ENTRY 22754 20200117 228522754 0 1 SUBENT 22754001 20200117 228522754 1 1 BIB 9 29 22754 1 2 TITLE Measurement of (n,2n) cross-sections for several 22754 1 3 dosimetry reactions between 12 and 20 MeV. 22754 1 4 AUTHOR (M.Sakuma, S.Iwasaki, H.Shimada, N.Odano, K.Suda, 22754 1 5 J.R.Dumais, K.Sugiyama) 22754 1 6 INSTITUTE (2JPNTOH) 22754 1 7 REFERENCE (R,JAERI-M-92-027,278,1992) Main Ref. 197Au(n,2n) data 22754 1 8 (J,PNE,26,231,1991) First author S.Iwasaki. 22754 1 9 Graphs of cross section ratios Nb/Al, Au/Al. 22754 1 10 (R,JAERI-M-93-046,257,1993) First author S.Iwasaki. 22754 1 11 Other data of this report are in Entry 22751. 22754 1 12 FACILITY (DYNAM,2JPNTOH) Tohoku University 4.5-MV Dynamitron 22754 1 13 Accelerator of Fast Neutron Laboratory. 22754 1 14 INC-SOURCE (D-T) T(d,n)He-4 reaction. Incident deuteron beam 22754 1 15 energy about 3 MeV. Air-cooled Ti-T target, Ti-layer 22754 1 16 of 11 mm diameter, 10.1 mg/cm**2 thickness, on copper 22754 1 17 backing of 0.5mm thickness, mounted in thin copper 22754 1 18 chamber (circular tube of 70 mm long, 14mm outer 22754 1 19 diameter, 1 mm thick wall, end plate of 0.5 mm thick).22754 1 20 Beam profile was measured to be two-dimensional 22754 1 21 Gaussian distribution of 4-mm FWHM. 22754 1 22 INC-SPECT Neutron intensity was monitored with NE-213 detector. 22754 1 23 DETECTOR (SCIN) NE-213 liquid scintillation detector,2" diameter22754 1 24 2" thickness. For neutron intensity monitoring. 22754 1 25 (HPGE) 80 cc high-purity germanium detector calibrated22754 1 26 with a set of standard gamma-ray source. For gamma-ray22754 1 27 of sample foils. 22754 1 28 HISTORY (20081006C) M.M. 22754 1 29 (20200117A) SD: DECAY-DATA corrected in Subents 002-00522754 1 30 ERR-ANALYS updated in Subents 002-009. 22754 1 31 ENDBIB 29 0 22754 1 32 NOCOMMON 0 0 22754 1 33 ENDSUBENT 32 0 22754 199999 SUBENT 22754002 20200117 228522754 2 1 BIB 9 53 22754 2 2 REACTION ((41-NB-93(N,2N)41-NB-92-M,,SIG)/ 22754 2 3 (13-AL-27(N,A)11-NA-24,,SIG)) 22754 2 4 SAMPLE Rectangular foils 10mmx10mmx0.5mm(thickness) . 22754 2 5 Sample set was composed of two Al foils sandwiched 22754 2 6 between Nb foils with Au foil opposite the target. 22754 2 7 METHOD (ACTIV) 1-st series of irradiations for c-s ratios: 22754 2 8 Neutron energy 19.9-12.8 MeV, angle for irradiation22754 2 9 0-140 deg., d+ energy 3.26MeV, beam current 10 microA,22754 2 10 irradiation time 50 hours. 22754 2 11 (TOF) Angular spectra of source neutrons were 22754 2 12 measured by TOF technique at angles from 0 to 150 deg 22754 2 13 at intervals of 10 or 5 deg. 22754 2 14 (GSPEC) Gamma-rays from samples were measured. 22754 2 15 DECAY-DATA (41-NB-92-M,10.15D,DG,934.53,0.990) 22754 2 16 Measured gamma-ray 934.53+-0.05 keV with emission 22754 2 17 probability 0.990+-0.002 . HL error 0.02 d. 22754 2 18 (11-NA-24,14.959HR,B-,,,DG,1368.633,0.99994) 22754 2 19 Measured gamma-ray 1368.633+-0.006 with emission 22754 2 20 probability 0.99994+-0.002. HL error 0.004 hr. 22754 2 21 Decay data from J.H.Baard,W.L.Ziip,H.J.Nolthenius,198922754 2 22 Nuclear Data Guide for Reactor Neutron Metrology, 22754 2 23 Kluwer Academic Publ., Dordrecht, Netherlands. 