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