ENTRY 22231 20200808 22902223100000001 SUBENT 22231001 20200808 22902223100100001 BIB 15 228 2223100100002 TITLE Reaction cross sections on carbon for neutron energies2223100100003 from 11.5 to 19 MeV 2223100100004 AUTHOR (B.Antolkovic,G.Dietze,H.Klein) 2223100100005 REFERENCE (J,NSE,107,1,1991) Subents 002-008 data 2223100100006 (J,RPD,44,31,1992) Subents 009- data 2223100100007 Secondary alpha particle spectra and partial kerma 2223100100008 factors of the reaction n + 12C -> n + 3 alpha 2223100100009 carbon deduced from microscopic cross sections at 2223100100010 incident neutron energies below 75 MeV . 2223100100011 INSTITUTE (2GERPTB) G.Dietze, H.Klein and experimental site 2223100100012 (3CRORBZ) B.Antolkovic 2223100100013 REL-REF (M,,B.Antolkovic+,J,NP/A,524,285,1991) 2223100100014 Processing and analysis of data 2223100100015 FACILITY (VDG,2GERPTB) The PTB Van De Graaff generator was used 2223100100016 for 13 to 19 MeV neutron energies. 2223100100017 (ISOCY,2GERPTB) The PTB isochronous cyclotron was used 2223100100018 for 11.5 to 13.5 MeV neutron energies. 2223100100019 MONITOR (1-H-1(N,EL)1-H-1,,SIG) Recoil proton measurement 2223100100020 INC-SOURCE (D-T) Monoenergetic neutrons of energy between 2223100100021 13 and 19 MeV were produced by bombarding a titanium- 2223100100022 tritium target with deuterons. Neutrons of 14.8, 17 2223100100023 and 19 MeV were produced at zero degree with respect 2223100100024 to the incident beam direction. And neutron with other2223100100025 energies were produced making use of the energy 2223100100026 distribution of the reaction. 2223100100027 . Targets of different thicknesses were used to obtain 2223100100028 optimum neutron yields. 2223100100029 . The incident deuteron energy could be specified 2223100100030 within +/- 2 keV. Using TOF techniques and Monte Carlo2223100100031 calculations it was deduced that a negligible amount 2223100100032 of neutrons were produced between 9.5 and 1 MeV below 2223100100033 the nominal energy. 2223100100034 . The neutron energy width was determined from the 2223100100035 energy loss of the deuterons within the gas and the 2223100100036 neutron energy distribution was assumed to be 2223100100037 rectangular. 2223100100038 . Ti-T target,2.40 mg/cm2 Ti on 1-mm-thick Ag, mean 2223100100039 deuteron energy 2.55 MeV 2223100100040 Emission angle Mean neutron energy Energy distr.width 2223100100041 deg MeV MeV 2223100100042 0.0 19.00 +- 0.030 0.380 2223100100043 27.65 18.50 +- 0.027 0.350 2223100100044 39.78 18.00 +- 0.024 0.310 2223100100045 49.61 17.50 +- 0.022 0.275 2223100100046 . Ti-T target, 2.29 mg/cm2 Ti on 1-mm-thick Ag, mean 2223100100047 deuteron energy 1.15 MeV 2223100100048 Emission angle Mean neutron energy Energy distr.width 2223100100049 deg MeV MeV 2223100100050 0.0 17.00 +- 0.050 0.700 2223100100051 35.55 16.50 +- 0.042 0.600 2223100100052 51.60 16.00 +- 0.034 0.500 2223100100053 65.00 15.50 +- 0.027 0.400 2223100100054 77.40 15.00 +- 0.023 0.300 2223100100055 82.24 14.80 +- 0.016 0.240 2223100100056 87.14 14.60 +- 0.014 0.200 2223100100057 92.07 14.40 +- 0.011 0.160 2223100100058 97.08 14.20 +- 0.009 0.120 2223100100059 102.25 14.00 +- 0.006 0.100 2223100100060 116.03 13.50 +- 0.006 0.050 2223100100061 132.44 13.00 +- 0.007 0.100 2223100100062 . Ti-T target, 2.29 mg/cm2 Ti on 1-mm-thick Ag,deuteron2223100100063 energy 0.2 MeV, neutron emission angle 0.0 deg, 2223100100064 mean neutron energy 14.80+-0.030 MeV, neutron energy 2223100100065 distribution width 0.460 MeV. 2223100100066 (D-D) Monoenergetic neutrons of energy between 2223100100067 11.5 and 13.5 MeV were produced with the D-D reaction,2223100100068 using a deuterium gas target and the pulsed deuteron 2223100100069 beam of the energy variable cyclotron. The mean 2223100100070 deuteron energy within the gas was implicitly deter- 2223100100071 mined by neutron time of flight measurements using an 2223100100072 NE213 detector. An uncertainty of 30 keV was achieved.2223100100073 The neutron energy width was determined from the 2223100100074 energy loss of the deuterons within the gas and the 2223100100075 neutron energy distribution was again assumed to be 2223100100076 rectangular. 2223100100077 The D-N and the deuteron breakup reactions on 2223100100078 molybdenum entrance foil and the gold beam stop 2223100100079 yielded (15%) neutrons with energies distributed 2223100100080 equally over a 6 MeV region below the nominal energy. 2223100100081 . D2 gas target, 3 cm long, 10 kPa D2, mean deuteron 2223100100082 energy form 8.4 MeV to 10.53 MeV , emission angle 0.deg2223100100083 Mean neutron energy,MeV Energy distribution width,MeV 2223100100084 13.535 +- 0.030 0.080 2223100100085 12.895 +- 0.030 0.085 2223100100086 12.555 +- 0.030 0.090 2223100100087 11.915 +- 0.030 0.095 2223100100088 11.505 +- 0.030 0.100 2223100100089 INC-SPECT .The neutron fluence applied in the irradiation of the 2223100100090 emulsions was determined using a proton recoil 2223100100091 telescope in a geometry similar to that used during 2223100100092 exposure of the emulsions. The signals from 2 prop. 2223100100093 counters and a surface barrier detector were analyzed 2223100100094 in coincidence to distinguish the recoil proton events2223100100095 from the neutron interaction in a 10.085mg/cm2 thick 2223100100096 tristearine radiator. 