ENTRY 22754 20200117 22852275400000001
SUBENT 22754001 20200117 22852275400100001
BIB 9 29 2275400100002
TITLE Measurement of (n,2n) cross-sections for several 2275400100003
dosimetry reactions between 12 and 20 MeV. 2275400100004
AUTHOR (M.Sakuma, S.Iwasaki, H.Shimada, N.Odano, K.Suda, 2275400100005
J.R.Dumais, K.Sugiyama) 2275400100006
INSTITUTE (2JPNTOH) 2275400100007
REFERENCE (R,JAERI-M-92-027,278,1992) Main Ref. 197Au(n,2n) data 2275400100008
(J,PNE,26,231,1991) First author S.Iwasaki. 2275400100009
Graphs of cross section ratios Nb/Al, Au/Al. 2275400100010
(R,JAERI-M-93-046,257,1993) First author S.Iwasaki. 2275400100011
Other data of this report are in Entry 22751. 2275400100012
FACILITY (DYNAM,2JPNTOH) Tohoku University 4.5-MV Dynamitron 2275400100013
Accelerator of Fast Neutron Laboratory. 2275400100014
INC-SOURCE (D-T) T(d,n)He-4 reaction. Incident deuteron beam 2275400100015
energy about 3 MeV. Air-cooled Ti-T target, Ti-layer 2275400100016
of 11 mm diameter, 10.1 mg/cm**2 thickness, on copper 2275400100017
backing of 0.5mm thickness, mounted in thin copper 2275400100018
chamber (circular tube of 70 mm long, 14mm outer 2275400100019
diameter, 1 mm thick wall, end plate of 0.5 mm thick).2275400100020
Beam profile was measured to be two-dimensional 2275400100021
Gaussian distribution of 4-mm FWHM. 2275400100022
INC-SPECT Neutron intensity was monitored with NE-213 detector. 2275400100023
DETECTOR (SCIN) NE-213 liquid scintillation detector,2" diameter2275400100024
2" thickness. For neutron intensity monitoring. 2275400100025
(HPGE) 80 cc high-purity germanium detector calibrated2275400100026
with a set of standard gamma-ray source. For gamma-ray2275400100027
of sample foils. 2275400100028
HISTORY (20081006C) M.M. 2275400100029
(20200117A) SD: DECAY-DATA corrected in Subents 002-0052275400100030
ERR-ANALYS updated in Subents 002-009. 2275400100031
ENDBIB 29 0 2275400100032
NOCOMMON 0 0 2275400100033
ENDSUBENT 32 0 2275400199999
SUBENT 22754002 20200117 22852275400200001
BIB 9 53 2275400200002
REACTION ((41-NB-93(N,2N)41-NB-92-M,,SIG)/ 2275400200003
(13-AL-27(N,A)11-NA-24,,SIG)) 2275400200004
SAMPLE Rectangular foils 10mmx10mmx0.5mm(thickness) . 2275400200005
Sample set was composed of two Al foils sandwiched 2275400200006
between Nb foils with Au foil opposite the target. 2275400200007
METHOD (ACTIV) 1-st series of irradiations for c-s ratios: 2275400200008
Neutron energy 19.9-12.8 MeV, angle for irradiation2275400200009
0-140 deg., d+ energy 3.26MeV, beam current 10 microA,2275400200010
irradiation time 50 hours. 2275400200011
(TOF) Angular spectra of source neutrons were 2275400200012
measured by TOF technique at angles from 0 to 150 deg 2275400200013
at intervals of 10 or 5 deg. 2275400200014
(GSPEC) Gamma-rays from samples were measured. 2275400200015
DECAY-DATA (41-NB-92-M,10.15D,DG,934.53,0.990) 2275400200016
Measured gamma-ray 934.53+-0.05 keV with emission 2275400200017
probability 0.990+-0.002 . HL error 0.02 d. 2275400200018
(11-NA-24,14.959HR,B-,,,DG,1368.633,0.99994) 2275400200019
Measured gamma-ray 1368.633+-0.006 with emission 2275400200020
probability 0.99994+-0.002. HL error 0.004 hr. 2275400200021
Decay data from J.H.Baard,W.L.Ziip,H.J.Nolthenius,19892275400200022
