SUBENT 23032001 20230213 20231011 2303200100001
BIB 18 126 2303200100002
TITLE Measurements of activation cross sections of (n,p) 2303200100003
and (n,alpha) reactions in the energy range of 2303200100004
3.5-5.9 MeV using a deuterium gas target 2303200100005
AUTHOR (M.Furuta, T.Shimizu, H.Hayashi, I.Miyazaki, 2303200100006
H.Yamamoto, M.Shibata, K.Kawade) 2303200100007
REFERENCE (J,ANE,35,1652,2008) 2303200100008
#doi:10.1016/j.anucene.2008.02.010 2303200100009
Main reference, data are given 2303200100010
(S,JAEA-C-2008-008,56,2008) 2303200100011
REL-REF (R,,R.B.Firestone,B,FIRESTONE,,,1996) Decay data taken 2303200100012
INSTITUTE (2JPNNAG) Graduate School of Engineering, Nagoya 2303200100013
University, Nagoya, Japan. M.Furuta, T.Shimizu, 2303200100014
H.Hayashi, I.Miyazaki, H.Yamamoto, K.Kawade. Experi- 2303200100015
mental site. 2303200100016
Radioisotope Research Center, Nagoya University, 2303200100017
Nagoya, Japan. M.Shibata, Corresponding author. 2303200100018
E-mail address: i45329a@nucc.cc.nagoya-u.ac.jp 2303200100019
FACILITY (VDG,2JPNNAG) Van de Graaff accelerator (KN-VdG) at 2303200100020
Nagoya University, accelerating voltage is 1 -13.5 MV 2303200100021
INC-SOURCE (D-D) The gas cell is filled with D2 at 1.6E+5 Pa and 2303200100022
is separated from the vacuum of the accelerator by a 2303200100023
2.2-micrometer thick Havar foil, which acts as 2303200100024
a window. 2303200100025
INC-SPECT 80% lay in the high-energy region, 20% in low-energy 2303200100026
region. For energy determination Al/In method is used.2303200100027
METHOD (ACTIV) 2303200100028
(STTA) Samples were sandwiched between two indium 2303200100029
monitor foils 2303200100030
SAMPLE Metallic samples were of rectangular form 10*10 mm 2303200100031
and 0.1 - 0.5 mm thick. Powder samples were wrapped 2303200100032
in a cartridge paper 1 - 2 mm thick. 2303200100033
Indium monitor metal sample is 0.2 mm thick, 150 mil- 2303200100034
ligram weight, 99.9% purity, In-115 abundance 95.71% 2303200100035
DETECTOR (HPGE) Well-type high purity Ge detector for sample 2303200100036
activity measurements; 2303200100037
Closed-end-type high purity Ge detector for 2303200100038
monitor In-115-m activity measurements 2303200100039
MONITOR (49-IN-115(N,INL)49-IN-115-M,,SIG) 2303200100040
DECAY-MON (49-IN-115-M,4.486HR,DG,336.2,0.459) 2303200100041
(12-MG-27,9.458MIN,DG,843.7,0.718) 2303200100042
MONIT-REF (,,3,JENDL-D-99,,2002) 2303200100043
JENDL Dosimetry file 99: K.Kobayashi et al., 2002. 2303200100044
JAERI, p.1344. 2303200100045
Monitor cross sections : 2303200100046
------------------------ 2303200100047
energy 27Al(n,p) 115In(n,n') 27Al(n,p)/115In(n,n') 2303200100048
MeV mb mb No-dim 2303200100049
3.00 1.44 340.40 0.0043 2303200100050
3.20 2.75 337.82 0.0081 2303200100051
3.40 4.05 335.24 0.0121 2303200100052
3.60 5.36 330.50 0.0162 2303200100053
3.80 6.65 325.03 0.0205 2303200100054
4.00 8.52 319.57 0.0267 2303200100055
4.20 12.07 314.69 0.0384 2303200100056
4.40 15.62 318.04 0.0491 2303200100057
4.60 19.17 321.99 0.0595 2303200100058
4.80 22.72 325.93 0.0697 2303200100059
5.00 27.11 329.87 0.0822 2303200100060
5.20 34.05 333.81 0.1020 2303200100061
5.40 40.99 337.76 0.1214 2303200100062
5.60 47.93 341.70 0.1403 2303200100063
5.80 54.87 345.64 0.1587 2303200100064
6.00 60.15 348.40 0.1726 2303200100065
6.20 60.47 347.35 0.1741 2303200100066
6.40 60.78 342.77 0.1773 2303200100067
6.60 61.10 337.94 0.1808 2303200100068
6.80 61.41 333.10 0.1844 2303200100069
7.00 62.51 328.27 0.1904 2303200100070
CORRECTION Corrections were made for low-energy neutrons. 2303200100071
Magnitude of these corrections are: 2303200100072
... 2303200100073
Reaction Magnitude,% 2303200100074
min max 2303200100075
27Al(n,p)27Mg 11 71 2303200100076
28Si(n,p)28Al 28 83 2303200100077
29Si(n,p)29Al 24 52 2303200100078
41K(n,p) 41Ar 12 42 2303200100079
51V(n,p) 51Ti 23 75 2303200100080