2223100100097 The detection efficiency was calculated taking into 2223100100098 account the actual irradiation geometry and the 2223100100099 evaluated N-P scattering cross section. Two moderating2223100100100 neutron detectors were used to monitor the fluence 2223100100101 during irradiation of the emulsions. 2223100100102 For the cyclotron measurements, the fluence was 2223100100103 determined using the NE213 liquid scintillator. 2223100100104 The well known hydrogen content of the scintillator 2223100100105 was used to normalize to the N-P scattering cross 2223100100106 section. The total uncertainty was about 3 %, was 2223100100107 estimated from the fitting procedure, the basic cross 2223100100108 sections and the hydrogen content. 2223100100109 SAMPLE .ILFORD C2 nuclear emulsions were used as samples and 2223100100110 detectors to study the C-12(N,N+3ALPHA).The emulsions 2223100100111 with a carbon content of 0.277g/cm3 and a thickness 2223100100112 of 200 micro-meter were exposed at an angle of 13.8 2223100100113 adeg to monoenergetic neutrons of energies 11.9, 12.9,2223100100114 14.0, 17.0 and 19.0 MeV. 2223100100115 .The scintillator which has a well known carbon content2223100100116 is used as a carbon target as well as an alpha 2223100100117 detector. 2223100100118 METHOD (ASSOP) The nuclear emulsion technique was used to 2223100100119 investigate C-12(N,N+3ALPHA) reaction for neutron 2223100100120 energies of 11.9 to 19.0 MeV. The total and various 2223100100121 partial cross sections from the N-3ALPHA breakup 2223100100122 were determined. 2223100100123 (TOF) The total cross sections of all reactions with 2223100100124 charged particles (except carbon recoil protons) in 2223100100125 the exit channel were determined W.R.T the N-P 2223100100126 scattering cross section using an NE213 scintillator 2223100100127 with TOF technique. 2223100100128 (PHD) The pulse shape discrimination technique was 2223100100129 used with the NE213 detector. 2223100100130 DETECTOR (PLATE) The nuclear emulsions which contain carbon 2223100100131 as a main constituent are used both as a carbon target2223100100132 and as a alpha-particle detector. The simultaneous 2223100100133 detection of all charged particles of such an event 2223100100134 yields a kinematically complete measurement. The 2223100100135 emulsions were developed by a 2-temperature technique2223100100136 after which they were scanned for 3-pronged events 2223100100137 using a Leitz Ortholux binocular microscope.The 2223100100138 reaction kinematics was determined by measuring the 2223100100139 spatial orientations and ranges of each of the 3 2223100100140 prongs of a star . 2223100100141 (SCIN) The NE213 scintillation detector also served 2223100100142 both as the carbon target and the alpha particle 2223100100143 detector. It was used in assessing reactions with 2223100100144 very low statistical uncertainties. The response 2223100100145 of this detector, 2.54 cm in height by 10.16 cm in 2223100100146 diameter, was measured for monoenergetic neutrons 2223100100147 applying 'TOF' techniques and compared with Monte- 2223100100148 Carlo simulations. Elastic and inelastic cross 2223100100149 sections were taken from ENDF/B-V. 2223100100150 COMMENT Of compiler M.M. Alpha energy diff. CS presented on 2223100100151 Fig. 1 of J.Radiation Protection Dosimetry,44,31,1992 2223100100152 have insufficient quality for digitization - 2223100100153 overlapping, triangles and full points could not be 2223100100154 separated. 2223100100155 ADD-RES Distribution of alpha particle spectrum, normalized 2223100100156 to 1. ( Fig.2 left, right) 2223100100157 En=17.0 MeV 2223100100158 Eaplha, MeV Value, no-dim. 2223100100159 0.079 0.0028 2223100100160 0.369 0.0325 2223100100161 0.607 0.0684 2223100100162 0.862 0.1086 2223100100163 1.134 0.1467 2223100100164 1.390 0.1785 2223100100165 1.629 0.1955 2223100100166 1.868 0.2104 2223100100167 2.124 0.2316 2223100100168 2.414 0.2423 2223100100169 2.637 0.2467 2223100100170 2.860 0.2216 2223100100171 3.135 0.2112 2223100100172 3.374 0.2282 2223100100173 3.633 0.1779 2223100100174 3.890 0.1760 2223100100175 4.129 0.1803 2223100100176 4.369 0.1700 2223100100177 4.626 0.1638 2223100100178 4.884 0.1430 2223100100179 5.108 0.1221 2223100100180 5.348 0.1096 2223100100181 5.604 0.1182 2223100100182 5.863 0.0805 2223100100183 6.103 0.0680 2223100100184 6.360 0.0577 2223100100185 6.600 0.0684 2223100100186 6.858 0.0349 2223100100187 7.115 0.0308 2223100100188 7.355 0.0184 2223100100189 7.612 0.0270 2223100100190 7.886 0.0250 2223100100191 8.075 0.0104 2223100100192 8.366 0.0085 2223100100193 8.606 0.0066 2223100100194 8.845 0.0047 2223100100195 En=12.9 MeV 2223100100196 Eaplha, MeV Value, no-dim. 2223100100197 0.086 0.0343 2223100100198 0.378 0.1291 2223100100199 0.635 0.2095 2223100100200 0.893 0.3600 2223100100201 1.133 0.3930 +- 0.0206 2223100100202 1.390 0.4527 +- 0.0226 2223100100203 1.630 0.3743 +- 0.0288 2223100100204 1.869 0.3022 +- 0.0288 2223100100205 2.108 0.2774 +- 0.0288 2223100100206 2.382 0.2526 +- 0.0288 2223100100207 2.604 0.2217 +- 0.0288 2223100100208 2.861 0.1515 +- 0.0391 2223100100209 3.101 0.1866 +- 0.0432 2223100100210 3.340 0.1412 +- 0.0556 2223100100211 3.614 0.2009 +- 0.0762 2223100100212 3.854 0.1226 +- 0.0680 2223100100213 4.128 0.1267 +- 0.1010 2223100100214 4.367 0.0730 +- 0.0701 2223100100215 4.589 0.0524 +- 0.0494 2223100100216 4.863 0.0256 +- 0.0268 2223100100217 HISTORY (19930707C) N.O. 2223100100218 (19961225A) * * Corrected by S. Maev 2223100100219 MONITOR added; FACILITY, DETECTOR, SAMPLE, ERR-ANALYS 2223100100220 corrected. DATA-ERR -> ERR-T. Subents 002 and 003; 2223100100221 006 and 007 were merged. 