ENTRY 21958 20170823 22642195800000001 SUBENT 21958001 20170823 22642195800100001 BIB 13 62 2195800100002 INSTITUTE (2GERJUL) 2195800100003 REFERENCE (J,NSE,88,(2),143,1984) 2195800100004 AUTHOR (S.M.Qaim,R.Woelfle,M.M.Rahman,H.Ollig) 2195800100005 TITLE Measurement of (n,p) and (n,alpha) reaction cross 2195800100006 sections on some isotopes of nickel in the energy 2195800100007 region of 5 to 10 MeV using a deuterium gas target 2195800100008 at a compact cyclotron 2195800100009 FACILITY (CYCLO,2GERJUL) Compact cyclotron CV28 2195800100010 INC-SOURCE (D-D) Small-cell 3.7 cm long,4 cm diam.,filled with 2195800100011 D2 at 1.8 bar. Cyclotron vacuum-cell separated by a 2195800100012 7 micro-m thick Havar foil. D-energy 3.0-7.0 MeV. 2195800100013 Beam-spot about 0.3 cm**2. (Full details are given 2195800100014 in Tbl.1 of NSE,88,(2),143,1984) 2195800100015 Beam current about 4 micro-A. 2195800100016 Contribution of background neutrons is seen in making 2195800100017 2 irradiations in an identical geometry: 2195800100018 - one with the target cell filled with D2 gas 2195800100019 -other without any gas 2195800100020 exp. for Al-27(n,alpha) and d-energy=7 MeV one find 3%2195800100021 INC-SPECT (EN-RSL-HW) The spread is due to angle of emission and 2195800100022 deuteron energy loss in gas. 2195800100023 SAMPLE .Cylinder diam.=10cm 2195800100024 .distance from beam stop 2195800100025 -0.5 cm angular range 6.8-45 degr. 2195800100026 -2 cm angular range 5 -14 degr. 2195800100027 METHOD (ACTIV,CHSEP) 2195800100028 PART-DET (DG) 2195800100029 (XR) 2195800100030 DETECTOR (SCIN) Liquid scintillator NE-213 encapsulated by an 2195800100031 aluminum cell (5.0 cm high, 5.0-cm diam), also it was 2195800100032 used for n-spectrum to verify the change of n-flux 2195800100033 ERR-ANALYS (ERR-T) Include both statistical and systematic errors.2195800100034 The minimum overall error was about 12%; in some cases2195800100035 it was much higher due to low count rates (large 2195800100036 statistical errors) and/or due to high errors in 2195800100037 background neutron corrections for E > 6.0 MeV. 2195800100038 Detailed description was taken from NSE 88(1984) 143. 2195800100039 (ERR-1) Uncertainty in sample weight 2195800100040 (ERR-2) Uncertainty in irradiation time 2195800100041 (ERR-3,1.,2.) Error in half-life-dependent effects 2195800100042 (ERR-4) Uncertainty in neutron source characteristics 2195800100043 (ERR-5) Uncertainty in irradiation geometry 2195800100044 (ERR-6,1.,15.) Uncertainty in correction for activity 2195800100045 induced by back-ground neutrons (gas in/out, breakup)2195800100046 (ERR-7) Uncertainty in correction for absorption and 2195800100047 scattering of neutrons in the sample 2195800100048 (ERR-8) Error in excitation function of monitor react. 2195800100049 (ERR-9,2.,20.) Uncertainty in determination of detector2195800100050 counts 2 to 20 (statistics, pileup, coincidence 2195800100051 losses, geometry) 2195800100052 (ERR-10,,2.) Uncertainty in absorption of gamma rays 2195800100053 in the sample 2195800100054 (ERR-11) Uncertainty in detector efficiency 2195800100055 (ERR-12,2.,3.) Uncertainty in chemical yield 2195800100056 (ERR-13,1.,5.) Uncertainty in decay data 2195800100057 HISTORY (19850123C) 2195800100058 (20151214A) SD:Updated to new date formats,lower case. 2195800100059 BIB, ERR-ANALYS update. DATA-ERR -> ERR-T in Subents. 