Nuclear Data Guide for Reactor Neutron Metrology, 2275400200023
Kluwer Academic Publ., Dordrecht, Netherlands. 2275400200024
ANALYSIS Cross sections ratio was derived from ratio of 2275400200025
reaction-rates. 2275400200026
CORRECTION - Fluctuation of neutron flux during irradiation. 2275400200027
- Difference of neutron flux between foils. 2275400200028
- Nonmonochromaticity of irradiating neutrons. 2275400200029
- Contribution of parasitic D(d,n)He-3 neutrons to 2275400200030
reaction rate of Al-27(n,alpha)Na-24 . 2275400200031
- Finite dimensions of sample foils. 2275400200032
- Self-absorption of gamma-rays in the foils. 2275400200033
- Sum-coincidence effect of cascade gamma-rays for Al 2275400200034
samples was evaluated experimentally to be less 1%, 2275400200035
was included in uncertainties of efficiencies.. 2275400200036
ERR-ANALYS (ERR-T) Total uncertainty 2.5 - 7.0 % is given as 2275400200037
error bar on Fig.2 2275400200038
(ERR-S,0.7,2.0) Uncertainty in counting statistics of 2275400200039
gamma-ray - 0.7-2.0 %. 2275400200040
(ERR-1,2.1,4.5) Uncertainty in detection efficiency 2275400200041
of gamma-ray - 2.1-4.5 %. 2275400200042
(ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 2275400200043
(ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 2275400200044
(ERR-4,0.1,0.2) Uncertainty in decay half-life of 2275400200045
nuclei - 0.1-0.2%. 2275400200046
(ERR-5,0.002,2.6) Uncertainty in emission probability 2275400200047
of gamma-ray - 0.002-2.6% 2275400200048
(2.6% -for gamma-rays from Au-196). 2275400200049
(ERR-6,,0.1) Uncertainty due corrections < 0.1% . 2275400200050
STATUS (CURVE) Fig.2 of JAERI-M-92-027,278(triangl.,1-st exp.)2275400200051
Fig.3 of Progr.Nucl.En.,26(1991)231 2275400200052
(COREL,22754003) Data from Run 2 2275400200053
HISTORY (20200117A) SD: DECAY-DATA corrected, STATUS, 2275400200054
ERR-ANALYS updated. DATA-ERR -> ERR-T. 2275400200055
ENDBIB 53 0 2275400200056
COMMON 2 3 2275400200057
EN-ERR-DIG ERR-DIG 2275400200058
MEV NO-DIM 2275400200059
0.16495E-010.16805E-01 2275400200060
ENDCOMMON 3 0 2275400200061
DATA 3 10 2275400200062
EN DATA ERR-T 2275400200063
MEV NO-DIM NO-DIM 2275400200064
12.788 3.6878 0.15523 2275400200065
13.698 3.9773 0.20154 2275400200066
14.844 4.0598 0.18604 2275400200067
14.853 4.1372 0.18644 2275400200068
16.066 4.9625 0.24825 2275400200069
17.430 5.9704 0.31026 2275400200070
17.438 5.8617 0.30986 2275400200071
18.669 6.6556 0.38798 2275400200072
19.583 7.5498 0.38778 2275400200073
19.911 7.9145 0.38738 2275400200074
ENDDATA 12 0 2275400200075
ENDSUBENT 74 0 2275400299999
SUBENT 22754003 20200117 22852275400300001
BIB 9 54 2275400300002
REACTION ((41-NB-93(N,2N)41-NB-92-M,,SIG)/ 2275400300003
(13-AL-27(N,A)11-NA-24,,SIG)) 2275400300004
SAMPLE Rectangular foils 20mm x 5mm x 0.5mm(thickness) in 2275400300005
second irradiation, except Au foils of 0.2mm thick. 2275400300006
Sample set was composed of two Al foils sandwiched 2275400300007
between Nb foils with Au foil opposite the target. 2275400300008
METHOD (ACTIV) 2-nd series of irradiations for c-s ratios: 2275400300009
Neutron energy 19.4-12.7 MeV, angle for irradiation2275400300010
0-140 deg., d+ energy 2.85MeV, beam current 10 microA,2275400300011
irradiation time 36 hours. 2275400300012