22754 2 24 ANALYSIS Cross sections ratio was derived from ratio of 22754 2 25 reaction-rates. 22754 2 26 CORRECTION - Fluctuation of neutron flux during irradiation. 22754 2 27 - Difference of neutron flux between foils. 22754 2 28 - Nonmonochromaticity of irradiating neutrons. 22754 2 29 - Contribution of parasitic D(d,n)He-3 neutrons to 22754 2 30 reaction rate of Al-27(n,alpha)Na-24 . 22754 2 31 - Finite dimensions of sample foils. 22754 2 32 - Self-absorption of gamma-rays in the foils. 22754 2 33 - Sum-coincidence effect of cascade gamma-rays for Al 22754 2 34 samples was evaluated experimentally to be less 1%, 22754 2 35 was included in uncertainties of efficiencies.. 22754 2 36 ERR-ANALYS (ERR-T) Total uncertainty 2.5 - 7.0 % is given as 22754 2 37 error bar on Fig.2 22754 2 38 (ERR-S,0.7,2.0) Uncertainty in counting statistics of 22754 2 39 gamma-ray - 0.7-2.0 %. 22754 2 40 (ERR-1,2.1,4.5) Uncertainty in detection efficiency 22754 2 41 of gamma-ray - 2.1-4.5 %. 22754 2 42 (ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 22754 2 43 (ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 22754 2 44 (ERR-4,0.1,0.2) Uncertainty in decay half-life of 22754 2 45 nuclei - 0.1-0.2%. 22754 2 46 (ERR-5,0.002,2.6) Uncertainty in emission probability 22754 2 47 of gamma-ray - 0.002-2.6% 22754 2 48 (2.6% -for gamma-rays from Au-196). 22754 2 49 (ERR-6,,0.1) Uncertainty due corrections < 0.1% . 22754 2 50 STATUS (CURVE) Fig.2 of JAERI-M-92-027,278(triangl.,1-st exp.)22754 2 51 Fig.3 of Progr.Nucl.En.,26(1991)231 22754 2 52 (COREL,22754003) Data from Run 2 22754 2 53 HISTORY (20200117A) SD: DECAY-DATA corrected, STATUS, 22754 2 54 ERR-ANALYS updated. DATA-ERR -> ERR-T. 22754 2 55 ENDBIB 53 0 22754 2 56 COMMON 2 3 22754 2 57 EN-ERR-DIG ERR-DIG 22754 2 58 MEV NO-DIM 22754 2 59 0.16495E-010.16805E-01 22754 2 60 ENDCOMMON 3 0 22754 2 61 DATA 3 10 22754 2 62 EN DATA ERR-T 22754 2 63 MEV NO-DIM NO-DIM 22754 2 64 12.788 3.6878 0.15523 22754 2 65 13.698 3.9773 0.20154 22754 2 66 14.844 4.0598 0.18604 22754 2 67 14.853 4.1372 0.18644 22754 2 68 16.066 4.9625 0.24825 22754 2 69 17.430 5.9704 0.31026 22754 2 70 17.438 5.8617 0.30986 22754 2 71 18.669 6.6556 0.38798 22754 2 72 19.583 7.5498 0.38778 22754 2 73 19.911 7.9145 0.38738 22754 2 74 ENDDATA 12 0 22754 2 75 ENDSUBENT 74 0 22754 299999 SUBENT 22754003 20200117 228522754 3 1 BIB 9 54 22754 3 2 REACTION ((41-NB-93(N,2N)41-NB-92-M,,SIG)/ 22754 3 3 (13-AL-27(N,A)11-NA-24,,SIG)) 22754 3 4 SAMPLE Rectangular foils 20mm x 5mm x 0.5mm(thickness) in 22754 3 5 second irradiation, except Au foils of 0.2mm thick. 22754 3 6 Sample set was composed of two Al foils sandwiched 22754 3 7 between Nb foils with Au foil opposite the target. 22754 3 8 METHOD (ACTIV) 2-nd series of irradiations for c-s ratios: 22754 3 9 Neutron energy 19.4-12.7 MeV, angle for irradiation22754 3 10 0-140 deg., d+ energy 2.85MeV, beam current 10 microA,22754 3 11 irradiation time 36 hours. 