ENTRY 10026 20200811 14721002600000001 SUBENT 10026001 20200811 14721002600100001 BIB 13 41 1002600100002 TITLE Fast neutron capture by vanadium and titanium 1002600100003 AUTHOR (N.D.Dudey, R.R.Heinrich, A.A.Madson) 1002600100004 REFERENCE (J,JNE,23,443,1969) 1002600100005 #doi:10.1016/0022-3107(69)90014-8 1002600100006 (P,ANL-7575,170,1969) Data for reactions 51V(n,g)52V, 1002600100007 50Ti(n,g)51Ti are the same as in the main ref. 1002600100008 (P,ANL-7450,105,1968) Preliminary results. 1002600100009 INSTITUTE (1USAANL) 1002600100010 FACILITY (VDG,1USAANL) 4-MeV Van-de-Graaff. 1002600100011 INC-SOURCE (P-LI7) 7Li(p,n). 1002600100012 INC-SPECT Energy resolution is one-half the full neutron energy 1002600100013 spread. 1002600100014 DETECTOR (NAICR,GELI) Used either NaI(Tl) detector at 45% 1002600100015 geometry or Ge(Li) detector at 25% geometry. Used 1002600100016 152Eu, 154Eu and 160Tb gamma-ray energies and 1002600100017 branching ratios to determine relative detector 1002600100018 efficiency. Absolute efficiency determined using 1002600100019 calibrated standards of 57Co, 137Cs, 54Mn, 60Co. 1002600100020 METHOD (ACTIV) The gold foils sandwiching the targets were 1002600100021 intended as secondary monitors and their thicknesses 1002600100022 were kept sufficiently small to assure that only a 1002600100023 negligible number of neutrons would be removed from 1002600100024 the beam. The primary neutron flux monitor was a 235U 1002600100025 fission chamber. The irradiated samples were counted 1002600100026 either on a 2x1 in. NaI and Ge(Li) gamma-ray detectors 1002600100027 were coupled to a 4096-channel pulse-height analyzer. 1002600100028 MONITOR (92-U-235(N,F),,SIG) Fission chamber as flux monitor. 1002600100029 (79-AU-197(N,G)79-AU-198,,SIG) Au foils sandwiched to 1002600100030 targets used as secondary flux monitors 1002600100031 CORRECTION Corrected for impurities in 235U monitor foil, 1002600100032 variation in neutron intensities, and presence of 2nd 1002600100033 neutron group at approx. 700 keV. Not corrected for 1002600100034 neutron scattering or self-absorption. 1002600100035 STATUS (APRVD) Approved by author. 1002600100036 HISTORY (19691021C) 1002600100037 (19800723A) Converted to reaction formalism 1002600100038 (19810423A) BIB correction to monitor. 1002600100039 (19841205A) BIB corrections. 1002600100040 (19990719A) Converted to new date formats, lower case. 1002600100041 (20200811A) BP: Updated references, added doi, details 1002600100042 of uncertainties and samples. 1002600100043 ENDBIB 41 0 1002600100044 NOCOMMON 0 0 1002600100045 ENDSUBENT 44 0 1002600199999 SUBENT 10026002 20200811 14721002600200001 BIB 5 16 1002600200002 REACTION (23-V-51(N,G)23-V-52,,SIG) 1002600200003 SAMPLE A natural metallic disc of 1 cm dia. 1002600200004 Thickness varied between 0.130 cm and 0.270 cm for 1002600200005 vanadium. Isotopic abundance of 51V was 99.76%. 1002600200006 ERR-ANALYS (DATA-ERR) Standard deviation in absolute value of 1002600200007 cross section given. Individual errors are listed 1002600200008 below: 1002600200009 (ERR-S,1.,5.) Counting statistics. 1002600200010 (ERR-1,3.,4.) Detection efficiency for Ge(Li), NaI(Tl).1002600200011 (ERR-2) Decay scheme. 1002600200012 (ERR-3) 235U(n,F) cs. 1002600200013 (ERR-4,3.,10.) Source-to-target distance. 1002600200014 (ERR-5) Dimensions of proton beam spot. 1002600200015 (ERR-6,1.,4.) Neutron energy. 1002600200016 DECAY-DATA (23-V-52,,DG,1434.) 1002600200017 STATUS (TABLE) Table 1, page 449 of the main reference. 