(TOF) Angular spectra of source neutrons were 2275400300013
measured by TOF technique at angles from 0 to 150 deg 2275400300014
at intervals of 10 or 5 deg. 2275400300015
(GSPEC) Gamma-rays from samples were measured. 2275400300016
DECAY-DATA (41-NB-92-M,10.15D,DG,934.53,0.990) 2275400300017
Measured gamma-ray 934.53+-0.05 keV with emission 2275400300018
probability 0.990+-0.002 . HL error 0.02 d. 2275400300019
(11-NA-24,14.959HR,B-,,,DG,1368.633,0.99994) 2275400300020
Measured gamma-ray 1368.633+-0.006 with emission 2275400300021
probability 0.99994+-0.002. HL error 0.004 hr. 2275400300022
Decay data from J.H.Baard,W.L.Ziip,H.J.Nolthenius,19892275400300023
Nuclear Data Guide for Reactor Neutron Metrology, 2275400300024
Kluwer Academic Publ., Dordrecht, Netherlands. 2275400300025
ANALYSIS Cross sections ratio was derived from ratio of 2275400300026
reaction-rates. 2275400300027
CORRECTION - Fluctuation of neutron flux during irradiation. 2275400300028
- Difference of neutron flux between foils. 2275400300029
- Nonmonochromaticity of irradiating neutrons. 2275400300030
- Contribution of parasitic D(d,n)He-3 neutrons to 2275400300031
reaction rate of Al-27(n,alpha)Na-24 . 2275400300032
- Finite dimensions of sample foils. 2275400300033
- Self-absorption of gamma-rays in the foils. 2275400300034
- Sum-coincidence effect of cascade gamma-rays for Al 2275400300035
samples was evaluated experimentally to be less 1%, 2275400300036
was included in uncertainties of efficiencies.. 2275400300037
ERR-ANALYS (ERR-T) Total uncertainty 2.5 - 7.0 % is given as 2275400300038
error bar on Fig.2 2275400300039
(ERR-S,0.7,2.0) Uncertainty in counting statistics of 2275400300040
gamma-ray - 0.7-2.0 %. 2275400300041
(ERR-1,2.1,4.5) Uncertainty in detection efficiency 2275400300042
of gamma-ray - 2.1-4.5 %. 2275400300043
(ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 2275400300044
(ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 2275400300045
(ERR-4,0.1,0.2) Uncertainty in decay half-life of 2275400300046
nuclei - 0.1-0.2%. 2275400300047
(ERR-5,0.002,2.6) Uncertainty in emission probability 2275400300048
of gamma-ray - 0.002-2.6% 2275400300049
(2.6% -for gamma-rays from Au-196). 2275400300050
(ERR-6,,0.1) Uncertainty due corrections < 0.1% . 2275400300051
STATUS (CURVE) Fig.2 of JAERI-M-92-027,278(circles, 2-nd exp.)2275400300052
Fig.3 of Progr.Nucl.En.,26(1991)231 2275400300053
(COREL,22754002) Data from Run 1 2275400300054
HISTORY (20200117A) SD: DECAY-DATA corrected, STATUS, 2275400300055
ERR-ANALYS updated. DATA-ERR -> ERR-T. 2275400300056
ENDBIB 54 0 2275400300057
COMMON 2 3 2275400300058
EN-ERR-DIG ERR-DIG 2275400300059
MEV NO-DIM 2275400300060
0.16495E-010.16805E-01 2275400300061
ENDCOMMON 3 0 2275400300062
DATA 3 17 2275400300063
EN DATA ERR-T 2275400300064
MEV NO-DIM NO-DIM 2275400300065
12.832 3.6558 0.77316E-01 2275400300066
13.017 3.7291 0.62212E-01 2275400300067
13.660 3.6990 0.77516E-01 2275400300068
13.897 3.5231 0.77516E-01 2275400300069
14.720 4.0006 0.62411E-01 2275400300070
15.012 4.1646 0.77516E-01 2275400300071
15.974 4.3909 0.77515E-01 2275400300072
16.285 4.8180 0.62012E-01 2275400300073
17.198 5.4795 0.10852 2275400300074
17.487 5.3334 0.10852 2275400300075
17.490 5.7365 0.93218E-01 2275400300076
