ENTRY 10030 20200811 14721003000000001 SUBENT 10030001 20200811 14721003000100001 BIB 14 41 1003000100002 TITLE Reaction cross sections of 85Rb(n,gamma)86Rb(m), 1003000100003 87Rb(n,gamma)88Rb, and 89Y(n,gamma)90Y(m) between 1003000100004 0.16 MeV and 1.5 MeV 1003000100005 AUTHOR (N.D.Dudey,R.R.Heinrich,A.A.Madson) 1003000100006 REFERENCE (J,JNE,24,181,1970) 1003000100007 #doi:10.1016/0022-3107(70)90034-1 1003000100008 (P,ANL-7450,105,1968) Preliminary results. 1003000100009 (P,ANL-7575,170,1969) Subsequent preprint. 1003000100010 REL-REF (M,10026001,N.D.Dudey+,J,JNE,23,443,1969) Irradiation 1003000100011 conditions and flux monitoring techniques. 1003000100012 INSTITUTE (1USAANL) 1003000100013 FACILITY (VDG,1USAANL) 4-MeV Van de Graaff. 1003000100014 INC-SOURCE (P-LI7) Neutrons were produced by the 7Li(p,n)7Be 1003000100015 reaction. 1003000100016 INC-SPECT Energy resolution given is 1/2 full energy spread. 1003000100017 METHOD (ACTIV) The targets were irradiated, disintegration 1003000100018 rate was determined by counting gamma-rays. The 1003000100019 neutron intensity was monitored both by a 235U 1003000100020 fission counter and by gold foils sandwiching the 1003000100021 targets. 1003000100022 MONITOR (92-U-235(N,F),,SIG) From BNL-325, Suppl.2 (1965) 1003000100023 (79-AU-197(N,G)79-AU-198,,SIG) Secondary standard. 1003000100024 The neutron intensity was monitored both by a 235U 1003000100025 fission counter and by gold foils sandwiching the 1003000100026 targets. 1003000100027 MONIT-REF (,J.R.Stehn+,R,BNL-325,(S2),1965) 1003000100028 CORRECTION Corrected for angular distribution of neutrons, 1003000100029 second neutron group. Not corrected for neutron 1003000100030 scattering or self-absorption (estimated less than 1003000100031 2%). corrected gamma decay data for decay during 1003000100032 counting time. 1003000100033 STATUS (APRVD) Approved by author. 1003000100034 HISTORY (19691219C) 1003000100035 (19800723A) converted to reaction formalism 1003000100036 (19990719A) converted to new date formats, lower case. 1003000100037 (20120325A) SD: Page added to report in REFERENCE; 1003000100038 ERR-ANALYS was updated in all Subents according to 1003000100039 new EXFOR rules. Cosmetic changes in all subents. 1003000100040 (20171114U) OS. Minor corr. in sub.1 1003000100041 (20200811A) BP: Updated references, added doi, 1003000100042 REL-REF, decay data. 1003000100043 ENDBIB 41 0 1003000100044 NOCOMMON 0 0 1003000100045 ENDSUBENT 44 0 1003000199999 SUBENT 10030002 20200811 14721003000200001 BIB 6 16 1003000200002 REACTION (37-RB-85(N,G)37-RB-86-M,,SIG) 1003000200003 SAMPLE RbNO(3). disc-shaped pellets, diam. 1.00 cm, 1003000200004 Thicknesses from 0.20 to 0.25 cm, weights from 0.35 1003000200005 to 0.55 grams. 1003000200006 DETECTOR (GELI,NAICR) Two series. 20-cc Ge(Li) detector - 25% 1003000200007 geometry. 2x1 in. NaI(Tl) detector - 45% geometry. 1003000200008 Efficiencies determined with absolutely calibrated 1003000200009 standard solutions. 