61Ni(n,p)61Co 19 54 2303200100081
65Cu(n,p)65Ni 31 60 2303200100082
64Zn(n,p)64Cu 8 35 2303200100083
67Zn(n,p)67Cu 14 37 2303200100084
69Ga(n,p)69mZn 22 45 2303200100085
79Br(n,p)79mSe 10 33 2303200100086
92Mo(n,p)92mNb 18 50 2303200100087
69Ga(n,a)66Cu 38 74 2303200100088
93Nb(n,a)90mY 18 40 2303200100089
ERR-ANALYS (ERR-T) Total error 2303200100090
Source of error - experimental errorS 2303200100091
(ERR-S,0.5,72.) Error range of counting statistics. 2303200100092
Min error = 0.5%. The uncertainty of counting 2303200100093
statistics for most of the data is 30% or less. 2303200100094
(ERR-SYS) Systematic error called "experimental" by 2303200100095
the authors. Includes ERR-S, ERR-2 to ERR-11,ERR-13 2303200100096
(MONIT-ERR) General error of In115(n,n') monitor 2303200100097
cross sections 2303200100098
(ERR-1) Error of the Al-27(n,p)/In-115(n,n') cross 2303200100099
sections 2303200100100
(ERR-2,4.,42.) Error range for low-energy neutrons 2303200100101
(ERR-3,,11.) Max fluctuation of neutron fluence rate 2303200100102
(ERR-4) Detector efficiency error (Eg = 80-300 keV) 2303200100103
(ERR-5) Detector efficiency error (Eg > 300 keV) 2303200100104
(ERR-6,1.2,4.5) Error range for efficiency calibration 2303200100105
(ERR-7,,0.6) Max true coincidence sum error 2303200100106
(ERR-8) Sample weight error 2303200100107
(ERR-9,,0.6) Max sample thickness error 2303200100108
(ERR-10,0.02,2.5) Error range for gamma self-absorp. 2303200100109
(ERR-11) Gamma-ray peak area evaluation 0.5 2303200100110
(ERR-12,0.004,24.3) Error range gamma emission prob. 2303200100111
(ERR-13,,15.) The uncertainty of background low-energy 2303200100112
neutrons for most of the data is 15% or less. 2303200100113
(ERR-14,0.004,24.3) Error of the monitor decay 2303200100114
gamma-ray intensity 2303200100115
(ERR-15) Error due to the nuclear data. Includes 2303200100116
MONIT-ERR, ERR-12 and decay errors 2303200100117
(HL-ERR) Error of the In-115-m half life 2303200100118
STATUS (TABLE) Table 6 from JAEA-C-2008-008,56,2008 2303200100119
HISTORY (20081022C) SM 2303200100120
(20101223U) addition of ref. JAEA-C-2008-006 2303200100121
(20110310U) SD: ref. JAEA-C-2008-006 corrected on 2303200100122
JAEA-C-2008-008. 2303200100123
(20220218U) SD: Monitor: 13-AL-27(N,P)12-MG-27 deleted2303200100124
(used for neutron energy determination only). HL-ERR 2303200100125
deleted (error included in ERR-15). 2303200100126
(20230213A) SD: Correction in Subent 008. 2303200100127
ERR-14 deleted (absent in the article). 2303200100128
ENDBIB 126 0 2303200100129
COMMON 7 6 2303200100130
EN-ERR MONIT-ERR ERR-1 ERR-4 ERR-5 ERR-8 2303200100131
ERR-11 2303200100132
KEV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2303200100133
PER-CENT 2303200100134
100. 3. 4. 3. 1.5 0.12303200100135
0.5 2303200100136
ENDCOMMON 6 0 2303200100137
ENDSUBENT 136 0 2303200199999
SUBENT 23032012 20081022 22032303201200001
BIB 5 9 2303201200002
REACTION (35-BR-79(N,P)34-SE-79-M,,SIG) 2303201200003
DECAY-DATA (34-SE-79-M,3.92MIN,DG,95.7,0.0962) 2303201200004
SAMPLE .Natural K-Br, 99.9% purity, weight 82 milligram, 2303201200005
thickness 1.70 mm, Br-79 abundance 50.69% 2303201200006
REL-REF .The data in FENDL/A-2.0 agree with the present results2303201200007
within 30%. JENDL-3.3 gives total values, not meta- 2303201200008
stable ones. 2303201200009
ERR-ANALYS (ERR-HL) Error of half-life 2303201200010
(ERR-IDD) Error of decay gamma intensity 2303201200011
ENDBIB 9 0 2303201200012
COMMON 3 3 2303201200013
ERR-15 ERR-HL ERR-IDD 2303201200014
PER-CENT MIN NO-DIM 2303201200015
4.5 0.01 0.0028 2303201200016
ENDCOMMON 3 0 2303201200017
DATA 4 3 2303201200018
EN DATA ERR-T ERR-SYS 2303201200019
MEV MB PER-CENT PER-CENT 2303201200020
5.61 2.6 43. 43. 2303201200021
5.25 2.9 18. 17. 2303201200022
5.17 3.8 20. 20. 2303201200023
ENDDATA 5 0 2303201200024
ENDSUBENT 23 0 2303201299999