18.326 6.8495 0.15503 2275400300077
18.574 6.9059 0.15523 2275400300078
19.166 7.2646 0.15523 2275400300079
19.306 7.0754 0.18604 2275400300080
19.511 7.4118 0.20154 2275400300081
19.512 7.4893 0.18584 2275400300082
ENDDATA 19 0 2275400300083
ENDSUBENT 82 0 2275400399999
SUBENT 22754004 20200117 22852275400400001
BIB 9 53 2275400400002
REACTION ((79-AU-197(N,2N)79-AU-196,,SIG)/ 2275400400003
(13-AL-27(N,A)11-NA-24,,SIG)) 2275400400004
SAMPLE Rectangular foils 10mmx10mmx0.5mm(thickness) . 2275400400005
Sample set was composed of two Al foils sandwiched 2275400400006
between Nb foils with Au foil opposite the target. 2275400400007
METHOD (ACTIV) 1-st series of irradiations for c-s ratios: 2275400400008
Neutron energy 19.9-12.8 MeV, angle for irradiation2275400400009
0-140 deg., d+ energy 3.26MeV, beam current 10 microA,2275400400010
irradiation time 50 hours. 2275400400011
(TOF) Angular spectra of source neutrons were 2275400400012
measured by TOF technique at angles from 0 to 150 deg 2275400400013
at intervals of 10 or 5 deg. 2275400400014
(GSPEC) Gamma-rays from samples were measured. 2275400400015
DECAY-DATA (79-AU-196-G,6.183D,DG,355.73,0.869) 2275400400016
Measured gamma-ray 355.73+-0.05 keV with emission 2275400400017
probability 0.869+-0.010 . HL error 0.010 d. 2275400400018
(11-NA-24,14.959HR,B-,,,DG,1368.633,0.99994) 2275400400019
Measured gamma-ray 1368.633+-0.006 with emission 2275400400020
probability 0.99994+-0.002. HL error 0.004 hr. 2275400400021
Decay data from J.H.Baard,W.L.Ziip,H.J.Nolthenius,19892275400400022
Nuclear Data Guide for Reactor Neutron Metrology, 2275400400023
Kluwer Academic Publ., Dordrecht, Netherlands. 2275400400024
ANALYSIS Cross sections ratio was derived from ratio of 2275400400025
reaction-rates. 2275400400026
CORRECTION - Fluctuation of neutron flux during irradiation. 2275400400027
- Difference of neutron flux between foils. 2275400400028
- Nonmonochromaticity of irradiating neutrons. 2275400400029
- Contribution of parasitic D(d,n)He-3 neutrons to 2275400400030
reaction rate of Al-27(n,alpha)Na-24 . 2275400400031
- Finite dimensions of sample foils. 2275400400032
- Self-absorption of gamma-rays in the foils. 2275400400033
- Sum-coincidence effect of cascade gamma-rays for Al 2275400400034
samples was evaluated experimentally to be less 1%, 2275400400035
was included in uncertainties of efficiencies.. 2275400400036
ERR-ANALYS (ERR-T) Total uncertainty 2.5 - 7.0 % is given as 2275400400037
error bar on Fig.3 2275400400038
(ERR-S,0.7,2.0) Uncertainty in counting statistics of 2275400400039
gamma-ray - 0.7-2.0 %. 2275400400040
(ERR-1,2.1,4.5) Uncertainty in detection efficiency 2275400400041
of gamma-ray - 2.1-4.5 %. 2275400400042
(ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 2275400400043
(ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 2275400400044
(ERR-4,0.1,0.2) Uncertainty in decay half-life of 2275400400045
nuclei - 0.1-0.2%. 2275400400046
(ERR-5,0.002,2.6) Uncertainty in emission probability 2275400400047
of gamma-ray - 0.002-2.6% 2275400400048
(2.6% -for gamma-rays from Au-196). 2275400400049
(ERR-6,,0.1) Uncertainty due corrections < 0.1% . 2275400400050
STATUS (CURVE) Fig.3 of JAERI-M-92-027,278(triangl.,1-st exp),2275400400051