2195800100060 (20170823A) SD: Subents 007,008 were added. Cosmetic 2195800100061 corrections in all Subents. STATUS moved to Subents 2195800100062 002-006. Meaningless zeros were deleted from the data. 2195800100063 EN-ERR -> EN-RSL-HW. 2195800100064 ENDBIB 62 0 2195800100065 COMMON 7 6 2195800100066 ERR-1 ERR-2 ERR-4 ERR-5 ERR-7 ERR-8 2195800100067 ERR-11 2195800100068 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2195800100069 PER-CENT 2195800100070 0.1 0.1 3. 3. 4. 8. 2195800100071 3. 2195800100072 ENDCOMMON 6 0 2195800100073 ENDSUBENT 72 0 2195800199999 SUBENT 21958002 20170823 22642195800200001 BIB 8 21 2195800200002 REACTION (28-NI-58(N,A)26-FE-55,,SIG) 2195800200003 SAMPLE (28-NI-58,NAT=0.68) 7.g of 99.999% pure nickel in form 2195800200004 of 1.x 1.cm cylinder (with iron monitor foils in front2195800200005 and at the back); irrad.-time=6 hr; 0.6 cm from the 2195800200006 back of the beam stop. 2195800200007 MONITOR (26-FE-54(N,P)25-MN-54,,SIG) For n-flux monitoring 2195800200008 used as external standard 2195800200009 (28-NI-58(N,P)27-CO-58,,SIG) for internal standard 2195800200010 MONIT-REF (,B.A.Magurno,R,BNL-NCS-50446,1975) 2195800200011 B.A.Magurno, ed., "Evaluated Nuclear Data File 2195800200012 (ENDF)/B-IV, Dosimetry File," BNL-NCS-50446, 2195800200013 Brookhaven National Laboratory (1975). 2195800200014 DECAY-DATA (26-FE-55,2.7YR,XR) 2195800200015 DETECTOR (SILI) Si(Li) detector for Fe-55 radioactivity 2195800200016 measurement 2195800200017 STATUS (TABLE) Tbl.IV from NSE,88,(2),143,1984 2195800200018 (SPSDD,21958007) From Prof. S.M.Qaim:'The cross section2195800200019 values for the reactions reported in 1984 were 2195800200020 renormalized to the new monitor cross section in 1999. 2195800200021 HISTORY (20151214A) SD: DETECTOR, DECAY-DATA added. 2195800200022 (20170823U) SD: STATUS 'SPSDD' was added. 2195800200023 ENDBIB 21 0 2195800200024 NOCOMMON 0 0 2195800200025 DATA 4 9 2195800200026 EN EN-RSL-HW DATA ERR-T 2195800200027 KEV KEV MB MB 2195800200028 5355. 150. 51.0 7.6 2195800200029 5978. 98. 82.7 12.1 2195800200030 6410. 223. 95.6 13.8 2195800200031 6953. 236. 103.7 15.0 2195800200032 7478. 247. 111.3 16.1 2195800200033 7994. 258. 113.4 16.8 2195800200034 8499. 268. 126.9 19.3 2195800200035 9146. 278. 120.2 21.6 2195800200036 9493. 286. 127.4 27.5 2195800200037 ENDDATA 11 0 2195800200038 ENDSUBENT 37 0 2195800299999 SUBENT 21958003 20170823 22642195800300001 BIB 8 20 2195800300002 REACTION (28-NI-62(N,A)26-FE-59,,SIG) 2195800300003 SAMPLE (28-NI-62,NAT=0.0371) 20.g of nickel, sintered together2195800300004 to a solid mass of cylindrical form with a length of 2195800300005 ~1.2 cm and a diam. of ~1.6 cm (with iron monitor 2195800300006 foils in front and at the back); 2195800300007 irrad.-time=8 hr; 0.5 cm from the back of the beam stop2195800300008 DECAY-DATA (26-FE-59,44.6D,DG,1099.,0.565,DG,1292.,0.432) 2195800300009 MONITOR (26-FE-54(N,P)25-MN-54,,SIG) For n-flux monitoring 2195800300010 used as external standard 2195800300011 (28-NI-58(N,P)27-CO-58,,SIG) for internal standard 2195800300012 MONIT-REF (,B.A.Magurno,R,BNL-NCS-50446,1975) 2195800300013 B.A.Magurno, ed., "Evaluated Nuclear Data File 2195800300014 (ENDF)/B-IV, Dosimetry File," BNL-NCS-50446, 2195800300015 Brookhaven National Laboratory (1975). 