2223100100222 (20181111A) M.M. Upper -> lower case correction. 2223100100223 Dates were corrected for 4-digits year. 2223100100224 ERR-ANALYS was corrected according to now-days rules. 2223100100225 Code SPSDD was added in Subent 006 . 2223100100226 INC-SOURCE, ANALYSIS information was added 2223100100227 Second ref. was added . Subents 009-011 were added. 2223100100228 EN-ERR and EN-RSL were added in data Subents. 2223100100229 (20200808A) SD: Corrections in Subents 006,009,010. 2223100100230 ENDBIB 228 0 2223100100231 NOCOMMON 0 0 2223100100232 ENDSUBENT 231 0 2223100199999 SUBENT 22231002 20181111 22722223100200001 BIB 8 48 2223100200002 REACTION (6-C-12(N,N+2A)2-HE-4,ISP,SIG) 2223100200003 C12(n,n')C12*(3alpha) 2223100200004 ANALYSIS Data for explosure of emulsions and data analysis: 2223100200005 En,MeV F,1/cm2 N L,cm Nb/N,% C1*C2 C3 2223100200006 11.9 1.44E+8 1400 45.0 8.1 1.21 1.88 2223100200007 12.9 1.48E+8 859 45.0 9.1 1.19 1.58 2223100200008 14.0 1.36E+8 1516 35.0 8.5 1.18 1.47 2223100200009 14.8 1.51E+8 982 35.0 8.4 1.18 1.31 2223100200010 17.0 2.00E+8 925 35.0 6.9 1.17 1.25 2223100200011 19.0 2.95E+8 913 30.0 7.9 1.17 1.21 2223100200012 F - neutron fluence, 2223100200013 N - number of vents, 2223100200014 L - distance between neutron source and sample, 2223100200015 Nb - background events, 2223100200016 C1,C2,C3 - correction factors for loss of events 2223100200017 - alpha particles leaving emulsion before stopping, 2223100200018 - alpha track perpendicular to emulsion surface, 2223100200019 - low-energy alpha particle ( cutoff ~ 0.45 MeV) 2223100200020 CORRECTION .In the emulsion measurements, corrections were made 2223100200021 for dead time losses,flux attenuation in air, 2223100200022 construction materials and radiator backing and for 2223100200023 a small background peak under the proton recoil peak. 2223100200024 COMMENT . The data is the partial C-12(N,N3A) 2223100200025 reaction cross section deduced by subtracting 2223100200026 C-12(N,A)BE-9(N2A) reaction via the 2.4 MeV 2223100200027 level of Be-9 from the total C-12(N,N3A) cross 2223100200028 section. 2223100200029 EN-SEC (E-EXC,6-C-12) Min/max excitation energy of C-12 2223100200030 are given in DATA block 2223100200031 ERR-ANALYS (ERR-T) Total error in the nuclear emulsion 2223100200032 measurements. Its constituents given below 2223100200033 (ERR-S,,3.) Max statistical error (3%) 2223100200034 (ERR-1) Background subtraction error (3 %) 2223100200035 (ERR-2) Neutron fluence determination error (3 %) 2223100200036 (ERR-3) Carbon content determination error (2 %) 2223100200037 (ERR-4,3.,9.6) Corrections error 2223100200038 Sum of other correction uncertainties 2223100200039 at 12 MeV neutron energy (9.6 %) 2223100200040 Sum of correction factor uncertainties 2223100200041 at 19. MeV neutron energy (3 % ) 2223100200042 STATUS (TABLE) From Table III of J.Nucl.Sci.Eng.,107,1,1991 2223100200043 HISTORY (19930701C) N.O. 2223100200044 (19931129E) 2223100200045 (19961225A) Data section rearranged and similar data 2223100200046 from other Subentries moved in this one 2223100200047 (20181111A) E-EXC-MIN=8MeV added at first point 2223100200048 instead of blank according to a comment of N.Otsuka 2223100200049 (NDS,IAEA) 2223100200050 ENDBIB 48 0 2223100200051 COMMON 3 3 2223100200052 ERR-1 ERR-2 ERR-3 2223100200053 PER-CENT PER-CENT PER-CENT 2223100200054 3.0 3.0 2.0 2223100200055 ENDCOMMON 3 0 2223100200056 DATA 8 32 2223100200057 EN EN-ERR EN-RSL E-EXC-MIN E-EXC-MAX E-EXC-MEAN 2223100200058 DATA ERR-T 2223100200059 MEV MEV MEV MEV MEV MEV 2223100200060 MB MB 2223100200061 11.9 0.030 0.095 8. 10.25 9.6 2223100200062 110.8 17.0 2223100200063 11.9 0.030 0.095 10.25 11.25 10.8 2223100200064 16.4 8.6 2223100200065 11.9 0.030 0.095 11.25 12.25 11.8 2223100200066 1.6 0.5 2223100200067 12.9 0.030 0.085 8. 10.25 9.6 2223100200068 71.7 8.5 2223100200069 12.9 0.030 0.085 10.25 11.25 10.8 2223100200070 49.8 12.4 2223100200071 12.9 0.030 0.085 11.25 12.25 11.8 2223100200072 7.4 7.0 2223100200073 12.9 0.030 0.085 12.25 13.50 12.8 2223100200074 1.2 1.0 2223100200075 14.0 0.006 0.100 8. 10.25 9.6 2223100200076 76.5 8.0 2223100200077 14.0 0.006 0.100 10.25 11.25 10.8 2223100200078 47.0 3.6 2223100200079 14.0 0.006 0.100 11.25 12.25 11.8 2223100200080 37.6 12.2 2223100200081 14.0 0.006 0.100 12.25 13.50 12.8 2223100200082 8.4 5.9 2223100200083 14.8 0.030 0.460 8. 10.25 9.6 2223100200084 69.0 8.4 2223100200085 14.8 0.030 0.460 10.25 11.25 10.8 2223100200086 36.1 4.0 2223100200087 14.8 0.030 0.460 11.25 12.25 11.8 2223100200088 50.2 4.9 2223100200089 14.8 0.030 0.460 12.25 13.50 12.8 2223100200090 48.7 12.1 2223100200091 14.8 0.030 0.460 13.50 14.50 14.0 2223100200092 5.6 0.7 2223100200093 17.0 0.050 0.700 8. 10.25 9.6 2223100200094 44.5 4.9 2223100200095 17.0 0.050 0.700 10.25 11.25 10.8 2223100200096 25.0 2.5 2223100200097 17.0 0.050 0.700 11.25 12.25 11.8 2223100200098 35.7 2.8 2223100200099 17.0 0.050 0.700 12.25 13.50 12.8 2223100200100 71.1 4.1 2223100200101 17.0 0.050 0.700 13.50 14.50 14.0 2223100200102 42.9 5.9 2223100200103 17.0 0.050 0.700 14.50 15.50 15.0 2223100200104 29.4 5.4 2223100200105 17.0 0.050 0.700 15.50 16.50 16.0 2223100200106 9.4 2.8 2223100200107 19.0 0.030 0.380 8. 