Fig.4 of Progr.Nucl.En.,26(1991)231 2275400400052
(COREL,22754005) Data from Run 2 2275400400053
HISTORY (20200117A) SD: DECAY-DATA corrected, STATUS, 2275400400054
ERR-ANALYS updated. DATA-ERR -> ERR-T. 2275400400055
ENDBIB 53 0 2275400400056
COMMON 2 3 2275400400057
EN-ERR-DIG ERR-DIG 2275400400058
MEV NO-DIM 2275400400059
0.15647E-010.57175E-01 2275400400060
ENDCOMMON 3 0 2275400400061
DATA 3 12 2275400400062
EN DATA ERR-T 2275400400063
MEV NO-DIM NO-DIM 2275400400064
12.778 16.794 0.68125 2275400400065
12.779 17.213 0.94327 2275400400066
13.682 18.498 0.99491 2275400400067
13.699 18.130 0.94174 2275400400068
14.836 17.979 0.78605 2275400400069
16.056 23.168 1.6777 2275400400070
17.421 25.724 1.3625 2275400400071
17.422 26.457 1.4681 2275400400072
18.646 25.513 1.7825 2275400400073
19.567 27.321 1.5205 2275400400074
19.902 27.187 1.4149 2275400400075
19.903 27.711 1.5721 2275400400076
ENDDATA 14 0 2275400400077
ENDSUBENT 76 0 2275400499999
SUBENT 22754005 20200117 22852275400500001
BIB 9 54 2275400500002
REACTION ((79-AU-197(N,2N)79-AU-196,,SIG)/ 2275400500003
(13-AL-27(N,A)11-NA-24,,SIG)) 2275400500004
SAMPLE Rectangular foils 20mmx5mmx0.5mm(thickness) in 2275400500005
second irradiation, except Au foils of 0.2mm thick. 2275400500006
Sample set was composed of two Al foils sandwiched 2275400500007
between Nb foils with Au foil opposite the target. 2275400500008
METHOD (ACTIV) 2-nd series of irradiations for c-s ratios: 2275400500009
Neutron energy 19.4-12.7 MeV, angle for irradiation2275400500010
0-140 deg., d+ energy 2.85MeV, beam current 10 microA,2275400500011
irradiation time 36 hours. 2275400500012
(TOF) Angular spectra of source neutrons were 2275400500013
measured by TOF technique at angles from 0 to 150 deg 2275400500014
at intervals of 10 or 5 deg. 2275400500015
(GSPEC) Gamma-rays from samples were measured. 2275400500016
DECAY-DATA (79-AU-196-G,6.183D,DG,355.73,0.869) 2275400500017
Measured gamma-ray 355.73+-0.05 keV with emission 2275400500018
probability 0.869+-0.010 . HL error 0.010 d. 2275400500019
(11-NA-24,14.959HR,B-,,,DG,1368.633,0.99994) 2275400500020
Measured gamma-ray 1368.633+-0.006 with emission 2275400500021
probability 0.99994+-0.002. HL error 0.004 hr. 2275400500022
Decay data from J.H.Baard,W.L.Ziip,H.J.Nolthenius,19892275400500023
Nuclear Data Guide for Reactor Neutron Metrology, 2275400500024
Kluwer Academic Publ., Dordrecht, Netherlands. 2275400500025
ANALYSIS Cross sections ratio was derived from ratio of 2275400500026
reaction-rates. 2275400500027
CORRECTION - Fluctuation of neutron flux during irradiation. 2275400500028
- Difference of neutron flux between foils. 2275400500029
- Nonmonochromaticity of irradiating neutrons. 2275400500030
- Contribution of parasitic D(d,n)He-3 neutrons to 2275400500031
reaction rate of Al-27(n,alpha)Na-24 . 2275400500032
- Finite dimensions of sample foils. 2275400500033
- Self-absorption of gamma-rays in the foils. 2275400500034
- Sum-coincidence effect of cascade gamma-rays for Al 2275400500035
samples was evaluated experimentally to be less 1%, 2275400500036
was included in uncertainties of efficiencies.. 2275400500037
ERR-ANALYS (ERR-T) Total uncertainty 2.5 - 7.0 % is given as 2275400500038
error bar on Fig.3 2275400500039