1003000200010 DECAY-DATA (37-RB-86-M,1.04MIN,DG,560.) 1003000200011 ERR-ANALYS (DATA-ERR) Standard deviations in absolute cross 1003000200012 section values, and include uncertainties in: 1003000200013 (ERR-1,5.,6.) detection efficiency (5-6%), 1003000200014 (ERR-2,5.,8.) flux monitor (5-8%), 1003000200015 (ERR-3,2.,6.) decay curve fitting (2-6%), 1003000200016 (ERR-4,1.,4.) neutron energy (1-4%). 1003000200017 STATUS (TABLE) Table 1 of J.Nucl.Energ.24(1970)181. 1003000200018 ENDBIB 16 0 1003000200019 NOCOMMON 0 0 1003000200020 DATA 4 29 1003000200021 EN EN-RSL DATA DATA-ERR 1003000200022 KEV KEV MB MB 1003000200023 156. 49.2 17.3 1.69 1003000200024 174. 65.0 16.1 1.72 1003000200025 231. 48.8 15.8 1.82 1003000200026 284. 65.0 13.4 1.30 1003000200027 290. 31.0 13.8 1.26 1003000200028 323. 50.0 13.5 1.38 1003000200029 413. 51.7 13.4 1.22 1003000200030 425. 44.8 13.3 1.56 1003000200031 456. 57.8 13.5 1.47 1003000200032 503. 59.3 13.5 1.28 1003000200033 546. 52.6 11.3 0.95 1003000200034 611. 53.5 10.7 1.07 1003000200035 649. 63.7 10.1 1.12 1003000200036 714. 62.7 9.9 1.03 1003000200037 776. 54.3 9.56 0.92 1003000200038 827. 65.4 8.19 0.84 1003000200039 889. 56.3 8.72 0.77 1003000200040 904. 56.4 7.68 0.71 1003000200041 922. 81.9 8.46 0.80 1003000200042 980. 69.0 7.45 0.91 1003000200043 1064. 86.1 6.63 0.62 1003000200044 1070. 81.3 7.20 0.66 1003000200045 1111. 72.2 6.74 0.90 1003000200046 1141. 88.4 7.15 0.68 1003000200047 1201. 80.3 6.58 0.61 1003000200048 1220. 90.8 6.78 0.70 1003000200049 1385. 86.1 6.69 0.65 1003000200050 1393. 89.6 6.41 0.59 1003000200051 1484. 87.1 5.50 0.52 1003000200052 ENDDATA 31 0 1003000200053 ENDSUBENT 52 0 1003000299999 SUBENT 10030003 20200811 14721003000300001 BIB 7 16 1003000300002 REACTION (37-RB-87(N,G)37-RB-88,,SIG) 1003000300003 SAMPLE RbNO(3). disc-shaped pellets, diam. 1.00 cm. 1003000300004 Thicknesses from 0.20 to 0.25 cm, weights from 0.35 1003000300005 to 0.55 grams. 1003000300006 DETECTOR (PROPC) Thin (3/4 in.) beta proportional counter. 1003000300007 Beta efficiency determined relative to calibrated 1003000300008 gamma detectors. 1003000300009 DECAY-DATA (37-RB-88,17.8MIN,B-) 1003000300010 ERR-ANALYS (DATA-ERR) Standard deviations in absolute cross 1003000300011 section values, and include uncertainties in: 1003000300012 (ERR-1) detection efficiency (7%), 1003000300013 (ERR-2,5.,8.) flux monitor (5-8%), 1003000300014 (ERR-3,1.,4.) decay curve fitting (1-4%), 1003000300015 (ERR-4,1.,4.) neutron energy (1-4%). 1003000300016 HISTORY (20200811A) BP: Added half-life. 1003000300017 STATUS (TABLE) Table 2 of J.Nucl.Energ.24(1970)181. 1003000300018 ENDBIB 16 0 1003000300019 COMMON 1 3 1003000300020 ERR-1 1003000300021 PER-CENT 1003000300022 7. 1003000300023 ENDCOMMON 3 0 1003000300024 DATA 4 24 1003000300025 EN EN-RSL DATA DATA-ERR 1003000300026 KEV KEV MB MB 1003000300027 156. 49.5 8.23 0.81 1003000300028 231. 48.8 7.11 0.71 1003000300029 290. 