10.25 9.6 2223100200108 45.9 5.3 2223100200109 19.0 0.030 0.380 10.25 11.25 10.8 2223100200110 21.3 2.8 2223100200111 19.0 0.030 0.380 11.25 12.25 11.8 2223100200112 33.3 3.2 2223100200113 19.0 0.030 0.380 12.25 13.50 12.8 2223100200114 39.4 3.4 2223100200115 19.0 0.030 0.380 13.50 14.50 14.0 2223100200116 39.9 3.5 2223100200117 19.0 0.030 0.380 14.50 15.50 15.0 2223100200118 44.1 3.4 2223100200119 19.0 0.030 0.380 15.50 16.50 16.0 2223100200120 41.3 6.1 2223100200121 19.0 0.030 0.380 16.50 17.50 17.0 2223100200122 18.4 4.8 2223100200123 19.0 0.030 0.380 17.50 18.50 18.0 2223100200124 7.4 2.6 2223100200125 ENDDATA 68 0 2223100200126 ENDSUBENT 125 0 2223100299999 NOSUBENT 22231003 20181111 22722223100300001 SUBENT 22231004 20181111 22722223100400001 BIB 7 43 2223100400002 REACTION (6-C-12(N,A)4-BE-9,PAR,SIG) 2223100400003 ANALYSIS Data for explosure of emulsions and data analysis: 2223100400004 En,MeV F,1/cm2 N L,cm Nb/N,% C1*C2 C3 2223100400005 11.9 1.44E+8 1400 45.0 8.1 1.21 1.88 2223100400006 12.9 1.48E+8 859 45.0 9.1 1.19 1.58 2223100400007 14.0 1.36E+8 1516 35.0 8.5 1.18 1.47 2223100400008 14.8 1.51E+8 982 35.0 8.4 1.18 1.31 2223100400009 17.0 2.00E+8 925 35.0 6.9 1.17 1.25 2223100400010 19.0 2.95E+8 913 30.0 7.9 1.17 1.21 2223100400011 F - neutron fluence, 2223100400012 N - number of vents, 2223100400013 L - distance between neutron source and sample, 2223100400014 Nb - background events, 2223100400015 C1,C2,C3 - correction factors for loss of events 2223100400016 - alpha particles leaving emulsion before stopping, 2223100400017 - alpha track perpendicular to emulsion surface, 2223100400018 - low-energy alpha particle ( cutoff ~ 0.45 MeV) 2223100400019 CORRECTION .In the emulsion measurements, corrections were made 2223100400020 for dead time losses,flux attenuation in air, 2223100400021 construction materials and radiator backing and for 2223100400022 a small background peak under the proton recoil peak. 2223100400023 COMMENT .The data is the contribution of the partial 2223100400024 C-12(N,A)BE-9(N+2A) reaction via the 2.4 MeV level of 2223100400025 Be-9 to the total C-12(N,N+3A) cross section. It has 2223100400026 been extracted considering kinematical conditions. 2223100400027 ERR-ANALYS (ERR-T) Total error in the nuclear emulsion 2223100400028 measurements. Its constituents given below 2223100400029 (ERR-S,,3.) Max statistical error (3%) 2223100400030 (ERR-1) Background subtraction error (3 %) 2223100400031 (ERR-2) Neutron fluence determination error (3 %) 2223100400032 (ERR-3) Carbon content determination error (2 %) 2223100400033 (ERR-4,3.,9.6) Corrections error 2223100400034 Sum of other correction uncertainties 2223100400035 at 12 MeV neutron energy (9.6 %) 2223100400036 Sum of correction factor uncertainties 2223100400037 at 19. MeV neutron energy (3 % ) 2223100400038 STATUS (TABLE) From Table III of J.Nucl.Sci.Eng.,107,1,1991 2223100400039 HISTORY (19930707C) N.O. 2223100400040 (19931129E) 2223100400041 (19961225U) Excitation energy is introduced 2223100400042 (20181111A) Reaction was corrected : 2223100400043 6-C-12(N,N+2A)2-HE-4,PAR,SIG -> 2223100400044 6-C-12(N,A)4-BE-9,PAR,SIG ; E-EXC -> E-LVL 2223100400045 ENDBIB 43 0 2223100400046 COMMON 4 3 2223100400047 E-LVL ERR-1 ERR-2 ERR-3 2223100400048 MEV PER-CENT PER-CENT PER-CENT 2223100400049 2.43 3.0 3.0 2.0 2223100400050 ENDCOMMON 3 0 2223100400051 DATA 5 6 2223100400052 EN EN-ERR EN-RSL DATA ERR-T 2223100400053 MEV MEV MEV MB MB 2223100400054 11.9 0.030 0.095 48.0 12.0 2223100400055 12.9 0.030 0.085 37.0 17.0 2223100400056 14.0 0.006 0.100 32.0 20.0 2223100400057 14.8 0.016 0.240 18.0 14.0 2223100400058 17.0 0.050 0.700 14.0 8.0 2223100400059 19.0 0.030 0.380 9.0 9.0 2223100400060 ENDDATA 8 0 2223100400061 ENDSUBENT 60 0 2223100499999 SUBENT 22231005 20181111 22722223100500001 BIB 7 46 2223100500002 REACTION (6-C-12(N,N+2A)2-HE-4,,SIG,,MSC) 2223100500003 12C(n,n+3a) cross section excluding 12C(n,n2)12C 2223100500004 contribution 2223100500005 ANALYSIS Data for explosure of emulsions and data analysis: 2223100500006 En,MeV F,1/cm2 N L,cm Nb/N,% C1*C2 C3 2223100500007 11.9 1.44E+8 1400 45.0 8.1 1.21 1.88 2223100500008 12.9 1.48E+8 859 45.0 9.1 1.19 1.58 2223100500009 14.0 1.36E+8 1516 35.0 8.5 1.18 1.47 2223100500010 14.8 1.51E+8 982 35.0 8.4 1.18 1.31 2223100500011 17.0 2.00E+8 925 35.0 6.9 1.17 1.25 2223100500012 19.0 2.95E+8 913 30.0 7.9 1.17 1.21 2223100500013 F - neutron fluence, 2223100500014 N - number of vents, 2223100500015 L - distance between neutron source and sample, 2223100500016 Nb - background events, 2223100500017 C1,C2,C3 - correction factors for loss of events 2223100500018 - alpha particles leaving emulsion before stopping, 2223100500019 - alpha track perpendicular to emulsion surface, 2223100500020 - low-energy alpha particle ( cutoff ~ 0.45 MeV) 2223100500021 CORRECTION .In the emulsion measurements, corrections were made 2223100500022 for dead time losses,flux attenuation in air, 2223100500023 construction materials and radiator backing and for 2223100500024 a small background peak under the proton recoil peak. 2223100500025 COMMENT .Data is the total C-12(N,N3A) reaction cross sections 2223100500026 including C-12(N,A)BE-9(N+2A) reaction via the 2.4 MeV2223100500027 level of Be-9 and all inelastic channels except the 2223100500028 inel. scat. via the 7.6 MeV level of carbon. 