(ERR-S,0.7,2.0) Uncertainty in counting statistics of 2275400500040
gamma-ray - 0.7-2.0 %. 2275400500041
(ERR-1,2.1,4.5) Uncertainty in detection efficiency 2275400500042
of gamma-ray - 2.1-4.5 %. 2275400500043
(ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 2275400500044
(ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 2275400500045
(ERR-4,0.1,0.2) Uncertainty in decay half-life of 2275400500046
nuclei - 0.1-0.2%. 2275400500047
(ERR-5,0.002,2.6) Uncertainty in emission probability 2275400500048
of gamma-ray - 0.002-2.6% 2275400500049
(2.6% -for gamma-rays from Au-196). 2275400500050
(ERR-6,,0.1) Uncertainty due corrections < 0.1% . 2275400500051
STATUS (CURVE) Fig.3 of JAERI-M-92-027,278(circles, 2-nd exp.)2275400500052
Fig.4 of Progr.Nucl.En.,26(1991)231 2275400500053
(COREL,22754004) Data from Run 1 2275400500054
HISTORY (20200117A) SD: DECAY-DATA corrected, STATUS, 2275400500055
ERR-ANALYS updated. DATA-ERR -> ERR-T. 2275400500056
ENDBIB 54 0 2275400500057
COMMON 2 3 2275400500058
EN-ERR-DIG ERR-DIG 2275400500059
MEV NO-DIM 2275400500060
0.15647E-010.57175E-01 2275400500061
ENDCOMMON 3 0 2275400500062
DATA 3 10 2275400500063
EN DATA ERR-T 2275400500064
MEV NO-DIM NO-DIM 2275400500065
13.009 17.403 0.47163 2275400500066
15.005 18.856 0.52403 2275400500067
17.467 22.994 0.89086 2275400500068
17.471 24.828 0.62960 2275400500069
18.316 27.481 0.83846 2275400500070
18.550 26.046 0.83922 2275400500071
19.149 25.732 0.78757 2275400500072
19.280 25.144 0.78605 2275400500073
19.485 25.913 0.89162 2275400500074
19.496 27.065 0.83846 2275400500075
ENDDATA 12 0 2275400500076
ENDSUBENT 75 0 2275400599999
SUBENT 22754006 20200117 22852275400600001
BIB 8 30 2275400600002
REACTION (11-NA-23(N,2N)11-NA-22,,SIG) 2275400600003
MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) 2275400600004
MONIT-REF (,,3,IRDF-90,,1990) 2275400600005
SAMPLE Sodium - in form of NaCl compound, packed in aluminum 2275400600006
boxes of 25 x 15 x 10 mm size and 1.5mm wall thickness.2275400600007
25mm x 15mmx 0.5mm for niobium. 2275400600008
All samples between Nb foils to determine neutron 2275400600009
flux in the sample. 2275400600010
METHOD (ACTIV) Irradiation for (n,2n) cross sections : 2275400600011
Neutron energy 19.4-15.9 MeV, angle for irradiation 2275400600012
0- 80 deg., d+ energy 2.83MeV, beam current 10 microA,2275400600013
irradiation time 84 hours. 2275400600014
ERR-ANALYS (ERR-T) Total uncertainty 3.5 - 5.5% is given as 2275400600015
error bar on Fig.5 2275400600016
(ERR-S,0.5,2.0) Uncertainty in counting statistics of 2275400600017
gamma-ray - 0.5-2.0 %. 2275400600018
(ERR-1,2.5,4.0) Uncertainty in detection efficiency 2275400600019
of gamma-ray - 2.5-4.0 %. 2275400600020
(ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 2275400600021
(ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 2275400600022
(ERR-4,0.03,0.6) Uncertainty in decay half-life of 2275400600023
nuclei - 0.03-0.6%. 2275400600024
(ERR-5,0.02,0.5) Uncertainty in emission probability 2275400600025
of gamma-ray - 0.02-0.5% 2275400600026
(2.6% -for gamma-rays from Au-196). 2275400600027
(MONIT-ERR,2.2,3.0) Uncertainty of reference cross 2275400600028
section data - 2.2 - 3.0% . 2275400600029
STATUS (CURVE) Fig.5 of JAERI-M-92-027,278 2275400600030