31.0 6.55 0.66 1003000300030 323. 50.0 5.65 0.57 1003000300031 379. 31.2 5.19 0.49 1003000300032 425. 44.8 5.24 0.58 1003000300033 456. 57.4 3.81 0.38 1003000300034 467. 59.8 4.20 0.40 1003000300035 503. 59.3 3.78 0.38 1003000300036 572. 55.3 3.59 0.36 1003000300037 649. 63.7 4.18 0.43 1003000300038 714. 62.7 2.99 0.30 1003000300039 776. 54.3 2.97 0.31 1003000300040 827. 65.4 2.63 0.26 1003000300041 904. 56.4 2.64 0.26 1003000300042 980. 69.0 2.71 0.27 1003000300043 1070. 81.3 2.78 0.27 1003000300044 1111. 72.2 2.63 0.26 1003000300045 1201. 80.3 2.46 0.25 1003000300046 1297. 50.1 2.47 0.43 1003000300047 1385. 86.1 3.17 0.32 1003000300048 1393. 89.6 2.64 0.27 1003000300049 1484. 87.1 2.52 0.25 1003000300050 1561. 89.4 2.84 0.29 1003000300051 ENDDATA 26 0 1003000300052 ENDSUBENT 51 0 1003000399999 SUBENT 10030004 20200811 14721003000400001 BIB 7 16 1003000400002 REACTION (39-Y-89(N,G)39-Y-90-M,,SIG) 1003000400003 SAMPLE Y2O3. disc-shaped pellets, diam. 1.00 cm, thicknesses 1003000400004 from 0.20 to 0.25 cm, weights from 0.35 to 0.55 grams. 1003000400005 DETECTOR (NAICR) Two 4 x 4 in. Nai(Tl) detectors in close 1003000400006 geometry, corrected for chance coincidences. 1003000400007 DECAY-DATA (39-Y-90-M,3.1HR,DG,202./482.1) 1003000400008 ERR-ANALYS (DATA-ERR) Standard deviations in absolute cross 1003000400009 section values, and include uncertainties in: 1003000400010 (ERR-1) detection efficiency (3%), 1003000400011 (ERR-2,4.,8.) flux monitor (4-8%), 1003000400012 (ERR-3,1.,3.) decay curve fitting (1-3%), 1003000400013 (ERR-4,1.,4.) neutron energy (1-4%). 1003000400014 STATUS (TABLE) Table 3 of J.Nucl.Energ.24(1970)181. 1003000400015 HISTORY (19810423A) BIB correction. 1003000400016 (20200811A) BP: Corrected decaying isotope, added 1003000400017 half-life. 1003000400018 ENDBIB 16 0 1003000400019 COMMON 1 3 1003000400020 ERR-1 1003000400021 PER-CENT 1003000400022 3. 1003000400023 ENDCOMMON 3 0 1003000400024 DATA 4 24 1003000400025 EN EN-RSL DATA DATA-ERR 1003000400026 KEV KEV MB MB 1003000400027 162. 42.9 0.334 0.023 1003000400028 245. 40.5 0.344 0.018 1003000400029 259. 33.3 0.297 0.021 1003000400030 314. 36.0 0.352 0.021 1003000400031 354. 47.4 0.417 0.029 1003000400032 426. 35.6 0.394 0.029 1003000400033 472. 45.4 0.407 0.032 1003000400034 509. 74.1 0.409 0.031 1003000400035 577. 39.4 0.452 0.028 1003000400036 636. 35.8 0.466 0.033 1003000400037 649. 85.2 0.499 0.039 1003000400038 723. 39.7 0.486 0.022 1003000400039 783. 38.2 0.511 0.032 1003000400040 843. 37.8 0.535 0.032 1003000400041 853. 91.8 0.572 0.045 1003000400042 899. 31.2 0.495 0.026 1003000400043 943. 42.9 0.401 0.027 1003000400044 976. 45.4 0.417 0.026 1003000400045 1043. 46.0 0.385 0.024 1003000400046 1106. 44.9 0.324 0.020 1003000400047 1182. 49.9 0.286 0.018 1003000400048 1230. 76.2 0.264 0.022 1003000400049 1330. 69.7 0.284 0.020 1003000400050 1449. 51.3 0.297 0.019 1003000400051 ENDDATA 26 0 1003000400052 ENDSUBENT 51 0 1003000499999 ENDENTRY 4 0 1003099999999