2223100500029 ERR-ANALYS (ERR-T) Total error in the nuclear emulsion 2223100500030 measurements. Its constituents given below 2223100500031 (ERR-S,,3.) Max statistical error (3%) 2223100500032 (ERR-1) Background subtraction error (3 %) 2223100500033 (ERR-2) Neutron fluence determination error (3 %) 2223100500034 (ERR-3) Carbon content determination error (2 %) 2223100500035 (ERR-4,3.,9.6) Corrections error 2223100500036 Sum of other correction uncertainties 2223100500037 at 12 MeV neutron energy (9.6 %) 2223100500038 Sum of correction factor uncertainties 2223100500039 at 19. MeV neutron energy (3 % ) 2223100500040 STATUS (TABLE) From Table III of J.Nucl.Sci.Eng.,107,1,1991 2223100500041 (DEP,22231002) 2223100500042 (DEP,22231004) 2223100500043 HISTORY (19930707C) N.O. 2223100500044 (19931129E) 2223100500045 (19961225U) Cross-reference is given 2223100500046 (20181111A) MSC code was added according to a comment 2223100500047 of N.Otsuka (NDS,IAEA) 2223100500048 ENDBIB 46 0 2223100500049 COMMON 3 3 2223100500050 ERR-1 ERR-2 ERR-3 2223100500051 PER-CENT PER-CENT PER-CENT 2223100500052 3.0 3.0 2.0 2223100500053 ENDCOMMON 3 0 2223100500054 DATA 5 6 2223100500055 EN EN-ERR EN-RSL DATA ERR-T 2223100500056 MEV MEV MEV MB MB 2223100500057 11.9 0.030 0.095 176.8 18.2 2223100500058 12.9 0.030 0.085 167.1 14.0 2223100500059 14.0 0.006 0.100 210.5 14.6 2223100500060 14.8 0.016 0.240 227.6 14.8 2223100500061 17.0 0.050 0.700 272.0 16.9 2223100500062 19.0 0.030 0.380 300.0 17.9 2223100500063 ENDDATA 8 0 2223100500064 ENDSUBENT 63 0 2223100599999 SUBENT 22231006 20200808 22902223100600001 BIB 8 58 2223100600002 REACTION (6-C-12(N,N+A)4-BE-8,ISP/PAR,SIG,,MSC) 2223100600003 cross section for all (n,n3a) reactions via 8Be(g.s.) 2223100600004 and characterized by the three-alpha energy 2223100600005 ANALYSIS Data for exposure of emulsions and data analysis: 2223100600006 En,MeV F,1/cm2 N L,cm Nb/N,% C1*C2 C3 2223100600007 11.9 1.44E+8 1400 45.0 8.1 1.21 1.88 2223100600008 12.9 1.48E+8 859 45.0 9.1 1.19 1.58 2223100600009 14.0 1.36E+8 1516 35.0 8.5 1.18 1.47 2223100600010 14.8 1.51E+8 982 35.0 8.4 1.18 1.31 2223100600011 17.0 2.00E+8 925 35.0 6.9 1.17 1.25 2223100600012 19.0 2.95E+8 913 30.0 7.9 1.17 1.21 2223100600013 F - neutron fluence, 2223100600014 N - number of vents, 2223100600015 L - distance between neutron source and sample, 2223100600016 Nb - background events, 2223100600017 C1,C2,C3 - correction factors for loss of events 2223100600018 - alpha particles leaving emulsion before stopping, 2223100600019 - alpha track perpendicular to emulsion surface, 2223100600020 - low-energy alpha particle ( cutoff ~ 0.45 MeV) 2223100600021 CORRECTION .In the emulsion measurements, corrections were made 2223100600022 for dead time losses,flux attenuation in air, 2223100600023 construction materials and radiator backing and for 2223100600024 a small background peak under the proton recoil peak. 2223100600025 COMMENT .The partial cross sections for the transition via 2223100600026 the 8-Be ground state in the C-12(N,N3A) breakup 2223100600027 reaction was extracted from experimental data and 2223100600028 given in table IV as below. 12-C(N,A)9-BE contribution2223100600029 is included 2223100600030 EN-SEC (E-EXC,6-C-12) (Min., max, mean) excitation energy of 2223100600031 intermediate nucleus. 12-C excitation energy bins 2223100600032 overlap with reaction 12-C(N,A)9-BE 2223100600033 (E-LVL,4-BE-8) 2223100600034 ERR-ANALYS (ERR-T) Total error in the nuclear emulsion 2223100600035 measurements. Its constituents given below 2223100600036 (ERR-S,,3.) Max statistical error (3%) 2223100600037 (ERR-1) Background subtraction error (3 %) 2223100600038 (ERR-2) Neutron fluence determination error (3 %) 2223100600039 (ERR-3) Carbon content determination error (2 %) 2223100600040 (ERR-4,3.,9.6) Corrections error 2223100600041 Sum of other correction uncertainties 2223100600042 at 12 MeV neutron energy (9.6 %) 2223100600043 Sum of correction factor uncertainties 2223100600044 at 19. MeV neutron energy (3 % ) 2223100600045 STATUS (TABLE) From Table IV of J.Nucl.Sci.Eng.,107,1,1991 2223100600046 (SPSDD,22231009) This Subent is superseded by data of 2223100600047 newer publication in Subent 22231009 2223100600048 HISTORY (19930707C) N.O. 2223100600049 (19931129E) 2223100600050 (19961225A) .Excitation energy is introduced and 2223100600051 sigma contributions specified 2223100600052 .Data moved from SUBENT 007 in this one 2223100600053 (20181111A) M.M. Code SPSDD was added. 2223100600054 Reaction was corrected : 2223100600055 (N,N+2A)2-HE-4,PAR,SIG -> (N,N+A)4-BE-8,ISP/PAR,SIG ; 2223100600056 E-EXC-MIN=8.MeV was added at first poin instead of 2223100600057 blank. 2223100600058 (20200808A) SD: SF8=MSC added to REACTION code with 2223100600059 explanation. 2223100600060 ENDBIB 58 0 2223100600061 COMMON 4 3 2223100600062 E-LVL ERR-1 ERR-2 ERR-3 2223100600063 MEV PER-CENT PER-CENT PER-CENT 2223100600064 0. 3.0 3.0 2.0 2223100600065 ENDCOMMON 3 0 2223100600066 DATA 8 32 2223100600067 EN EN-ERR EN-RSL E-EXC-MIN E-EXC-MAX E-EXC-MEAN 2223100600068 DATA ERR-T 2223100600069 MEV MEV MEV MEV MEV MEV 2223100600070 MB MB 2223100600071 11.9 0.030 0.095 8. 