ENTRY 11235 20241001 151511235000 1 SUBENT 11235001 20241001 151511235001 1 BIB 6 14 11235001 2 TITLE Cross sections for the B11(n, gamma)B12 reaction 11235001 3 AUTHOR (W.L.Imhof,R.G.Johnson,F.J.Vaughn,M.Walt) 11235001 4 REFERENCE (J,PR,125,1334,1962) 11235001 5 #doi:10.1103/PhysRev.125.1334 11235001 6 (W,IMHOF,1963) 11235001 7 INSTITUTE (1USALMS) 11235001 8 FACILITY (VDG,1USALMS) 3 Mev Van de Graaff generator. 11235001 9 HISTORY (19760629T) Translated from SCISRS. 11235001 10 (19800820A) converted to reaction formalism. 11235001 11 (20201028A) BP: Verified entry using a private 11235001 12 communication from Imhof. Updated to new date formats, 11235001 13 lower case. Corrections according latest EXFOR rules 11235001 14 and Dict. 11235001 15 (20240915A) OS. STATUS changed in subs.2,5 11235001 16 ENDBIB 14 0 11235001 17 NOCOMMON 0 0 11235001 18 ENDSUBENT 17 0 1123500199999 SUBENT 11235002 20241001 151511235002 1 BIB 8 21 11235002 2 REACTION (5-B-0(N,TOT),,SIG) 11235002 3 SAMPLE The total cross section sample consisted of boron 11235002 4 powder packed in a 2.54 cm diameter tantalum cylinder 11235002 5 with a wall thickness of 0.014 cm. 11235002 6 DETECTOR (SCIN) Plastic scintillator having a diameter of 5.08 11235002 7 cm and a length of 2.54 cm. 11235002 8 METHOD (TOF) Time of flight discrimination was used. The 11235002 9 neutrons were detected by a plastic scintillator 11235002 10 which was placed in the collimator at a distance of 11235002 11 92 cm from the boron sample. An identical tantalum 11235002 12 cylinder containing no boron was used to determine 11235002 13 the "sample-out" counts. 11235002 14 ERR-ANALYS (ERR-S) Statistical error in all total cross 11235002 15 sections for E=950-1095 keV is approximately +-0.09 b. 11235002 16 CORRECTION In-scattering corrections of about 0.5% of 11235002 17 the cross section were applied to the data. 11235002 18 STATUS (SCSRS) 11235002 19 HISTORY (20201028A) BP: Added sample, detector, method, 11235002 20 correction, uncertainties and status, corrected neutron11235002 21 energy values. 11235002 22 (20240915A) STATUS changed 11235002 23 ENDBIB 21 0 11235002 24 COMMON 1 3 11235002 25 EN-RSL 11235002 26 KEV 11235002 27 4.0 11235002 28 ENDCOMMON 3 0 11235002 29 DATA 3 47 11235002 30 EN DATA ERR-S 11235002 31 MEV B B 11235002 32 0.9501 1.841 0.09 11235002 33 0.9599 1.709 0.09 11235002 34 0.9686 1.825 0.09 11235002 35 0.9739 1.671 0.09 11235002 36 0.9787 1.608 0.09 11235002 37 0.985 1.679 0.09 11235002 38 0.9895 1.484 0.09 11235002 39 0.9947 1.382 0.09 11235002 40 0.9997 1.698 0.09 11235002 41 1.0045 1.454 0.09 11235002 42 1.009 1.452 0.09 11235002 43 1.0125 1.436 0.09 11235002 44 1.0148 1.240 0.09 11235002 45 1.017 1.399 0.09 11235002 46 1.019 1.313 0.09 11235002 47 1.0204 1.181 0.09 11235002 48 1.0216 1.145 0.09 11235002 49 1.0227 1.247 0.09 11235002 50 1.024 1.181 0.09 11235002 51 1.025 1.291 0.09 11235002 52 1.026 1.560 0.09 11235002 53 1.0277 1.565 0.09 11235002 54 1.030 1.741 0.09 11235002 55 1.0321 1.697 0.09 11235002 56 1.0339 1.817 0.09 11235002 57 1.0351 1.831 0.09 11235002 58 1.0367 1.817 0.09 11235002 59 1.0387 1.710 0.09 11235002 60 1.0405 1.808 0.09 11235002 61 1.0423 1.829 0.09 11235002 62 1.0468 1.814 0.09 11235002 63 1.0517 1.834 0.09 11235002 64 1.0554 1.742 0.09 11235002 65 1.067 1.876 0.09 11235002 66 1.081 1.991 0.09 11235002 67 1.095 