22754 3 12 (TOF) Angular spectra of source neutrons were 22754 3 13 measured by TOF technique at angles from 0 to 150 deg 22754 3 14 at intervals of 10 or 5 deg. 22754 3 15 (GSPEC) Gamma-rays from samples were measured. 22754 3 16 DECAY-DATA (41-NB-92-M,10.15D,DG,934.53,0.990) 22754 3 17 Measured gamma-ray 934.53+-0.05 keV with emission 22754 3 18 probability 0.990+-0.002 . HL error 0.02 d. 22754 3 19 (11-NA-24,14.959HR,B-,,,DG,1368.633,0.99994) 22754 3 20 Measured gamma-ray 1368.633+-0.006 with emission 22754 3 21 probability 0.99994+-0.002. HL error 0.004 hr. 22754 3 22 Decay data from J.H.Baard,W.L.Ziip,H.J.Nolthenius,198922754 3 23 Nuclear Data Guide for Reactor Neutron Metrology, 22754 3 24 Kluwer Academic Publ., Dordrecht, Netherlands. 22754 3 25 ANALYSIS Cross sections ratio was derived from ratio of 22754 3 26 reaction-rates. 22754 3 27 CORRECTION - Fluctuation of neutron flux during irradiation. 22754 3 28 - Difference of neutron flux between foils. 22754 3 29 - Nonmonochromaticity of irradiating neutrons. 22754 3 30 - Contribution of parasitic D(d,n)He-3 neutrons to 22754 3 31 reaction rate of Al-27(n,alpha)Na-24 . 22754 3 32 - Finite dimensions of sample foils. 22754 3 33 - Self-absorption of gamma-rays in the foils. 22754 3 34 - Sum-coincidence effect of cascade gamma-rays for Al 22754 3 35 samples was evaluated experimentally to be less 1%, 22754 3 36 was included in uncertainties of efficiencies.. 22754 3 37 ERR-ANALYS (ERR-T) Total uncertainty 2.5 - 7.0 % is given as 22754 3 38 error bar on Fig.2 22754 3 39 (ERR-S,0.7,2.0) Uncertainty in counting statistics of 22754 3 40 gamma-ray - 0.7-2.0 %. 22754 3 41 (ERR-1,2.1,4.5) Uncertainty in detection efficiency 22754 3 42 of gamma-ray - 2.1-4.5 %. 22754 3 43 (ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 22754 3 44 (ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 22754 3 45 (ERR-4,0.1,0.2) Uncertainty in decay half-life of 22754 3 46 nuclei - 0.1-0.2%. 22754 3 47 (ERR-5,0.002,2.6) Uncertainty in emission probability 22754 3 48 of gamma-ray - 0.002-2.6% 22754 3 49 (2.6% -for gamma-rays from Au-196). 22754 3 50 (ERR-6,,0.1) Uncertainty due corrections < 0.1% . 22754 3 51 STATUS (CURVE) Fig.2 of JAERI-M-92-027,278(circles, 2-nd exp.)22754 3 52 Fig.3 of Progr.Nucl.En.,26(1991)231 22754 3 53 (COREL,22754002) Data from Run 1 22754 3 54 HISTORY (20200117A) SD: DECAY-DATA corrected, STATUS, 22754 3 55 ERR-ANALYS updated. DATA-ERR -> ERR-T. 22754 3 56 ENDBIB 54 0 22754 3 57 COMMON 2 3 22754 3 58 EN-ERR-DIG ERR-DIG 22754 3 59 MEV NO-DIM 22754 3 60 0.16495E-010.16805E-01 22754 3 61 ENDCOMMON 3 0 22754 3 62 DATA 3 17 22754 3 63 EN DATA ERR-T 22754 3 64 MEV NO-DIM NO-DIM 22754 3 65 12.832 3.6558 0.77316E-01 22754 3 66 13.017 3.7291 0.62212E-01 22754 3 67 13.660 3.6990 0.77516E-01 22754 3 68 13.897 3.5231 0.77516E-01 22754 3 69 14.720 4.0006 0.62411E-01 22754 3 70 15.012 4.1646 0.77516E-01 22754 3 71 15.974 4.3909 0.77515E-01 22754 3 72 16.285 4.8180 0.62012E-01 22754 3 73 17.198 5.4795 0.10852 22754 3 74 17.487 5.3334 0.10852 22754 3 