SUBENT 22433001 20220102 23072243300100001
BIB 15 76 2243300100002
TITLE Measurement of (n,p) cross-sections for short-lived 2243300100003
products by 13.4-14.9 MeV neutrons 2243300100004
AUTHOR (Y.Kasugai, H.Yamamoto, K.Kawade, T.Iida) 2243300100005
INSTITUTE (2JPNNAG,2JPNOSA) 2243300100006
REFERENCE (J,ANE,25,(1-3),23,1998) 2243300100007
(J,ANE,25,1285,1998) Errata. Correction of tables. 2243300100008
FACILITY (CCW,2JPNOSA) Intense 14 MeV neutron source (OKTAVIAN) 2243300100009
INC-SOURCE (D-T) The angles of irradiation with respect to the d+ 2243300100010
beam were between 0 and 155 deg, which covered the 2243300100011
neutron energies in the range 14.9-13.4 MeV. 2243300100012
In the early stage of the experiments, the samples 2243300100013
were irradiated at angles of 0, 45, 70, 95, 120 and 2243300100014
155 deg. 2243300100015
In the present arrangement the samples were irradiated 2243300100016
at angles of 0, 50, 75, 105, 125 and 155 deg. 2243300100017
Typical neutron flux was about 0.9-1.5E+8 n/cm2/sec at 2243300100018
the irradiation position. 2243300100019
Effective neutron reaction energy at each irradiation 2243300100020
point wise determined by 90Zr(n.2n)89Zr 2243300100021
93Nb(n,2n)92mNb ratio (Zr/Nb method). 2243300100022
The uncertainty in the neutron energy is estimated to 2243300100023
be +/- 50 keV. 2243300100024
SAMPLE 10 mm x 10 mm with 0.1-0.2 mm thick. 2243300100025
METHOD (ACTIV) Pneumatic sample transport system used. 2243300100026
Transfer time was about 2-4 sec. 2243300100027
DETECTOR (HPGE) Three Ge detectors (12%,4%,16% efficiency): 2243300100028
p-type HPGe, 60 cm3 for Egamma > 80 keV 2243300100029
n-type HPGe, 30 cm3 for Egamma < 80 keV 2243300100030
n-type HPGe 89cm3 for Al monitor foil 2243300100031
Each detector was covered with a 5 mm 2243300100032
acrylic absorber to reduce beta-rays. The efficiency 2243300100033
calibration was performed at a distance of 5 cm using 2243300100034
24-Na, 56-Co, 133-Ba, 152-Eu and 154-Eu Sources. 2243300100035
MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 2243300100036
ENDF/B-VI 2243300100037
CORRECTION Corrections were made for 2243300100038
- fractional contribution of low energy neutrons 2243300100039
- fluctuation of neutron flux 2243300100040
- counting loss due to coincidence sum effect 2243300100041
- deviation of gamma-ray detection efficiency due to 2243300100042
sample thickness 2243300100043
- self absorption of gamma-ray 2243300100044
- interfering reaction. 2243300100045
ERR-ANALYS (ERR-T) Total error, quadrature sum of two errors: 2243300100046
(ERR-1) Experimental error: 2243300100047
- correction for low energy neutrons (<2%) 2243300100048
- neutron flux fluctuation (<0.4%) 2243300100049
- detector efficiency: Eg >300 keV (1.5%) 2243300100050
Eg 80-300 keV (3%) 2243300100051
Eg <80 keV (5%) 2243300100052
- correction for true coincidence sum (<0.6%) 2243300100053
- correction for random coincidence sum (<0.1%) 2243300100054
- sample weight (<0.1%) 2243300100055
- self-absorption of gamma-rays (0.2-4%) 2243300100056
- counting statistics (1-20%) 2243300100057
- gamma peak area evaluation (<0.5%) 2243300100058
(ERR-2) Nuclear data error: 2243300100059
- Reference 27Al(n,a)24Na cross section (3.0%) 2243300100060
- absolute gamma intensity (0.3-10%) 2243300100061
- half-life (0-10%) 2243300100062
COMMENT Kiyoshi Kawade (2012-04-11) 2243300100063
27Al(n,p)27Mg reaction used for normalization 2243300100064
was measured with 27Al(n,alpha)24Na reaction in the 2243300100065
same irradiation. Only revision of the 27Al(n,alpha) 2243300100066
standard cross section give impact to measured 2243300100067
absolute cross sections. 2243300100068
STATUS (TABLE) Table 4 of Annal.Nucl.Energy 25(1998)23 2243300100069
HISTORY (19971209C) + + Compiled by S.M. 2243300100070
(20020627U) . . Corrected by S.M. 2243300100071
(20070521A) . . Corrected by S.M. 2243300100072
(20120409U) On. BIB updated (ERR-ANALYS etc.) SAMPLE 2243300100073
was added to Subents 2-29. Ref. on Errata was added. 2243300100074
(20150824A) SD: 14.02 MeV -> 14.01 MeV in Subents 003, 2243300100075
005, 007, 008, 010, 011, 012, 013, 014, 016, 017. One 2243300100076
point added in Subent 026. BIB updated in Subent 027. 2243300100077
(20220102A) SD: MONITOR updated in Subent 002. 2243300100078
ENDBIB 76 0 2243300100079
COMMON 1 3 2243300100080
EN-ERR 2243300100081
KEV 2243300100082
50. 2243300100083
ENDCOMMON 3 0 2243300100084
ENDSUBENT 83 0 2243300199999
SUBENT 22433024 20120409 22322243302400001
BIB 4 5 2243302400002
REACTION (47-AG-107(N,P)46-PD-107-M,,SIG) 2243302400003
SAMPLE (47-AG-107,ENR=0.9909) Ag, 70 mg, 2243302400004
Abundance: 107Ag: 99.09%, l09Ag: 0.91% 2243302400005
DECAY-DATA (46-PD-107-M,21.3SEC,DG,214.9,0.0069) 2243302400006
HISTORY (20120409A) On. ERR-T (MB) deleted. ERR-1 corrected. 2243302400007
ENDBIB 5 0 2243302400008
COMMON 1 3 2243302400009
ERR-2 2243302400010
PER-CENT 2243302400011
5.2 2243302400012
ENDCOMMON 3 0 2243302400013
DATA 4 6 2243302400014
EN DATA ERR-1 ERR-T 2243302400015
MEV MB PER-CENT PER-CENT 2243302400016
13.40 7.7 8.3 10. 2243302400017
13.65 7.3 8.0 9.6 2243302400018
13.88 7.2 8.9 10. 2243302400019
14.28 7.9 9.4 11. 2243302400020
14.58 7.4 9.9 11. 2243302400021
14.87 7.3 9.2 11. 2243302400022
ENDDATA 8 0 2243302400023
ENDSUBENT 22 0 2243302499999