1.833 0.09 11235002 68 1.125 2.280 11235002 69 1.150 2.304 11235002 70 1.175 2.723 11235002 71 1.200 2.959 11235002 72 1.225 3.395 11235002 73 1.250 3.896 11235002 74 1.250 3.941 11235002 75 1.275 4.289 11235002 76 1.300 4.142 11235002 77 1.325 3.736 11235002 78 1.350 3.257 11235002 79 ENDDATA 49 0 11235002 80 ENDSUBENT 79 0 1123500299999 SUBENT 11235003 20201028 147411235 3 1 BIB 4 6 11235 3 2 REACTION 1(5-B-11(N,0),,EN) 11235 3 3 2(5-B-11(N,G),,WID) 11235 3 4 ERR-ANALYS (DATA-ERR) Estimated uncertainty. 11235 3 5 STATUS (DEP,11235005) 11235 3 6 (TABLE) Page 1336 of J,PR,125,1334,1962. 11235 3 7 HISTORY (20201028A) BP: Updated uncertainties and status. 11235 3 8 ENDBIB 6 0 11235 3 9 NOCOMMON 0 0 11235 3 10 DATA 3 4 11235 3 11 DATA 1DATA 2DATA-ERR 2 11235 3 12 MEV MILLI-EV PER-CENT 11235 3 13 4.30E-01 3.00E+05 50.0 11235 3 14 1.027 3.00E+05 50.0 11235 3 15 1.280 2.00E+05 50.0 11235 3 16 1.780 9.00E+05 50.0 11235 3 17 ENDDATA 6 0 11235 3 18 ENDSUBENT 17 0 11235 399999 SUBENT 11235004 20201028 147411235 4 1 BIB 4 8 11235 4 2 REACTION 1(5-B-11(N,TOT),,WID) 11235 4 3 2(5-B-11(N,0),,J) 11235 4 4 3(5-B-11(N,0),,L) 11235 4 5 ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 11235 4 6 STATUS (DEP,11235005) 11235 4 7 (DEP,11235004) 11235 4 8 (TABLE) Page 1336 of J,PR,125,1334,1962. 11235 4 9 HISTORY (20201028A) BP: Updated uncertainties and status. 11235 4 10 ENDBIB 8 0 11235 4 11 NOCOMMON 0 0 11235 4 12 DATA 6 1 11235 4 13 EN-RES EN-RSL DATA 1DATA-ERR 1DATA 2DATA 311235 4 14 MEV MEV KEV KEV NO-DIM NO-DIM 11235 4 15 1.027 1.0E-02 10. 4. 1. 0.11235 4 16 ENDDATA 3 0 11235 4 17 ENDSUBENT 16 0 11235 499999 SUBENT 11235005 20241001 151511235005 1 BIB 9 17 11235005 2 REACTION (5-B-11(N,G)5-B-12,,SIG) 11235005 3 DETECTOR (TELES) Counter telescope 11235005 4 SAMPLE A powdered mixture of natural boron and iodine. 11235005 5 METHOD (ACTIV) Samples were bombarded with monoenergetic 11235005 6 neutrons and the resulting B12 beta-ray activity was 11235005 7 observed. The observed decrease in counting rate with 11235005 8 time indicated that the activity had a lifetime of 11235005 9 about 20 msec and served to identify it as produced 11235005 10 by the B11(n,gamma)B12 reaction. 11235005 11 MONITOR (53-I-127(N,G)53-I-128,,SIG) 11235005 12 ERR-ANALYS (ERR-S) Errors indicated are due to counting statistics11235005 13 only. Probable total error is 50%. 11235005 14 DECAY-DATA (5-B-12,20.0MSEC,B-) 11235005 15 STATUS (SCSRS) 11235005 16 HISTORY (20201028A) BP: Added sample, method, decay data, 11235005 17 status and updated uncertainties. 11235005 18 (20240915A) STATUS changed 11235005 19 ENDBIB 17 0 11235005 20 NOCOMMON 0 0 11235005 21 DATA 4 42 11235005 22 EN EN-RSL DATA ERR-S 11235005 23 MEV MEV B B 11235005 24 1.39E-01 7.00E-02 8.1E-06 0.5E-06 11235005 25 1.98E-01 7.00E-02 1.27E-05 1.0E-06 11235005 26 2.38E-01 7.00E-02 1.05E-05 2.1E-06 11235005 27 2.87E-01 7.00E-02 1.03E-05 1.8E-06 11235005 28 3.36E-01 7.00E-02 1.58E-05 1.9E-06 11235005 29 3.73E-01 7.00E-02 1.56E-05 1.3E-06 11235005 30 4.15E-01 7.00E-02 2.92E-05 1.2E-06 11235005 31 4.29E-01 7.00E-02 2.99E-05 1.6E-06 11235005 32 4.35E-01 7.00E-02 2.55E-05 1.3E-06 11235005 33 4.45E-01 7.00E-02 2.74E-05 1.3E-06 11235005 34 4.97E-01 7.00E-02 1.29E-05 0.5E-06 11235005 35 5.30E-01 7.00E-02 9.3E-06 1.0E-06 11235005 36 5.87E-01 7.00E-02 1.02E-05 0.4E-06 11235005 37 6.81E-01 