2195800300016 DETECTOR (GELI) used for Fe-59 radioactivity measurement 2195800300017 STATUS (TABLE) Tbl.IV from NSE,88,(2),143,1984 2195800300018 (SPSDD,21958008) From Prof. S.M.Qaim:'The cross section2195800300019 values for the reactions reported in 1984 were 2195800300020 renormalized to the new monitor cross section in 1999. 2195800300021 HISTORY (20170823U) SD: STATUS 'SPSDD' was added. 2195800300022 ENDBIB 20 0 2195800300023 NOCOMMON 0 0 2195800300024 DATA 4 6 2195800300025 EN EN-RSL-HW DATA ERR-T 2195800300026 KEV KEV MB MB 2195800300027 6410. 223. 0.40 0.05 2195800300028 6953. 236. 0.90 0.11 2195800300029 7478. 247. 1.56 0.18 2195800300030 7994. 258. 2.54 0.30 2195800300031 8499. 268. 3.26 0.40 2195800300032 9493. 286. 5.14 0.95 2195800300033 ENDDATA 8 0 2195800300034 ENDSUBENT 33 0 2195800399999 SUBENT 21958004 20170823 22642195800400001 BIB 9 19 2195800400002 REACTION (28-NI-64(N,A)26-FE-61,,SIG) 2195800400003 SAMPLE (28-NI-64,NAT=0.0095) 25.g of nickel powder in a 2195800400004 3.5-cm-long, 1.4-cm-diam polyethylene cylinder; 2195800400005 irrad.-time=30.min; 0.5 cm from the back of the 2195800400006 beam stop 2195800400007 ANALYSIS Immediately thereafter, gamma-ray spectroscopic 2195800400008 analysis was started without performing any chemical 2195800400009 separation. 2195800400010 DECAY-DATA (26-FE-61,6.MIN,DG,1205.,0.436) 2195800400011 MONITOR (28-NI-58(N,P)27-CO-58,,SIG) Internal monitor. 2195800400012 MONIT-REF (,B.A.Magurno,R,BNL-NCS-50446,1975) 2195800400013 B.A.Magurno, ed., "Evaluated Nuclear Data File 2195800400014 (ENDF)/B-IV, Dosimetry File," BNL-NCS-50446, 2195800400015 Brookhaven National Laboratory (1975). 2195800400016 COMMENT Due to the large size of the sample, and consequently 2195800400017 bad counting geometry, the neutron flux was determined 2195800400018 using only the internal monitor reaction. 2195800400019 STATUS (TABLE) Tbl.IV from NSE,88,(2),143,1984 2195800400020 HISTORY (20151214U) SD: ANALYSIS, COMMENT was added. 2195800400021 ENDBIB 19 0 2195800400022 NOCOMMON 0 0 2195800400023 DATA 4 6 2195800400024 EN EN-RSL-HW DATA ERR-T 2195800400025 KEV KEV MB MB 2195800400026 7015. 165. 0.20 0.07 2195800400027 7546. 169. 0.24 0.07 2195800400028 8067. 176. 0.55 0.10 2195800400029 8577. 182. 0.63 0.10 2195800400030 9081. 188. 0.64 0.15 2195800400031 9580. 192. 0.93 0.25 2195800400032 ENDDATA 8 0 2195800400033 ENDSUBENT 32 0 2195800499999 SUBENT 21958005 20170823 22642195800500001 BIB 7 14 2195800500002 REACTION (28-NI-61(N,P)27-CO-61,,SIG) 2195800500003 SAMPLE (28-NI-61,ENR=0.9292) 50 mg of an enriched 61Ni sample,2195800500004 sandwiched between two iron foils, for 2 hr at a 2195800500005 distance of 2 cm from the beam stop. 2195800500006 DECAY-DATA (27-CO-61,1.65HR,DG,67.,0.86) 2195800500007 MONITOR (26-FE-56(N,P)25-MN-56,,SIG) For n-flux monitoring 2195800500008 used as external standard 2195800500009 MONIT-REF (,B.A.Magurno,R,BNL-NCS-50446,1975) 2195800500010 B.A.Magurno, ed., "Evaluated Nuclear Data File 2195800500011 (ENDF)/B-IV, Dosimetry File," BNL-NCS-50446, 2195800500012 Brookhaven National Laboratory (1975). 2195800500013 DETECTOR (GE-IN) Intrinsic germanium detector with an active 2195800500014 area of 2. cm2 and having a thin beryllium window. 2195800500015 STATUS (TABLE) Tbl.IV from NSE,88,(2),143,1984 2195800500016 ENDBIB 14 0 2195800500017 NOCOMMON 0 0 2195800500018 DATA 4 9 2195800500019 EN EN-RSL-HW DATA ERR-T 2195800500020 KEV KEV MB MB 2195800500021 5314. 180. 19.7 4.2 2195800500022 5967. 102. 34.5 6.3 2195800500023 6536. 103. 