1002600200018 ENDBIB 16 0 1002600200019 COMMON 3 3 1002600200020 ERR-2 ERR-3 ERR-5 1002600200021 PER-CENT PER-CENT PER-CENT 1002600200022 2.0 4.0 10.0 1002600200023 ENDCOMMON 3 0 1002600200024 DATA 4 30 1002600200025 EN EN-RSL DATA DATA-ERR 1002600200026 KEV KEV MB MB 1002600200027 139. 79.4 11.98 0.87 1002600200028 163. 79.9 8.68 0.65 1002600200029 170. 31.9 11.87 1.07 1002600200030 204. 51.6 5.81 0.50 1002600200031 240. 51.6 5.09 0.47 1002600200032 272. 78.9 4.80 0.42 1002600200033 326. 80.1 4.90 0.40 1002600200034 337. 35.3 4.66 0.38 1002600200035 377. 53.5 3.37 0.29 1002600200036 379. 84.5 3.24 0.27 1002600200037 402. 37.0 3.87 0.28 1002600200038 444. 37.2 4.19 0.38 1002600200039 472. 45.4 2.66 0.23 1002600200040 503. 59.4 2.47 0.23 1002600200041 511. 90.3 2.11 0.16 1002600200042 577. 93.4 2.14 0.17 1002600200043 645. 89.4 2.23 0.17 1002600200044 727. 92.2 1.92 0.15 1002600200045 789. 53.6 2.52 0.23 1002600200046 848. 96.5 1.69 0.15 1002600200047 898. 98.4 1.67 0.13 1002600200048 939. 99.9 1.94 0.18 1002600200049 985. 56.9 2.38 0.17 1002600200050 1048. 104. 1.95 0.19 1002600200051 1125. 107. 1.72 0.16 1002600200052 1197. 109. 1.77 0.16 1002600200053 1292. 79.2 2.21 0.19 1002600200054 1385. 86.1 1.68 0.16 1002600200055 1488. 83.5 2.01 0.20 1002600200056 1659. 92.1 2.65 0.20 1002600200057 ENDDATA 32 0 1002600200058 ENDSUBENT 57 0 1002600299999 SUBENT 10026003 20200811 14721002600300001 BIB 5 16 1002600300002 REACTION (22-TI-50(N,G)22-TI-51,,SIG) 1002600300003 SAMPLE A natural metallic disc of 1 cm dia. 1002600300004 Thicknesses varied between 0.250 cm and 0.263 cm for 1002600300005 titanium. Isotopic abundance of 50Ti was 5.34%. 1002600300006 ERR-ANALYS (DATA-ERR) Standard deviation in absolute value of 1002600300007 cross section given. Individual errors are listed 1002600300008 below: 1002600300009 (ERR-S,1.,3.) Counting statistics. 1002600300010 (ERR-1) Detection efficiency for Ge(Li), NaI(Tl). 1002600300011 (ERR-2) Decay scheme. 1002600300012 (ERR-3) 235U(n,F) cs. 1002600300013 (ERR-4,3.,10.) Source-to-target distance. 1002600300014 (ERR-5) Dimensions of proton beam spot. 1002600300015 (ERR-6,1.,4.) Neutron energy. 1002600300016 DECAY-DATA (22-TI-51,,DG,320.) 1002600300017 STATUS (TABLE) Table 2, page 450 of the main reference. 1002600300018 ENDBIB 16 0 1002600300019 COMMON 4 3 1002600300020 ERR-1 ERR-2 ERR-3 ERR-5 1002600300021 PER-CENT PER-CENT PER-CENT PER-CENT 1002600300022 5.0 2.0 4.0 10.0 1002600300023 ENDCOMMON 3 0 1002600300024 DATA 4 27 1002600300025 EN EN-RSL DATA DATA-ERR 1002600300026 KEV KEV MB MB 1002600300027 140. 51.5 1.132 0.131 1002600300028 230. 52.2 0.768 0.075 1002600300029 337. 34.9 0.563 0.051 1002600300030 355. 65.1 0.414 0.036 1002600300031 413. 37.0 0.246 0.031 1002600300032 448. 48.3 0.211 0.019 1002600300033 486. 44.1 0.382 0.038 1002600300034 523. 49.7 0.285 0.026 1002600300035 550. 49.9 0.472 0.042 1002600300036 571. 50.4 0.553 0.050 1002600300037 605. 45.7 0.593 0.063 1002600300038 650. 51.6 0.518 0.045 1002600300039 702. 47.0 0.591 0.056 1002600300040 749. 53.4 0.443 0.040 1002600300041 808. 52.8 0.559 0.054 1002600300042 847. 55.3 0.577 0.052 1002600300043 897. 54.2 0.595 0.055 1002600300044 929. 73.3 0.528 0.053 1002600300045 1025. 75.1 0.745 0.089 1002600300046 1096. 74.8 0.753 0.067 1002600300047 1177. 78.0 0.606 0.056 1002600300048 1206. 65.9 0.730 0.059 1002600300049 1292. 79.1 0.808 0.079 1002600300050 1363. 68.0 0.867 0.073 1002600300051 1428. 82.7 0.730 0.066 1002600300052 1540. 70.7 0.989 0.106 1002600300053 1645. 106.1 0.741 0.110 1002600300054 ENDDATA 29 0 1002600300055 ENDSUBENT 54 0 1002600399999 ENDENTRY 3 0 1002699999999