 27 0 2250702799999 SUBENT 22507028 20180917 22702250702800001 BIB 6 13 2250702800002 REACTION (8-O-16(N,TOT),,KER,,,DERIV) 2250702800003 ANALYSIS .Derived from data for zirconium, zirconium oxide 2250702800004 INC-SPECT .Polyenergetic neutron beam 2250702800005 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250702800006 energy' neutron background 2250702800007 (ERR-3) uncertainty in attenuation in build-up caps - 2250702800008 only at 34-66 MeV 2250702800009 STATUS (DEP,22507014) kerma factor for ZrO2 2250702800010 (DEP,22507019) kerma factor for Zr 2250702800011 (COREL,22507026) 2250702800012 (COREL,22507027) 2250702800013 HISTORY (20150831C) SD 2250702800014 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250702800015 ENDBIB 13 0 2250702800016 NOCOMMON 0 0 2250702800017 DATA 6 1 2250702800018 EN DATA ERR-T ERR-2 ERR-3 ERR-4 2250702800019 MEV FGY*M2 FGY*M2 PER-CENT PER-CENT PER-CENT 2250702800020 44. 4.48 0.60 6.4 2.0 2.0 2250702800021 ENDDATA 3 0 2250702800022 ENDSUBENT 21 0 2250702899999 SUBENT 22507029 20180917 22702250702900001 BIB 6 13 2250702900002 REACTION (8-O-16(N,TOT),,KER,,,DERIV) 2250702900003 ANALYSIS .Mean values derived from Al2O3/Al, SiO2/Si and 2250702900004 ZrO2/Zr-walled LPPCs 2250702900005 INC-SPECT .Polyenergetic neutron beam 2250702900006 ERR-ANALYS (ERR-1,0.1,2.0) uncertainty in subtraction of 'non-peak2250702900007 energy' neutron background 2250702900008 (ERR-3) uncertainty in attenuation in build-up caps - 2250702900009 only at 34-66 MeV 2250702900010 STATUS (DEP,22507026) kerma factor for Al2O3/Al 2250702900011 (DEP,22507027) kerma factor for SiO2/Si 2250702900012 (DEP,22507028) kerma factor for ZrO2/Zr 2250702900013 HISTORY (20150831C) SD 2250702900014 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250702900015 ENDBIB 13 0 2250702900016 COMMON 2 3 2250702900017 ERR-3 ERR-4 2250702900018 PER-CENT PER-CENT 2250702900019 2.0 2.0 2250702900020 ENDCOMMON 3 0 2250702900021 DATA 4 3 2250702900022 EN DATA ERR-T ERR-2 2250702900023 MEV FGY*M2 FGY*M2 PER-CENT 2250702900024 34. 4.36 0.38 5.4 2250702900025 44. 4.74 0.42 6.4 2250702900026 66. 5.74 0.56 7.4 2250702900027 ENDDATA 5 0 2250702900028 ENDSUBENT 27 0 2250702999999 SUBENT 22507030 20180917 22702250703000001 BIB 6 11 2250703000002 REACTION (8-O-16(N,TOT),,KER,,,DERIV) 2250703000003 ANALYSIS .Derived from data for silicon and silicon oxide 2250703000004 INC-SPECT .Monoenergetic neutron beam 2250703000005 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250703000006 (low energy neutron background was not subtracted at 2250703000007 En between 5 and 17 MeV) 2250703000008 STATUS (DEP,22507006) kerma factor for Si 2250703000009 (DEP,22507007) kerma factor for SiO2 2250703000010 (COREL,22507031) 2250703000011 HISTORY (20150831C) SD 2250703000012 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250703000013 ENDBIB 11 0 2250703000014 COMMON 3 3 2250703000015 ERR-1 ERR-2 ERR-4 2250703000016 PER-CENT PER-CENT PER-CENT 2250703000017 1.5 2.0 3.0 2250703000018 ENDCOMMON 3 0 2250703000019 DATA 3 4 2250703000020 EN DATA ERR-T 2250703000021 MEV FGY*M2 FGY*M2 2250703000022 5.0 0.609 0.048 2250703000023 8.0 0.709 0.096 2250703000024 15.0 2.335 0.268 2250703000025 17.0 2.466 0.269 2250703000026 ENDDATA 6 0 2250703000027 ENDSUBENT 26 0 2250703099999 SUBENT 22507031 20180917 22702250703100001 BIB 6 11 2250703100002 REACTION (8-O-16(N,TOT),,KER,,,DERIV) 2250703100003 ANALYSIS .Derived from data for aluminium, aluminium oxide 2250703100004 INC-SPECT .Monoenergetic neutron beam 2250703100005 ERR-ANALYS (ERR-1) uncertainty in low energy neutron background 2250703100006 (low energy neutron background was not subtracted at 2250703100007 En between 5 and 17 MeV) 2250703100008 STATUS (DEP,22507003) kerma factor for Al 2250703100009 (DEP,22507005) kerma factor for AlO2 2250703100010 (COREL,22507030) 2250703100011 HISTORY (20150831C) SD 2250703100012 (20180917A) SD: Data units changed (PGY*CM2->FGY*M2). 2250703100013 ENDBIB 11 0 2250703100014 COMMON 3 3 2250703100015 ERR-1 ERR-2 ERR-4 2250703100016 PER-CENT PER-CENT PER-CENT 2250703100017 1.5 2.0 3.0 2250703100018 ENDCOMMON 3 0 2250703100019 DATA 3 4 2250703100020 EN DATA ERR-T 2250703100021 MEV FGY*M2 FGY*M2 2250703100022 5.0 0.634 0.053 2250703100023 8.0 0.869 0.087 2250703100024 15.0 2.442 0.209 2250703100025 17.0 2.454 0.267 2250703100026 ENDDATA 6 0 2250703100027 ENDSUBENT 26 0 2250703199999 ENDENTRY 31 0 2250799999999