ENTRY 11262 20220118 14961126200000001 SUBENT 11262001 20220118 14961126200100001 BIB 8 16 1126200100002 TITLE The Capture Cross Section of Boron for Neutrons of 1126200100003 Energies from 0.01 ev to 1000 ev 1126200100004 AUTHOR (R.B.Sutton,B.D.McDaniel,E.E.Anderson,L.S.Lavatelli) 1126200100005 REFERENCE (J,PR,71,272(1),1947) Journal publication. 1126200100006 #doi:10.1103/PhysRev.71.272 1126200100007 (R,LA-92,1944) Original publication. 1126200100008 REL-REF (M,14687001,C.P.Baker+,J,PR,59,332,1941) Method of 1126200100009 modulation of a cyclotron beam. 1126200100010 INSTITUTE (1USALAS) 1126200100011 FACILITY (CYCLO,1USALAS) 1126200100012 DETECTOR (BF3) 1126200100013 HISTORY (19761001T) Translated from SCISRS. 1126200100014 (19810428A) Converted to reaction formalism 1126200100015 (20220118A) BP: Updated to new date formats, lower 1126200100016 case. Corrections according last EXFOR rules and 1126200100017 Dict. Digitized transmission and cross section data. 1126200100018 ENDBIB 16 0 1126200100019 NOCOMMON 0 0 1126200100020 ENDSUBENT 19 0 1126200199999 SUBENT 11262002 20220118 14961126200200001 BIB 3 5 1126200200002 REACTION (5-B-0(N,TOT),,SIG) 1126200200003 STATUS (CURVE) Read from curve for BNL-325. 1126200200004 COMMENT Compiler's comment: Cannot trace these data in 1126200200005 original publications. Perhaps, they were combined from1126200200006 LA-92 cross section measurements. 1126200200007 ENDBIB 5 0 1126200200008 NOCOMMON 0 0 1126200200009 DATA 2 27 1126200200010 EN DATA 1126200200011 EV B 1126200200012 1.01 119. 1126200200013 1.17 103. 1126200200014 1.44 104. 1126200200015 1.9 90.2 1126200200016 3.52 60.5 1126200200017 7.35 45.6 1126200200018 8.95 39. 1126200200019 11.75 32.7 1126200200020 14.75 29.6 1126200200021 20.5 25.1 1126200200022 21.5 23.6 1126200200023 23.75 25.5 1126200200024 24.5 21.5 1126200200025 30. 20.4 1126200200026 32.3 21.5 1126200200027 33.7 20.2 1126200200028 37.7 20. 1126200200029 39. 18.2 1126200200030 48. 17.5 1126200200031 56.2 14.4 1126200200032 61.8 15.3 1126200200033 96.5 14.7 1126200200034 125. 11.7 1126200200035 137. 11. 1126200200036 208. 8.8 1126200200037 328. 7.6 1126200200038 400. 7.2 1126200200039 ENDDATA 29 0 1126200200040 ENDSUBENT 39 0 1126200299999 SUBENT 11262003 20220119 14961126200300001 BIB 6 14 1126200300002 REACTION (5-B-0(N,TOT),,TRN) 1126200300003 SAMPLE Absorber #1: 0.0234 g/cm2 of B and 0.123 g/cm2 of F. 1126200300004 METHOD (TOF) Neutron energies were determined by using the 1126200300005 method of modulation of a cyclotron beam to obtain 1126200300006 the time of Right of the neutrons over a 7.6-meter 1126200300007 path between the neutron moderator and a BF3 neutron 1126200300008 detector. Resolution (on-time) 200 microsec, 1126200300009 frequency 100 cps, source boron, collimation Type 1, 1126200300010 filter none. 1126200300011 ERR-ANALYS (DATA-ERR) Possibly the greatest source of error in 1126200300012 this experiment is the determination of the boron 1126200300013 content of the absorbers. 1126200300014 STATUS (CURVE) Fig. 2, page 13 of report LA-92,1944. 1126200300015 HISTORY (20220119C) BP 1126200300016 ENDBIB 14 0 1126200300017 COMMON 1 3 1126200300018 THICKNESS 1126200300019 G/CM-SQ 1126200300020 0.0234 1126200300021 ENDCOMMON 3 0 1126200300022 DATA 3 11 1126200300023 EN DATA DATA-ERR 1126200300024 EV NO-DIM NO-DIM 1126200300025 1.264E-02 0.325 0.010 1126200300026 1.926E-02 0.332 0.010 1126200300027 2.899E-02 0.390 0.008 1126200300028 4.367E-02 0.416 0.008 1126200300029 5.359E-02 0.442 0.011 1126200300030 6.651E-02 0.445 0.008 1126200300031 8.204E-02 0.496 0.010 1126200300032 1.228E-01 0.562 0.010 1126200300033 1.809E-01 0.599 0.010 1126200300034 2.708E-01 0.668 0.014 1126200300035 3.987E-01 0.742 0.011 1126200300036 ENDDATA 13 0 1126200300037 ENDSUBENT 36 0 1126200399999 SUBENT 11262004 20220119 14961126200400001 BIB 6 14 1126200400002 REACTION (5-B-0(N,TOT),,TRN) 1126200400003 SAMPLE Absorber #2: 0.1493 g/cm2 of B, 0.0735 g/cm2 of C. 1126200400004 METHOD (TOF) Neutron energies were determined by using the 1126200400005 method of modulation of a cyclotron beam to obtain 1126200400006 the time of Right of the neutrons over a 7.6-meter 1126200400007 path between the neutron moderator and a BF3 neutron 1126200400008 detector. Resolution (on-time) 50 microsec, 1126200400009 frequency 1000 cps, source paraffin, 1126200400010 collimation Type 1, Cd filter. 