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