HISTORY (20200117A) SD: STATUS ('PRELM' - deleted), 2275400600031
ERR-ANALYS updated. DATA-ERR -> ERR-T. 2275400600032
ENDBIB 30 0 2275400600033
COMMON 2 3 2275400600034
EN-ERR-DIG ERR-DIG 2275400600035
MEV PER-CENT 2275400600036
0.16751E-01 0.37220 2275400600037
ENDCOMMON 3 0 2275400600038
DATA 3 5 2275400600039
EN DATA ERR-T 2275400600040
MEV MB MB 2275400600041
15.912 59.498 2.7211 2275400600042
17.199 84.399 3.3994 2275400600043
18.355 103.54 3.4013 2275400600044
19.123 105.42 3.4014 2275400600045
19.414 110.47 4.4218 2275400600046
ENDDATA 7 0 2275400600047
ENDSUBENT 46 0 2275400699999
SUBENT 22754007 20200117 22852275400700001
BIB 8 30 2275400700002
REACTION (25-MN-55(N,2N)25-MN-54,,SIG) 2275400700003
MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) 2275400700004
MONIT-REF (,,3,IRDF-90,,1990) 2275400700005
SAMPLE Manganese - metallic Mn powder, packed in aluminum 2275400700006
rectangular boxes of 25 x 15 x 5 mm size. 2275400700007
25mm x 15mmx 0.5mm for niobium. 2275400700008
All samples between Nb foils to determine neutron 2275400700009
flux in the sample. 2275400700010
METHOD (ACTIV) Irradiation for (n,2n) cross sections : 2275400700011
Neutron energy 19.4-15.9 MeV, angle for irradiation 2275400700012
0- 80 deg., d+ energy 2.83MeV, beam current 10 microA,2275400700013
irradiation time 84 hours. 2275400700014
ERR-ANALYS (ERR-T) Total uncertainty 3.5 - 5.5% is given as 2275400700015
error bar on Fig.6 2275400700016
(ERR-S,0.5,2.0) Uncertainty in counting statistics of 2275400700017
gamma-ray - 0.5-2.0 %. 2275400700018
(ERR-1,2.5,4.0) Uncertainty in detection efficiency 2275400700019
of gamma-ray - 2.5-4.0 %. 2275400700020
(ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 2275400700021
(ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 2275400700022
(ERR-4,0.03,0.6) Uncertainty in decay half-life of 2275400700023
nuclei - 0.03-0.6%. 2275400700024
(ERR-5,0.02,0.5) Uncertainty in emission probability 2275400700025
of gamma-ray - 0.02-0.5% 2275400700026
(2.6% -for gamma-rays from Au-196). 2275400700027
(MONIT-ERR,2.2,3.0) Uncertainty of reference cross 2275400700028
section data - 2.2 - 3.0% . 2275400700029
STATUS (CURVE) Fig.6 of JAERI-M-92-027,278 2275400700030
HISTORY (20200117A) SD: STATUS ('PRELM' - deleted), 2275400700031
ERR-ANALYS updated. DATA-ERR -> ERR-T. 2275400700032
ENDBIB 30 0 2275400700033
COMMON 2 3 2275400700034
EN-ERR-DIG ERR-DIG 2275400700035
MEV PER-CENT 2275400700036
0.21057E-010.35595E-02 2275400700037
ENDCOMMON 3 0 2275400700038
DATA 3 3 2275400700039
EN DATA ERR-T 2275400700040
MEV B B 2275400700041
17.226 0.83548 0.16279E-01 2275400700042
18.372 0.79131 0.25558E-01 2275400700043
19.147 0.82929 0.27906E-01 2275400700044
ENDDATA 5 0 2275400700045
ENDSUBENT 44 0 2275400799999
SUBENT 22754008 20200117 22852275400800001
BIB 8 29 2275400800002
REACTION (28-NI-58(N,2N)28-NI-57,,SIG) 2275400800003
MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) 2275400800004
MONIT-REF (,,3,IRDF-90,,1990) 2275400800005
SAMPLE Size of high-purity metal foils 25mm x 15mm x 0.2mm 2275400800006
for nickel and 25mm x 15mmx 0.5mm for niobium. 2275400800007
All samples between Nb foils to determine neutron 2275400800008
flux in the sample. 2275400800009
METHOD (ACTIV) Irradiation for (n,2n) cross sections : 2275400800010