75 17.490 5.7365 0.93218E-01 22754 3 76 18.326 6.8495 0.15503 22754 3 77 18.574 6.9059 0.15523 22754 3 78 19.166 7.2646 0.15523 22754 3 79 19.306 7.0754 0.18604 22754 3 80 19.511 7.4118 0.20154 22754 3 81 19.512 7.4893 0.18584 22754 3 82 ENDDATA 19 0 22754 3 83 ENDSUBENT 82 0 22754 399999 SUBENT 22754004 20200117 228522754 4 1 BIB 9 53 22754 4 2 REACTION ((79-AU-197(N,2N)79-AU-196,,SIG)/ 22754 4 3 (13-AL-27(N,A)11-NA-24,,SIG)) 22754 4 4 SAMPLE Rectangular foils 10mmx10mmx0.5mm(thickness) . 22754 4 5 Sample set was composed of two Al foils sandwiched 22754 4 6 between Nb foils with Au foil opposite the target. 22754 4 7 METHOD (ACTIV) 1-st series of irradiations for c-s ratios: 22754 4 8 Neutron energy 19.9-12.8 MeV, angle for irradiation22754 4 9 0-140 deg., d+ energy 3.26MeV, beam current 10 microA,22754 4 10 irradiation time 50 hours. 22754 4 11 (TOF) Angular spectra of source neutrons were 22754 4 12 measured by TOF technique at angles from 0 to 150 deg 22754 4 13 at intervals of 10 or 5 deg. 22754 4 14 (GSPEC) Gamma-rays from samples were measured. 22754 4 15 DECAY-DATA (79-AU-196-G,6.183D,DG,355.73,0.869) 22754 4 16 Measured gamma-ray 355.73+-0.05 keV with emission 22754 4 17 probability 0.869+-0.010 . HL error 0.010 d. 22754 4 18 (11-NA-24,14.959HR,B-,,,DG,1368.633,0.99994) 22754 4 19 Measured gamma-ray 1368.633+-0.006 with emission 22754 4 20 probability 0.99994+-0.002. HL error 0.004 hr. 22754 4 21 Decay data from J.H.Baard,W.L.Ziip,H.J.Nolthenius,198922754 4 22 Nuclear Data Guide for Reactor Neutron Metrology, 22754 4 23 Kluwer Academic Publ., Dordrecht, Netherlands. 22754 4 24 ANALYSIS Cross sections ratio was derived from ratio of 22754 4 25 reaction-rates. 22754 4 26 CORRECTION - Fluctuation of neutron flux during irradiation. 22754 4 27 - Difference of neutron flux between foils. 22754 4 28 - Nonmonochromaticity of irradiating neutrons. 22754 4 29 - Contribution of parasitic D(d,n)He-3 neutrons to 22754 4 30 reaction rate of Al-27(n,alpha)Na-24 . 22754 4 31 - Finite dimensions of sample foils. 22754 4 32 - Self-absorption of gamma-rays in the foils. 22754 4 33 - Sum-coincidence effect of cascade gamma-rays for Al 22754 4 34 samples was evaluated experimentally to be less 1%, 22754 4 35 was included in uncertainties of efficiencies.. 22754 4 36 ERR-ANALYS (ERR-T) Total uncertainty 2.5 - 7.0 % is given as 22754 4 37 error bar on Fig.3 22754 4 38 (ERR-S,0.7,2.0) Uncertainty in counting statistics of 22754 4 39 gamma-ray - 0.7-2.0 %. 22754 4 40 (ERR-1,2.1,4.5) Uncertainty in detection efficiency 22754 4 41 of gamma-ray - 2.1-4.5 %. 22754 4 42 (ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 22754 4 43 (ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 22754 4 44 (ERR-4,0.1,0.2) Uncertainty in decay half-life of 22754 4 45 nuclei - 0.1-0.2%. 22754 4 46 (ERR-5,0.002,2.6) Uncertainty in emission probability 22754 4 47 of gamma-ray - 0.002-2.6% 22754 4 48 (2.6% -for gamma-rays from Au-196). 22754 4 49 (ERR-6,,0.1) Uncertainty due corrections < 0.1% . 