7.00E-02 7.6E-06 0.6E-06 11235005 38 7.55E-01 7.00E-02 8.4E-06 1.2E-06 11235005 39 7.80E-01 7.00E-02 1.00E-05 1.1E-06 11235005 40 8.78E-01 7.00E-02 7.5E-06 1.6E-06 11235005 41 9.27E-01 7.00E-02 1.07E-05 1.2E-06 11235005 42 9.65E-01 7.00E-02 1.10E-05 1.1E-06 11235005 43 1.031 7.00E-02 1.54E-05 0.7E-06 11235005 44 1.063 7.00E-02 1.31E-05 1.1E-06 11235005 45 1.113 7.00E-02 1.05E-05 0.8E-06 11235005 46 1.170 7.00E-02 7.3E-06 0.9E-06 11235005 47 1.215 7.00E-02 7.7E-06 0.8E-06 11235005 48 1.244 7.00E-02 1.08E-05 1.2E-06 11235005 49 1.281 7.00E-02 1.00E-05 0.7E-06 11235005 50 1.332 7.00E-02 8.8E-06 0.8E-06 11235005 51 1.371 7.00E-02 7.7E-06 1.1E-06 11235005 52 1.479 7.00E-02 7.3E-06 0.7E-06 11235005 53 1.568 7.00E-02 5.7E-06 0.9E-06 11235005 54 1.640 7.00E-02 8.7E-06 1.0E-06 11235005 55 1.680 7.0E-02 8.4E-06 0.9E-06 11235005 56 1.726 2.00E-01 1.14E-05 0.7E-06 11235005 57 1.760 2.00E-01 1.24E-05 1.1E-06 11235005 58 1.796 2.00E-01 1.16E-05 0.7E-06 11235005 59 1.832 2.00E-01 9.6E-06 1.0E-06 11235005 60 1.932 2.00E-01 8.0E-06 1.0E-06 11235005 61 2.085 2.00E-01 7.9E-06 1.0E-06 11235005 62 2.180 2.00E-01 6.7E-06 0.9E-06 11235005 63 2.228 2.00E-01 1.08E-05 1.0E-06 11235005 64 2.279 2.00E-01 1.08E-05 1.0E-06 11235005 65 2.325 2.00E-01 9.9E-06 1.0E-06 11235005 66 ENDDATA 44 0 11235005 67 ENDSUBENT 66 0 1123500599999 SUBENT 11235006 20201028 147411235 6 1 BIB 11 30 11235 6 2 REACTION (5-B-11(N,G)5-B-12,,SIG) 11235 6 3 INC-SOURCE (P-LI7) The paraffin block was bombarded with 11235 6 4 neutrons produced by the Li7(p,n) Be7 reaction. 11235 6 5 SAMPLE (5-B-11,ENR=0.985) For this measurement a boron 11235 6 6 sample enriched to 98.5% in B11 was used. The 11235 6 7 activation samples were hollow Plexiglass cylinders 11235 6 8 containing powdered boron mixed with 20% w/w powdered 11235 6 9 iodine. These cylinders had a wall thickness of 0.08 cm11235 6 10 and were 2.54 cm in diameter and 0.5 cm in length. 11235 6 11 DETECTOR (SCIN) The beta particles emitted by the B12 nuclei 11235 6 12 were detected by two 2.54 cm diameter plastic 11235 6 13 scintillators operated in coincidence. 11235 6 14 METHOD (ACTIV,COINC) Measurements at thermal energies were 11235 6 15 performed by placing the boron sample and the 11235 6 16 beta-ray counter at the center of a paraffin cube 11235 6 17 whose edges were 25 cm long. The reaction rate due to 11235 6 18 thermal neutrons was obtained from the observed 11235 6 19 difference in the counting rates from the boron 11235 6 20 sample with and without a cadmium cover. 11235 6 21 ANALYSIS The cross sections were calculated from the observed 11235 6 22 B12 activities, the amount of B11 in the samples, and 11235 6 23 the effective neutron flux striking the B11 11235 6 24 activation samples. 11235 6 25 MONITOR (53-I-127(N,G)53-I-128,,SIG) 11235 6 26 DECAY-DATA (5-B-12,20.0MSEC,B-) 11235 6 27 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 11235 6 28 STATUS (TABLE) Page 1336 of J,PR,125,1334,1962. 11235 6 29 HISTORY (19840605A) Data heading corrected. 11235 6 30 (20201028A) BP: Added sample, method, decay data, 11235 6 31 detector, analysis and status. 11235 6 32 ENDBIB 30 0 11235 6 33 NOCOMMON 0 0 11235 6 34 DATA 4 1 11235 6 35 EN DATA DATA-ERR MONIT 11235 6 36 EV MB MB B 11235 6 37 0.0253 5. 3. 5.6 11235 6 38 ENDDATA 3 0 11235 6 39 ENDSUBENT 38 0 11235 699999 ENDENTRY 6 0 1123599999999