Neutron energy 19.4-15.9 MeV, angle for irradiation 2275400800011
0- 80 deg., d+ energy 2.83MeV, beam current 10 microA,2275400800012
irradiation time 84 hours. 2275400800013
ERR-ANALYS (ERR-T) Total uncertainty 3.5 - 5.5% is given as 2275400800014
error bar on Fig.7 2275400800015
(ERR-S,0.5,2.0) Uncertainty in counting statistics of 2275400800016
gamma-ray - 0.5-2.0 %. 2275400800017
(ERR-1,2.5,4.0) Uncertainty in detection efficiency 2275400800018
of gamma-ray - 2.5-4.0 %. 2275400800019
(ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 2275400800020
(ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 2275400800021
(ERR-4,0.03,0.6) Uncertainty in decay half-life of 2275400800022
nuclei - 0.03-0.6%. 2275400800023
(ERR-5,0.02,0.5) Uncertainty in emission probability 2275400800024
of gamma-ray - 0.02-0.5% 2275400800025
(2.6% -for gamma-rays from Au-196). 2275400800026
(MONIT-ERR,2.2,3.0) Uncertainty of reference cross 2275400800027
section data - 2.2 - 3.0% . 2275400800028
STATUS (CURVE) Fig.7 of JAERI-M-92-027,278 2275400800029
HISTORY (20200117A) SD: STATUS ('PRELM' - deleted), 2275400800030
ERR-ANALYS updated. DATA-ERR -> ERR-T. 2275400800031
ENDBIB 29 0 2275400800032
COMMON 2 3 2275400800033
EN-ERR-DIG ERR-DIG 2275400800034
MEV PER-CENT 2275400800035
0.10126E-01 0.14684 2275400800036
ENDCOMMON 3 0 2275400800037
DATA 3 3 2275400800038
EN DATA ERR-T 2275400800039
MEV MB MB 2275400800040
17.203 59.031 1.9971 2275400800041
18.353 65.177 2.4611 2275400800042
19.134 67.732 2.4637 2275400800043
ENDDATA 5 0 2275400800044
ENDSUBENT 43 0 2275400899999
SUBENT 22754009 20200117 22852275400900001
BIB 6 17 2275400900002
REACTION (79-AU-197(N,2N)79-AU-196,,SIG) 2275400900003
MONITOR (13-AL-27(N,A)11-NA-24,,SIG) IRDF-90 c-s. 2275400900004
MONIT-REF (,N.P.Kochelov+,R,IAEA-NDS-141,1990) International 2275400900005
Dosimetry file (IRDF-90) . 2275400900006
ERR-ANALYS (DATA-ERR) No information about source of uncertainty 2275400900007
STATUS (CURVE) Fig.1 of reference JAERI-M-93-046,257,1993. 2275400900008
(DEP,22754004) 2275400900009
(DEP,22754005) 2275400900010
Data derived from References 2275400900011
M.Sakuma+,R,JAERI-M-92-027,278,1992 and 2275400900012
S.Iwasaki+,J,PNE,26,231,1991 2275400900013
data of ratio to Al-27(n,alpha) cross section( given 2275400900014
by IRDF-90 data). 2275400900015
HISTORY (20081009T) Data are moved from Entry 22751 Subent 002.2275400900016
(20200117A) SD: SF9=DERIV deleted from REACTION code. 2275400900017
Prev. HISTORY code corrected; ERR-ANALYS updated. 2275400900018
COMMENT deleted (info moved to STATUS). 2275400900019
ENDBIB 17 0 2275400900020
COMMON 2 3 2275400900021
EN-ERR-DIG ERR-DIG 2275400900022
MEV B 2275400900023
0.34251E-010.50352E-02 2275400900024
ENDCOMMON 3 0 2275400900025
DATA 3 9 2275400900026
EN DATA DATA-ERR 2275400900027
MEV B B 2275400900028
13.037 2.0824 0.51737E-01 2275400900029
15.064 2.0802 0.32893E-01 2275400900030
17.514 1.8292 0.42330E-01 2275400900031
17.516 1.7728 0.42330E-01 2275400900032
18.601 1.4637 0.32953E-01 2275400900033
19.192 1.3045 2275400900034
19.340 1.2623 2275400900035
19.537 1.2202 2275400900036
19.584 1.2626 2275400900037
ENDDATA 11 0 2275400900038
ENDSUBENT 37 0 2275400999999
ENDENTRY 9 0 2275499999999