22754 4 50 STATUS (CURVE) Fig.3 of JAERI-M-92-027,278(triangl.,1-st exp),22754 4 51 Fig.4 of Progr.Nucl.En.,26(1991)231 22754 4 52 (COREL,22754005) Data from Run 2 22754 4 53 HISTORY (20200117A) SD: DECAY-DATA corrected, STATUS, 22754 4 54 ERR-ANALYS updated. DATA-ERR -> ERR-T. 22754 4 55 ENDBIB 53 0 22754 4 56 COMMON 2 3 22754 4 57 EN-ERR-DIG ERR-DIG 22754 4 58 MEV NO-DIM 22754 4 59 0.15647E-010.57175E-01 22754 4 60 ENDCOMMON 3 0 22754 4 61 DATA 3 12 22754 4 62 EN DATA ERR-T 22754 4 63 MEV NO-DIM NO-DIM 22754 4 64 12.778 16.794 0.68125 22754 4 65 12.779 17.213 0.94327 22754 4 66 13.682 18.498 0.99491 22754 4 67 13.699 18.130 0.94174 22754 4 68 14.836 17.979 0.78605 22754 4 69 16.056 23.168 1.6777 22754 4 70 17.421 25.724 1.3625 22754 4 71 17.422 26.457 1.4681 22754 4 72 18.646 25.513 1.7825 22754 4 73 19.567 27.321 1.5205 22754 4 74 19.902 27.187 1.4149 22754 4 75 19.903 27.711 1.5721 22754 4 76 ENDDATA 14 0 22754 4 77 ENDSUBENT 76 0 22754 499999 SUBENT 22754005 20200117 228522754 5 1 BIB 9 54 22754 5 2 REACTION ((79-AU-197(N,2N)79-AU-196,,SIG)/ 22754 5 3 (13-AL-27(N,A)11-NA-24,,SIG)) 22754 5 4 SAMPLE Rectangular foils 20mmx5mmx0.5mm(thickness) in 22754 5 5 second irradiation, except Au foils of 0.2mm thick. 22754 5 6 Sample set was composed of two Al foils sandwiched 22754 5 7 between Nb foils with Au foil opposite the target. 22754 5 8 METHOD (ACTIV) 2-nd series of irradiations for c-s ratios: 22754 5 9 Neutron energy 19.4-12.7 MeV, angle for irradiation22754 5 10 0-140 deg., d+ energy 2.85MeV, beam current 10 microA,22754 5 11 irradiation time 36 hours. 22754 5 12 (TOF) Angular spectra of source neutrons were 22754 5 13 measured by TOF technique at angles from 0 to 150 deg 22754 5 14 at intervals of 10 or 5 deg. 22754 5 15 (GSPEC) Gamma-rays from samples were measured. 22754 5 16 DECAY-DATA (79-AU-196-G,6.183D,DG,355.73,0.869) 22754 5 17 Measured gamma-ray 355.73+-0.05 keV with emission 22754 5 18 probability 0.869+-0.010 . HL error 0.010 d. 22754 5 19 (11-NA-24,14.959HR,B-,,,DG,1368.633,0.99994) 22754 5 20 Measured gamma-ray 1368.633+-0.006 with emission 22754 5 21 probability 0.99994+-0.002. HL error 0.004 hr. 22754 5 22 Decay data from J.H.Baard,W.L.Ziip,H.J.Nolthenius,198922754 5 23 Nuclear Data Guide for Reactor Neutron Metrology, 22754 5 24 Kluwer Academic Publ., Dordrecht, Netherlands. 22754 5 25 ANALYSIS Cross sections ratio was derived from ratio of 22754 5 26 reaction-rates. 22754 5 27 CORRECTION - Fluctuation of neutron flux during irradiation. 22754 5 28 - Difference of neutron flux between foils. 22754 5 29 - Nonmonochromaticity of irradiating neutrons. 22754 5 30 - Contribution of parasitic D(d,n)He-3 neutrons to 22754 5 31 reaction rate of Al-27(n,alpha)Na-24 . 22754 5 32 - Finite dimensions of sample foils. 22754 5 33 - Self-absorption of gamma-rays in the foils. 22754 5 34 - Sum-coincidence effect of cascade gamma-rays for Al 22754 5 35 samples was evaluated experimentally to be less 1%, 22754 5 36 was included in uncertainties of efficiencies.. 