10.25 9.6 2223100600072 113.0 12.8 2223100600073 11.9 0.030 0.095 10.25 11.25 10.8 2223100600074 21.0 3.0 2223100600075 11.9 0.030 0.095 11.25 12.25 11.8 2223100600076 1.5 0.7 2223100600077 12.9 0.030 0.085 8. 10.25 9.6 2223100600078 67.3 8.3 2223100600079 12.9 0.030 0.085 10.25 11.25 10.8 2223100600080 51.6 4.7 2223100600081 12.9 0.030 0.085 11.25 12.25 11.8 2223100600082 10.3 1.7 2223100600083 12.9 0.030 0.085 12.25 13.50 12.8 2223100600084 0.7 0.5 2223100600085 14.0 0.006 0.100 8. 10.25 9.6 2223100600086 67.3 7.2 2223100600087 14.0 0.006 0.100 10.25 11.25 10.8 2223100600088 30.8 2.6 2223100600089 14.0 0.006 0.100 11.25 12.25 11.8 2223100600090 20.6 1.8 2223100600091 14.0 0.006 0.100 12.25 13.50 12.8 2223100600092 6.3 0.9 2223100600093 14.8 0.030 0.460 8. 10.25 9.6 2223100600094 64.3 8.1 2223100600095 14.8 0.030 0.460 10.25 11.25 10.8 2223100600096 22.5 2.9 2223100600097 14.8 0.030 0.460 11.25 12.25 11.8 2223100600098 20.6 2.6 2223100600099 14.8 0.030 0.460 12.25 13.50 12.8 2223100600100 16.7 2.0 2223100600101 14.8 0.030 0.460 13.50 14.50 14.0 2223100600102 1.1 0.3 2223100600103 17.0 0.050 0.700 8. 10.25 9.6 2223100600104 36.6 4.2 2223100600105 17.0 0.050 0.700 10.25 11.25 10.8 2223100600106 14.7 1.8 2223100600107 17.0 0.050 0.700 11.25 12.25 11.8 2223100600108 11.9 1.5 2223100600109 17.0 0.050 0.700 12.25 13.50 12.8 2223100600110 17.6 1.9 2223100600111 17.0 0.050 0.700 13.50 14.50 14.0 2223100600112 10.7 1.4 2223100600113 17.0 0.050 0.700 14.50 15.50 15.0 2223100600114 6.8 1.1 2223100600115 17.0 0.050 0.700 15.50 16.50 16.0 2223100600116 1.4 0.8 2223100600117 19.0 0.030 0.380 8. 10.25 9.6 2223100600118 42.3 5.0 2223100600119 19.0 0.030 0.380 10.25 11.25 10.8 2223100600120 10.7 1.9 2223100600121 19.0 0.030 0.380 11.25 12.25 11.8 2223100600122 6.0 1.3 2223100600123 19.0 0.030 0.380 12.25 13.50 12.8 2223100600124 6.0 1.1 2223100600125 19.0 0.030 0.380 13.50 14.50 14.0 2223100600126 7.3 1.4 2223100600127 19.0 0.030 0.380 14.50 15.50 15.0 2223100600128 3.6 0.9 2223100600129 19.0 0.030 0.380 15.50 16.50 16.0 2223100600130 5.1 1.1 2223100600131 19.0 0.030 0.380 16.50 17.50 17.0 2223100600132 2.5 0.8 2223100600133 19.0 0.030 0.380 17.50 18.50 18.0 2223100600134 0.5 0.4 2223100600135 ENDDATA 68 0 2223100600136 ENDSUBENT 135 0 2223100699999 NOSUBENT 22231007 20181111 22722223100700001 SUBENT 22231008 20181111 22722223100800001 BIB 9 64 2223100800002 REACTION (6-C-12(N,N+2A)2-HE-4,,SIG,,MSC) 2223100800003 Three-alpha break up cross section (excluding 2223100800004 12C(n,n'2)12C(7.65MeV)(3alpha) contribution) plus 2223100800005 12C(n,alpha0)9Be cross section. 2223100800006 PART-DET (A) 2223100800007 ANALYSIS Data for explosure of emulsions and data analysis: 2223100800008 En,MeV F,1/cm2 N L,cm Nb/N,% C1*C2 C3 2223100800009 11.9 1.44E+8 1400 45.0 8.1 1.21 1.88 2223100800010 12.9 1.48E+8 859 45.0 9.1 1.19 1.58 2223100800011 14.0 1.36E+8 1516 35.0 8.5 1.18 1.47 2223100800012 14.8 1.51E+8 982 35.0 8.4 1.18 1.31 2223100800013 17.0 2.00E+8 925 35.0 6.9 1.17 1.25 2223100800014 19.0 2.95E+8 913 30.0 7.9 1.17 1.21 2223100800015 F - neutron fluence, 2223100800016 N - number of vents, 2223100800017 L - distance between neutron source and sample, 2223100800018 Nb - background events, 2223100800019 C1,C2,C3 - correction factors for loss of events 2223100800020 - alpha particles leaving emulsion before stopping, 2223100800021 - alpha track perpendicular to emulsion surface, 2223100800022 - low-energy alpha particle ( cutoff ~ 0.45 MeV) 2223100800023 CORRECTION .In the emulsion measurements, corrections were made 2223100800024 for dead time losses,flux attenuation in air, 2223100800025 construction materials and radiator backing and for 2223100800026 a small background peak under the proton recoil peak. 2223100800027 COMMENT .Data is the sum of the neutron cross sections 2223100800028 C-12(N,N3A) including all channels except that for the2223100800029 sequential decay via the 7.65 MeV level of carbon for 2223100800030 which the 3alpha particle events can not be separated 2223100800031 from the carbon recoils. These n-induced reaction 2223100800032 cross-sections were deduced from the integral 2223100800033 of the difference spectra. 2223100800034 REL-REF (A,22075184,A.Takahashi+,J,NST,25,215,1988) 2223100800035 Ref. NST,25,215,1988 is REL-REF in 22075 . 2223100800036 (A,,N.Olsson+,J,PMB,34,909,1989) 2223100800037 (D,12899003,R.C.Haight+,J,NSE,87,41,1984) 2223100800038 (A,22077001,M.Baba+,C,88MITO,,209,1988) 2223100800039 (A,,L.F.Hansen,R,UCRL-95890,1986) Recommended data. 2223100800040 (A,,R.Boettger+,C,85SANTA,2,1455,1985) 2223100800041 (A,,W.Tornow,W,TORNOW,1988) 2223100800042 (D,12890001,D.W.Glasgow+,J,NSE,61,521,1976) 2223100800043 + priv.com.,1982 2223100800044 ( no (n,n+3a) data in NSE, probably from private 2223100800045 communication) 2223100800046 ERR-ANALYS (ERR-T) Total error in the nuclear emulsion 2223100800047 measurements. Its constituents given below 2223100800048 (ERR-S,,3.) Max statistical error (3%) 2223100800049 (ERR-1) Background subtraction error (3 %) 2223100800050 (ERR-2) Neutron fluence determination error (3 %) 2223100800051 (ERR-3) Carbon content determination error (2 %) 2223100800052 (ERR-4,3.,9.6) Corrections error 2223100800053 Sum of other correction uncertainties 2223100800054 at 12 MeV neutron energy (9.6 %) 2223100800055 Sum of correction factor uncertainties 2223100800056 at 19. MeV neutron energy (3 % ) 2223100800057 STATUS (TABLE) From Table V of J.Nucl.Sci.Eng.,107,1,1991 2223100800058 (DEP,22231005) 2223100800059 (DEP,22231006) 2223100800060 HISTORY (19930701C) N.O. 2223100800061 (19931129E) 2223100800062 (19961225U) Cross-reference to independent data is 2223100800063 given 2223100800064 (20181111A) M.M. REL-REFs were added. 