43.8 6.7 2195800500024 7095. 98. 46.8 5.5 2195800500025 7629. 96. 52.2 5.8 2195800500026 8118. 114. 58.0 6.9 2195800500027 8631. 114. 63.5 7.0 2195800500028 9134. 115. 70.6 11.4 2195800500029 9519. 256. 77.4 13.5 2195800500030 ENDDATA 11 0 2195800500031 ENDSUBENT 30 0 2195800599999 SUBENT 21958006 20170823 22642195800600001 BIB 5 8 2195800600002 REACTION (28-NI-62(N,P)27-CO-62-M,,SIG) 2195800600003 SAMPLE (28-NI-62,NAT=0.0371) 25.g of nickel powder in a 2195800600004 3.5-cm-long, 1.4-cm-diam polyethylene cylinder; 2195800600005 irrad.-time=30.min; 0.5 cm from the back of the 2195800600006 beam stop 2195800600007 DECAY-DATA (27-CO-62-M,14.0MIN,DG,1163.,0.685,DG,1173.,0.98) 2195800600008 MONITOR (28-NI-58(N,P)27-CO-58,,SIG) For internal monitor 2195800600009 STATUS (TABLE) Tbl.IV from NSE,88,(2),143,1984 2195800600010 ENDBIB 8 0 2195800600011 NOCOMMON 0 0 2195800600012 DATA 4 5 2195800600013 EN EN-RSL-HW DATA ERR-T 2195800600014 KEV KEV MB MB 2195800600015 7546. 169. 0.09 0.03 2195800600016 8067. 176. 0.16 0.05 2195800600017 8577. 182. 0.62 0.15 2195800600018 9081. 188. 0.85 0.20 2195800600019 9580. 192. 1.40 0.30 2195800600020 ENDDATA 7 0 2195800600021 ENDSUBENT 20 0 2195800699999 SUBENT 21958007 20170823 22642195800700001 BIB 7 10 2195800700002 REACTION (28-NI-58(N,A)26-FE-55,,SIG) 2195800700003 MONITOR (26-FE-54(N,P)25-MN-54,,SIG) 2195800700004 MONIT-REF (,N.P.Kocherov+,R,IAEA-NDS-141,1993) 2195800700005 COMMENT .Data recalculated from those measured in Subent 2195800700006 21958002 using new evaluated data for standard 2195800700007 cross-section 54Fe(n,p)24Mn given in MONIT-REF 2195800700008 STATUS (TABLE) From Table 4 of RCA,84,(1),1,1999 2195800700009 (COREL,21958002) 2195800700010 REL-REF (R,22465001,A.Fessler+,J,RCA,84,(1),1,1999) 2195800700011 HISTORY (20170823T) SD: Removed from 22465.006. 2195800700012 ENDBIB 10 0 2195800700013 NOCOMMON 0 0 2195800700014 DATA 4 9 2195800700015 EN EN-RSL-HW DATA ERR-T 2195800700016 MEV MEV MB MB 2195800700017 5.36 0.15 49.6 6.8 2195800700018 5.98 0.10 78.0 10.9 2195800700019 6.41 0.23 84.4 12.0 2195800700020 6.95 0.23 87.6 12.6 2195800700021 7.48 0.25 92.3 13.2 2195800700022 7.99 0.26 94.3 14.8 2195800700023 8.50 0.27 107.6 15.7 2195800700024 9.15 0.28 91.3 15.9 2195800700025 9.49 0.29 101.1 16.0 2195800700026 ENDDATA 11 0 2195800700027 ENDSUBENT 26 0 2195800799999 SUBENT 21958008 20170823 22642195800800001 BIB 7 10 2195800800002 REACTION (28-NI-62(N,A)26-FE-59,,SIG) 2195800800003 MONITOR (26-FE-54(N,P)25-MN-54,,SIG) 2195800800004 MONIT-REF (,N.P.Kocherov+,R,IAEA-NDS-141,1993) 2195800800005 COMMENT .Data recalculated from those measured in Subent 2195800800006 21958003 using new evaluated data for standard 2195800800007 cross-section 54Fe(n,p)24Mn given in MONIT-REF 2195800800008 STATUS (TABLE) From Table 4 of RCA,84,(1),1,1999 2195800800009 (COREL,21958003) 2195800800010 REL-REF (R,22465001,A.Fessler+,J,RCA,84,(1),1,1999) 2195800800011 HISTORY (20170823T) SD: Removed from 22465.007. 2195800800012 ENDBIB 10 0 2195800800013 NOCOMMON 0 0 2195800800014 DATA 4 6 2195800800015 EN EN-RSL-HW DATA ERR-T 2195800800016 MEV MEV MB MB 2195800800017 6.41 0.23 0.36 0.05 2195800800018 6.95 0.23 0.76 0.10 2195800800019 7.48 0.25 1.30 0.16 2195800800020 7.99 0.26 2.05 0.25 2195800800021 8.50 0.27 2.78 0.33 2195800800022 9.49 0.29 4.10 0.80 2195800800023 ENDDATA 8 0 2195800800024 ENDSUBENT 23 0 2195800899999 ENDENTRY 8 0 2195899999999