22754 5 37 ERR-ANALYS (ERR-T) Total uncertainty 2.5 - 7.0 % is given as 22754 5 38 error bar on Fig.3 22754 5 39 (ERR-S,0.7,2.0) Uncertainty in counting statistics of 22754 5 40 gamma-ray - 0.7-2.0 %. 22754 5 41 (ERR-1,2.1,4.5) Uncertainty in detection efficiency 22754 5 42 of gamma-ray - 2.1-4.5 %. 22754 5 43 (ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 22754 5 44 (ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 22754 5 45 (ERR-4,0.1,0.2) Uncertainty in decay half-life of 22754 5 46 nuclei - 0.1-0.2%. 22754 5 47 (ERR-5,0.002,2.6) Uncertainty in emission probability 22754 5 48 of gamma-ray - 0.002-2.6% 22754 5 49 (2.6% -for gamma-rays from Au-196). 22754 5 50 (ERR-6,,0.1) Uncertainty due corrections < 0.1% . 22754 5 51 STATUS (CURVE) Fig.3 of JAERI-M-92-027,278(circles, 2-nd exp.)22754 5 52 Fig.4 of Progr.Nucl.En.,26(1991)231 22754 5 53 (COREL,22754004) Data from Run 1 22754 5 54 HISTORY (20200117A) SD: DECAY-DATA corrected, STATUS, 22754 5 55 ERR-ANALYS updated. DATA-ERR -> ERR-T. 22754 5 56 ENDBIB 54 0 22754 5 57 COMMON 2 3 22754 5 58 EN-ERR-DIG ERR-DIG 22754 5 59 MEV NO-DIM 22754 5 60 0.15647E-010.57175E-01 22754 5 61 ENDCOMMON 3 0 22754 5 62 DATA 3 10 22754 5 63 EN DATA ERR-T 22754 5 64 MEV NO-DIM NO-DIM 22754 5 65 13.009 17.403 0.47163 22754 5 66 15.005 18.856 0.52403 22754 5 67 17.467 22.994 0.89086 22754 5 68 17.471 24.828 0.62960 22754 5 69 18.316 27.481 0.83846 22754 5 70 18.550 26.046 0.83922 22754 5 71 19.149 25.732 0.78757 22754 5 72 19.280 25.144 0.78605 22754 5 73 19.485 25.913 0.89162 22754 5 74 19.496 27.065 0.83846 22754 5 75 ENDDATA 12 0 22754 5 76 ENDSUBENT 75 0 22754 599999 SUBENT 22754006 20200117 228522754 6 1 BIB 8 30 22754 6 2 REACTION (11-NA-23(N,2N)11-NA-22,,SIG) 22754 6 3 MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) 22754 6 4 MONIT-REF (,,3,IRDF-90,,1990) 22754 6 5 SAMPLE Sodium - in form of NaCl compound, packed in aluminum 22754 6 6 boxes of 25 x 15 x 10 mm size and 1.5mm wall thickness.22754 6 7 25mm x 15mmx 0.5mm for niobium. 22754 6 8 All samples between Nb foils to determine neutron 22754 6 9 flux in the sample. 22754 6 10 METHOD (ACTIV) Irradiation for (n,2n) cross sections : 22754 6 11 Neutron energy 19.4-15.9 MeV, angle for irradiation 22754 6 12 0- 80 deg., d+ energy 2.83MeV, beam current 10 microA,22754 6 13 irradiation time 84 hours. 22754 6 14 ERR-ANALYS (ERR-T) Total uncertainty 3.5 - 5.5% is given as 22754 6 15 error bar on Fig.5 22754 6 16 (ERR-S,0.5,2.0) Uncertainty in counting statistics of 22754 6 17 gamma-ray - 0.5-2.0 %. 22754 6 18 (ERR-1,2.5,4.0) Uncertainty in detection efficiency 22754 6 19 of gamma-ray - 2.5-4.0 %. 22754 6 20 (ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 22754 6 21 (ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 22754 6 22 (ERR-4,0.03,0.6) Uncertainty in decay half-life of 22754 6 23 nuclei - 0.03-0.6%. 22754 6 24 (ERR-5,0.02,0.5) Uncertainty in emission probability 22754 6 25 of gamma-ray - 0.02-0.5% 22754 6 26 (2.6% -for gamma-rays from Au-196). 22754 6 27 (MONIT-ERR,2.2,3.0) Uncertainty of reference cross 22754 6 28 section data - 2.2 - 3.0% . 