2223100800065 Reactions was corrected : MSC code was added in SF8 2223100800066 ENDBIB 64 0 2223100800067 COMMON 3 3 2223100800068 ERR-1 ERR-2 ERR-3 2223100800069 PER-CENT PER-CENT PER-CENT 2223100800070 3.0 3.0 2.0 2223100800071 ENDCOMMON 3 0 2223100800072 DATA 5 21 2223100800073 EN EN-ERR EN-RSL DATA ERR-T 2223100800074 MEV MEV MEV MB MB 2223100800075 11.51 0.030 0.100 223.9 8.5 2223100800076 11.92 0.030 0.095 283.2 9.1 2223100800077 12.56 0.030 0.090 238.8 9.8 2223100800078 12.90 0.030 0.085 289.6 10.4 2223100800079 13.0 0.007 0.100 287.6 9.5 2223100800080 13.5 0.006 0.050 283.3 8.4 2223100800081 13.53 0.030 0.080 281.9 9.3 2223100800082 14.0 0.006 0.100 272.6 8.9 2223100800083 14.2 0.009 0.120 272.0 9.3 2223100800084 14.4 0.011 0.160 303.9 9.9 2223100800085 14.6 0.014 0.200 320.8 11.3 2223100800086 14.8 0.016 0.240 311.3 11.1 2223100800087 15.0 0.023 0.300 311.3 10.1 2223100800088 15.5 0.027 0.400 327.1 12.1 2223100800089 16.0 0.034 0.500 355.4 12.9 2223100800090 16.5 0.042 0.600 405.1 15.7 2223100800091 17.0 0.050 0.700 392.9 16.7 2223100800092 17.5 0.022 0.275 435.5 19.8 2223100800093 18.0 0.024 0.310 394.1 23.0 2223100800094 18.5 0.027 0.350 411.6 20.2 2223100800095 19.0 0.030 0.380 379.6 19.9 2223100800096 ENDDATA 23 0 2223100800097 ENDSUBENT 96 0 2223100899999 SUBENT 22231009 20200808 22902223100900001 BIB 7 18 2223100900002 REACTION (6-C-12(N,N+A)4-BE-8,ISP/PAR,SIG,,MSC) 2223100900003 cross section for all (n,n3a) reactions via 8Be(g.s.) 2223100900004 and characterized by the three-alpha energy 2223100900005 EN-SEC (E-EXC,6-C-12) Min., max. and mean energies in DATA 2223100900006 block are given. 2223100900007 (E-LVL,4-BE-8) 2223100900008 ANALYSIS Data of 22231.006 were re-analyzed 2223100900009 CORRECTION Low energy cut-off, Tables 1, 2 of J.Radiation 2223100900010 Protection Dosimetry,44,31,1992 data were used as input2223100900011 in Monte Carlo calculation by E-cut-off = 0.45 MeV . 2223100900012 ERR-ANALYS (ERR-T) Total error 2223100900013 (ERR-1,,10.) Correction uncertainty less 10.% 2223100900014 STATUS (TABLE) Table 1 of J.Radiation Protection Dosimetry,44,2223100900015 31,1992 2223100900016 This Subent supersedes Subent 22231.006 2223100900017 HISTORY (20181111C) M.M. Subent was added. 2223100900018 (20200808A) SD: SF8=MSC added to REACTION code with 2223100900019 explanation. 2223100900020 ENDBIB 18 0 2223100900021 COMMON 1 3 2223100900022 E-LVL 2223100900023 MEV 2223100900024 0. 2223100900025 ENDCOMMON 3 0 2223100900026 DATA 8 33 2223100900027 EN EN-ERR EN-RSL E-EXC-MIN E-EXC-MAX E-EXC-MEAN 2223100900028 DATA ERR-T 2223100900029 MEV MEV MEV MEV MEV MEV 2223100900030 MB MB 2223100900031 11.9 0.030 0.095 8. 10.25 9.6 2223100900032 134.8 4.6 2223100900033 11.9 0.030 0.095 10.25 11.25 10.75 2223100900034 21.0 3.0 2223100900035 11.9 0.030 0.095 11.25 12.25 11.75 2223100900036 1.5 0.7 2223100900037 12.9 0.030 0.085 8. 10.25 9.6 2223100900038 71.7 8.5 2223100900039 12.9 0.030 0.085 10.25 11.25 10.75 2223100900040 51.6 4.7 2223100900041 12.9 0.030 0.085 11.25 12.25 11.75 2223100900042 10.3 1.7 2223100900043 12.9 0.030 0.085 12.25 13.25 12.75 2223100900044 0.7 0.5 2223100900045 14.0 0.006 0.100 8. 10.25 9.6 2223100900046 76.5 8.1 2223100900047 14.0 0.006 0.100 10.25 11.25 10.75 2223100900048 30.8 2.6 2223100900049 14.0 0.006 0.100 11.25 12.25 11.75 2223100900050 23.1 1.8 2223100900051 14.0 0.006 0.100 12.25 13.25 12.75 2223100900052 4.5 0.6 2223100900053 14.0 0.006 0.100 13.25 14.25 13.75 2223100900054 0.5 0.2 2223100900055 14.8 0.016 0.240 8. 10.25 9.6 2223100900056 69.0 8.4 2223100900057 14.8 0.016 0.240 10.25 11.25 10.75 2223100900058 22.5 2.9 2223100900059 14.8 0.016 0.240 11.25 12.25 11.75 2223100900060 20.6 2.6 2223100900061 14.8 0.016 0.240 12.25 13.25 12.75 2223100900062 15.1 1.9 2223100900063 14.8 0.016 0.240 13.25 14.25 13.75 2223100900064 2.7 0.7 2223100900065 17.0 0.050 0.700 8. 10.25 9.6 2223100900066 44.5 4.9 2223100900067 17.0 0.050 0.700 10.25 11.25 10.75 2223100900068 14.7 1.8 2223100900069 17.0 0.050 0.700 11.25 12.25 11.75 2223100900070 11.9 1.5 2223100900071 17.0 0.050 0.700 12.25 13.25 12.75 2223100900072 14.6 1.8 2223100900073 17.0 0.050 0.700 13.25 14.25 13.75 2223100900074 11.2 1.5 2223100900075 17.0 0.050 0.700 14.25 15.25 14.75 2223100900076 8.9 1.4 2223100900077 17.0 0.050 0.700 15.25 16.25 15.75 2223100900078 1.9 0.9 2223100900079 19.0 0.030 0.380 8. 10.25 9.6 2223100900080 45.9 5.3 2223100900081 19.0 0.030 0.380 10.25 11.25 10.75 2223100900082 10.7 1.9 2223100900083 19.0 0.030 0.380 11.25 12.25 11.75 2223100900084 6.0 1.3 2223100900085 19.0 0.030 0.380 12.25 13.25 12.75 2223100900086 4.7 1.0 2223100900087 19.0 0.030 0.380 13.25 14.25 13.75 2223100900088 5.7 1.1 2223100900089 19.0 0.030 0.380 14.25 15.25 14.75 2223100900090 5.5 1.1 2223100900091 19.0 0.030 0.380 15.25 16.25 15.75 2223100900092 4.7 1.0 2223100900093 19.0 0.030 0.380 16.25 17.25 16.75 2223100900094 3.9 1.0 2223100900095 19.0 0.030 0.380 17.25 18.25 17.75 2223100900096 0.5 0.4 2223100900097 ENDDATA 70 0 2223100900098 ENDSUBENT 97 0 2223100999999 SUBENT 22231010 20200808 22902223101000001 BIB 7 17 2223101000002 REACTION (6-C-12(N,N+A)4-BE-8,ISP/PAR,SIG,,MSC) 2223101000003 cross section for all (n,n3a) reactions via 8Be(g.s.) 2223101000004 and characterized by the three-alpha energy 2223101000005 EN-SEC (E-EXC,6-C-12) Min., max. and mean energies in DATA 2223101000006 block are given. 