22754 6 29 STATUS (CURVE) Fig.5 of JAERI-M-92-027,278 22754 6 30 HISTORY (20200117A) SD: STATUS ('PRELM' - deleted), 22754 6 31 ERR-ANALYS updated. DATA-ERR -> ERR-T. 22754 6 32 ENDBIB 30 0 22754 6 33 COMMON 2 3 22754 6 34 EN-ERR-DIG ERR-DIG 22754 6 35 MEV PER-CENT 22754 6 36 0.16751E-01 0.37220 22754 6 37 ENDCOMMON 3 0 22754 6 38 DATA 3 5 22754 6 39 EN DATA ERR-T 22754 6 40 MEV MB MB 22754 6 41 15.912 59.498 2.7211 22754 6 42 17.199 84.399 3.3994 22754 6 43 18.355 103.54 3.4013 22754 6 44 19.123 105.42 3.4014 22754 6 45 19.414 110.47 4.4218 22754 6 46 ENDDATA 7 0 22754 6 47 ENDSUBENT 46 0 22754 699999 SUBENT 22754007 20200117 228522754 7 1 BIB 8 30 22754 7 2 REACTION (25-MN-55(N,2N)25-MN-54,,SIG) 22754 7 3 MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) 22754 7 4 MONIT-REF (,,3,IRDF-90,,1990) 22754 7 5 SAMPLE Manganese - metallic Mn powder, packed in aluminum 22754 7 6 rectangular boxes of 25 x 15 x 5 mm size. 22754 7 7 25mm x 15mmx 0.5mm for niobium. 22754 7 8 All samples between Nb foils to determine neutron 22754 7 9 flux in the sample. 22754 7 10 METHOD (ACTIV) Irradiation for (n,2n) cross sections : 22754 7 11 Neutron energy 19.4-15.9 MeV, angle for irradiation 22754 7 12 0- 80 deg., d+ energy 2.83MeV, beam current 10 microA,22754 7 13 irradiation time 84 hours. 22754 7 14 ERR-ANALYS (ERR-T) Total uncertainty 3.5 - 5.5% is given as 22754 7 15 error bar on Fig.6 22754 7 16 (ERR-S,0.5,2.0) Uncertainty in counting statistics of 22754 7 17 gamma-ray - 0.5-2.0 %. 22754 7 18 (ERR-1,2.5,4.0) Uncertainty in detection efficiency 22754 7 19 of gamma-ray - 2.5-4.0 %. 22754 7 20 (ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 22754 7 21 (ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 22754 7 22 (ERR-4,0.03,0.6) Uncertainty in decay half-life of 22754 7 23 nuclei - 0.03-0.6%. 22754 7 24 (ERR-5,0.02,0.5) Uncertainty in emission probability 22754 7 25 of gamma-ray - 0.02-0.5% 22754 7 26 (2.6% -for gamma-rays from Au-196). 22754 7 27 (MONIT-ERR,2.2,3.0) Uncertainty of reference cross 22754 7 28 section data - 2.2 - 3.0% . 22754 7 29 STATUS (CURVE) Fig.6 of JAERI-M-92-027,278 22754 7 30 HISTORY (20200117A) SD: STATUS ('PRELM' - deleted), 22754 7 31 ERR-ANALYS updated. DATA-ERR -> ERR-T. 22754 7 32 ENDBIB 30 0 22754 7 33 COMMON 2 3 22754 7 34 EN-ERR-DIG ERR-DIG 22754 7 35 MEV PER-CENT 22754 7 36 0.21057E-010.35595E-02 22754 7 37 ENDCOMMON 3 0 22754 7 38 DATA 3 3 22754 7 39 EN DATA ERR-T 22754 7 40 MEV B B 22754 7 41 17.226 0.83548 0.16279E-01 22754 7 42 18.372 0.79131 0.25558E-01 22754 7 43 19.147 0.82929 0.27906E-01 22754 7 44 ENDDATA 5 0 22754 7 45 ENDSUBENT 44 0 22754 799999 SUBENT 22754008 20200117 228522754 8 1 BIB 8 29 22754 8 2 REACTION (28-NI-58(N,2N)28-NI-57,,SIG) 22754 8 3 MONITOR (41-NB-93(N,2N)41-NB-92-M,,SIG) 22754 8 4 MONIT-REF (,,3,IRDF-90,,1990) 22754 8 5 SAMPLE Size of high-purity metal foils 25mm x 15mm x 0.2mm 22754 8 6 for nickel and 25mm x 15mmx 0.5mm for niobium. 22754 8 7 All samples between Nb foils to determine neutron 22754 8 8 flux in the sample. 22754 8 9 METHOD (ACTIV) Irradiation for (n,2n) cross sections : 22754 8 10 Neutron energy 19.4-15.9 MeV, angle for irradiation 22754 8 11 0- 80 deg., d+ energy 2.83MeV, beam current 10 microA,22754 8 12 irradiation time 84 hours. 22754 8 13 ERR-ANALYS (ERR-T) Total uncertainty 3.5 - 5.5% is given as 22754 8 14 error bar on Fig.7 22754 8 15 (ERR-S,0.5,2.0) Uncertainty in counting statistics of 22754 8 16 gamma-ray - 0.5-2.0 %. 22754 8 17 (ERR-1,2.5,4.0) Uncertainty in detection efficiency 22754 8 18 of gamma-ray - 2.5-4.0 %. 22754 8 19 (ERR-2,,0.1) Uncertainty in sample mass < 0.1%. 22754 8 20 (ERR-3,,0.1) Uncertainty in sample purity < 0.1 %. 22754 8 21 (ERR-4,0.03,0.6) Uncertainty in decay half-life of 22754 8 22 nuclei - 0.03-0.6%. 22754 8 23 (ERR-5,0.02,0.5) Uncertainty in emission probability 22754 8 24 of gamma-ray - 0.02-0.5% 22754 8 25 (2.6% -for gamma-rays from Au-196). 22754 8 26 (MONIT-ERR,2.2,3.0) Uncertainty of reference cross 22754 8 27 section data - 2.2 - 3.0% . 22754 8 28 STATUS (CURVE) Fig.7 of JAERI-M-92-027,278 22754 8 29 HISTORY (20200117A) SD: STATUS ('PRELM' - deleted), 22754 8 30 ERR-ANALYS updated. DATA-ERR -> ERR-T. 22754 8 31 ENDBIB 29 0 22754 8 32 COMMON 2 3 22754 8 33 EN-ERR-DIG ERR-DIG 22754 8 34 MEV PER-CENT 22754 8 35 0.10126E-01 0.14684 22754 8 36 ENDCOMMON 3 0 22754 8 37 DATA 3 3 22754 8 38 EN DATA ERR-T 22754 8 39 MEV MB MB 22754 8 40 17.203 59.031 1.9971 22754 8 41 18.353 65.177 2.4611 22754 8 42 19.134 67.732 2.4637 22754 8 43 ENDDATA 5 0 22754 8 44 ENDSUBENT 43 0 22754 899999 SUBENT 22754009 20200117 228522754 9 1 BIB 6 17 22754 9 2 REACTION (79-AU-197(N,2N)79-AU-196,,SIG) 22754 9 3 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) IRDF-90 c-s. 22754 9 4 MONIT-REF (,N.P.Kochelov+,R,IAEA-NDS-141,1990) International 22754 9 5 Dosimetry file (IRDF-90) . 22754 9 6 ERR-ANALYS (DATA-ERR) No information about source of uncertainty 22754 9 7 STATUS (CURVE) Fig.1 of reference JAERI-M-93-046,257,1993. 22754 9 8 (DEP,22754004) 22754 9 9 (DEP,22754005) 22754 9 10 Data derived from References 22754 9 11 M.Sakuma+,R,JAERI-M-92-027,278,1992 and 22754 9 12 S.Iwasaki+,J,PNE,26,231,1991 22754 9 13 data of ratio to Al-27(n,alpha) cross section( given 22754 9 14 by IRDF-90 data). 22754 9 15 HISTORY (20081009T) Data are moved from Entry 22751 Subent 002.22754 9 16 (20200117A) SD: SF9=DERIV deleted from REACTION code. 22754 9 17 Prev. HISTORY code corrected; ERR-ANALYS updated. 22754 9 18 COMMENT deleted (info moved to STATUS). 22754 9 19 ENDBIB 17 0 22754 9 20 COMMON 2 3 22754 9 21 EN-ERR-DIG ERR-DIG 22754 9 22 MEV B 22754 9 23 0.34251E-010.50352E-02 22754 9 24 ENDCOMMON 3 0 22754 9 25 DATA 3 9 22754 9 26 EN DATA DATA-ERR 22754 9 27 MEV B B 22754 9 28 13.037 2.0824 0.51737E-01 22754 9 29 15.064 2.0802 0.32893E-01 22754 9 30 17.514 1.8292 0.42330E-01 22754 9 31 17.516 1.7728 0.42330E-01 22754 9 32 18.601 1.4637 0.32953E-01 22754 9 33 19.192 1.3045 22754 9 34 19.340 1.2623 22754 9 35 19.537 1.2202 22754 9 36 19.584 1.2626 22754 9 37 ENDDATA 11 0 22754 9 38 ENDSUBENT 37 0 22754 999999 ENDENTRY 9 0 2275499999999