2223101000007 (LVL-NUMB,4-BE-8) 2223101000008 ANALYSIS Data of 22231.006 were re-analyzed 2223101000009 CORRECTION Low energy cut-off, Tables 1, 2 of J.Radiation 2223101000010 Protection Dosimetry,44,31,1992 data were used as input2223101000011 in Monte Carlo calculation by E-cut-off = 0.45 MeV . 2223101000012 ERR-ANALYS (ERR-T) Total error 2223101000013 (ERR-1,,10.) Correction uncertainty less 10.% 2223101000014 STATUS (TABLE) Table 1 of J.Radiation Protection Dosimetry,44,2223101000015 31,1992 2223101000016 HISTORY (20181111C) M.M. Subent was added. 2223101000017 (20200808A) SD: SF8=MSC added to REACTION code with 2223101000018 explanation. 2223101000019 ENDBIB 17 0 2223101000020 COMMON 1 3 2223101000021 LVL-NUMB 2223101000022 NO-DIM 2223101000023 1. 2223101000024 ENDCOMMON 3 0 2223101000025 DATA 8 27 2223101000026 EN EN-ERR EN-RSL E-EXC-MIN E-EXC-MAX E-EXC-MEAN 2223101000027 DATA ERR-T 2223101000028 MEV MEV MEV MEV MEV MEV 2223101000029 MB MB 2223101000030 11.9 0.030 0.095 10.25 11.25 10.75 2223101000031 19.3 2.1 2223101000032 11.9 0.030 0.095 11.25 12.25 11.75 2223101000033 0.1 0.1 2223101000034 12.9 0.030 0.085 10.25 11.25 10.75 2223101000035 23.7 2.4 2223101000036 12.9 0.030 0.085 11.25 12.25 11.75 2223101000037 10.6 1.7 2223101000038 12.9 0.030 0.085 12.25 13.25 12.75 2223101000039 0.5 0.3 2223101000040 14.0 0.006 0.100 10.25 11.25 10.75 2223101000041 16.1 1.8 2223101000042 14.0 0.006 0.100 11.25 12.25 11.75 2223101000043 35.2 2.6 2223101000044 14.0 0.006 0.100 12.25 13.25 12.75 2223101000045 14.3 1.9 2223101000046 14.0 0.006 0.100 13.25 14.25 13.75 2223101000047 0.7 0.3 2223101000048 14.8 0.016 0.240 10.25 11.25 10.75 2223101000049 13.6 1.7 2223101000050 14.8 0.016 0.240 11.25 12.25 11.75 2223101000051 32.6 2.5 2223101000052 14.8 0.016 0.240 12.25 13.25 12.75 2223101000053 41.1 4.0 2223101000054 14.8 0.016 0.240 13.25 14.25 13.75 2223101000055 10.1 1.7 2223101000056 17.0 0.050 0.700 10.25 11.25 10.75 2223101000057 10.3 1.6 2223101000058 17.0 0.050 0.700 11.25 12.25 11.75 2223101000059 23.8 1.8 2223101000060 17.0 0.050 0.700 12.25 13.25 12.75 2223101000061 44.2 3.8 2223101000062 17.0 0.050 0.700 13.25 14.25 13.75 2223101000063 39.7 3.5 2223101000064 17.0 0.050 0.700 14.25 15.25 14.75 2223101000065 31.8 3.3 2223101000066 17.0 0.050 0.700 15.25 16.25 15.75 2223101000067 14.2 2.0 2223101000068 19.0 0.030 0.380 10.25 11.25 10.75 2223101000069 10.7 1.7 2223101000070 19.0 0.030 0.380 11.25 12.25 11.75 2223101000071 27.2 2.4 2223101000072 19.0 0.030 0.380 12.25 13.25 12.75 2223101000073 26.1 2.4 2223101000074 19.0 0.030 0.380 13.25 14.25 13.75 2223101000075 31.6 2.8 2223101000076 19.0 0.030 0.380 14.25 15.25 14.75 2223101000077 39.6 3.6 2223101000078 19.0 0.030 0.380 15.25 16.25 15.75 2223101000079 43.4 3.8 2223101000080 19.0 0.030 0.380 16.25 17.25 16.75 2223101000081 28.2 2.6 2223101000082 19.0 0.030 0.380 17.25 18.25 17.75 2223101000083 10.2 1.9 2223101000084 ENDDATA 58 0 2223101000085 ENDSUBENT 84 0 2223101099999 SUBENT 22231011 20181030 22722223101100001 BIB 9 24 2223101100002 REACTION 1(6-C-12(N,N+2A)2-HE-4,,KER,,,DERIV) Kerma factor KF 2223101100003 n + 12C -> n + 3 alpha break up reaction. 2223101100004 2(6-C-12(N,N+2A)2-HE-4,,KE) 2223101100005 MONITOR 1(6-C-12(N,N+2A)2-HE-4,,SIG) 2223101100006 MONIT-REF 1(22231001,B.Antolkovic+,J,NSE,107,1,1991) 2223101100007 ANALYSIS 1 Kerma factor KF = Nc*EPSa*SIG, where 2223101100008 Nc - number of C-12 nuclides per unit mass, 2223101100009 EPSa - mean energy transferred to the kinetic energy 2223101100010 of alpha particles, 2223101100011 SIG - C12(n,n3alpha) reaction cross section. 2223101100012 CORRECTION Low energy cut-off, Tables 1, 2 of J.Radiation 2223101100013 Protection Dosimetry,44,31,1992 data were used as input2223101100014 in Monte Carlo calculation by E-cut-off = 0.45 MeV . 2223101100015 REL-REF (A,,B.Antolkovic+,J,RR,97,253,1984) 2223101100016 Mean energy agree, kerma factors higher 2223101100017 (D,,R.C.Haight+,J,NSE,87,41,1984) 2223101100018 KF=0.56+-0.08 at 1.55 MeV 2223101100019 (D,,G.Buehler+,J,RPD,13,13,1985) 2223101100020 KF = 0.96+-0.18 at 15. MeV, 0.80+-0.18 at 17.MeV 2223101100021 ERR-ANALYS (ERR-T) Includes statistical and correction errors. 2223101100022 (ERR-1,10.) Correction uncertainty less 10.% 2223101100023 STATUS (TABLE) Table 3 of J.Radiation Protection Dosimetry,44,2223101100024 31,1992 2223101100025 HISTORY (20181111C) M.M. Subent was added. 2223101100026 ENDBIB 24 0 2223101100027 NOCOMMON 0 0 2223101100028 DATA 6 6 2223101100029 EN EN-ERR EN-RSL DATA 1ERR-T 1DATA 22223101100030 MEV MEV MEV FGY*M2 FGY*M2 MEV 2223101100031 11.9 0.030 0.095 0.49 0.07 1.17 2223101100032 12.9 0.030 0.085 0.55 0.07 1.37 2223101100033 14.0 0.006 0.100 0.75 0.07 1.55 2223101100034 14.8 0.016 0.240 0.95 0.08 1.74 2223101100035 17.0 0.050 0.700 1.46 0.13 2.24 2223101100036 19.0 0.030 0.380 1.98 0.16 2.63 2223101100037 ENDDATA 8 0 2223101100038 ENDSUBENT 37 0 2223101199999 ENDENTRY 11 0 2223199999999