1126200400011 ERR-ANALYS (DATA-ERR) Possibly the greatest source of error in 1126200400012 this experiment is the determination of the boron 1126200400013 content of the absorbers. 1126200400014 STATUS (CURVE) Fig. 3, page 14 of report LA-92,1944. 1126200400015 HISTORY (20220119C) BP 1126200400016 ENDBIB 14 0 1126200400017 COMMON 1 3 1126200400018 THICKNESS 1126200400019 G/CM-SQ 1126200400020 0.1493 1126200400021 ENDCOMMON 3 0 1126200400022 DATA 3 12 1126200400023 EN DATA DATA-ERR 1126200400024 EV NO-DIM NO-DIM 1126200400025 2.898E-01 0.170 0.022 1126200400026 4.533E-01 0.213 0.013 1126200400027 7.177E-01 0.230 0.012 1126200400028 1.140E+00 0.277 0.009 1126200400029 1.450E+00 0.333 0.012 1126200400030 1.810E+00 0.336 0.012 1126200400031 2.301E+00 0.400 0.013 1126200400032 2.934E+00 0.403 0.013 1126200400033 3.675E+00 0.444 0.013 1126200400034 5.815E+00 0.561 0.011 1126200400035 9.314E+00 0.649 0.016 1126200400036 1.487E+01 0.793 0.020 1126200400037 ENDDATA 14 0 1126200400038 ENDSUBENT 37 0 1126200499999 SUBENT 11262005 20220119 14961126200500001 BIB 6 15 1126200500002 REACTION (5-B-0(N,TOT),,TRN) 1126200500003 SAMPLE Absorber #3: 0.594 g/cm2 of B, 0.285 g/cm2 of C, 1126200500004 0.049 g/cm2 of O, 0.17 g/cm2 of Pb. 1126200500005 METHOD (TOF) Neutron energies were determined by using the 1126200500006 method of modulation of a cyclotron beam to obtain 1126200500007 the time of Right of the neutrons over a 7.6-meter 1126200500008 path between the neutron moderator and a BF3 neutron 1126200500009 detector. Resolution (on-time) 10 microsec, 1126200500010 frequency 1000 cps, source paraffin, collimation 1126200500011 Type 2, Cd filter. 1126200500012 ERR-ANALYS (DATA-ERR) Possibly the greatest source of error in 1126200500013 this experiment is the determination of the boron 1126200500014 content of the absorbers. 1126200500015 STATUS (CURVE) Fig. 4, page 15 of report LA-92,1944. 1126200500016 HISTORY (20220119C) BP 1126200500017 ENDBIB 15 0 1126200500018 COMMON 1 3 1126200500019 THICKNESS 1126200500020 G/CM-SQ 1126200500021 0.594 1126200500022 ENDCOMMON 3 0 1126200500023 DATA 3 11 1126200500024 EN DATA DATA-ERR 1126200500025 EV NO-DIM NO-DIM 1126200500026 9.147E+00 0.235 0.012 1126200500027 1.347E+01 0.283 0.011 1126200500028 1.960E+01 0.318 0.014 1126200500029 2.863E+01 0.361 0.016 1126200500030 3.486E+01 0.346 0.014 1126200500031 4.182E+01 0.412 0.014 1126200500032 5.087E+01 0.418 0.015 1126200500033 7.482E+01 0.511 0.015 1126200500034 1.102E+02 0.548 0.019 1126200500035 1.603E+02 0.621 0.019 1126200500036 2.335E+02 0.768 0.022 1126200500037 ENDDATA 13 0 1126200500038 ENDSUBENT 37 0 1126200599999 SUBENT 11262006 20220119 14961126200600001 BIB 6 14 1126200600002 REACTION (5-B-0(N,TOT),,TRN) 1126200600003 SAMPLE Absorber #4: 1.80 g/cm2 of B, 0.885 g/cm2 of C. 1126200600004 METHOD (TOF) Neutron energies were determined by using the 1126200600005 method of modulation of a cyclotron beam to obtain 1126200600006 the time of Right of the neutrons over a 7.6-meter 1126200600007 path between the neutron moderator and a BF3 neutron 1126200600008 detector. Resolution (on-time) 10 microsec, 1126200600009 frequency 1000 cps, source paraffin, collimation 1126200600010 Type 2, Cd filter. 1126200600011 ERR-ANALYS (DATA-ERR) Possibly the greatest source of error in 1126200600012 this experiment is the determination of the boron 1126200600013 content of the absorbers. 1126200600014 STATUS (CURVE) Fig. 5, page 16 of report LA-92,1944. 1126200600015 HISTORY (20220119C) BP 1126200600016 ENDBIB 14 0 1126200600017 COMMON 1 3 1126200600018 THICKNESS 1126200600019 G/CM-SQ 1126200600020 1.80 1126200600021 ENDCOMMON 3 0 1126200600022 DATA 3 12 1126200600023 EN DATA DATA-ERR 1126200600024 EV NO-DIM NO-DIM 1126200600025 2.559E+01 0.047 0.012 1126200600026 3.634E+01 0.063 0.010 1126200600027 5.289E+01 0.066 0.012 1126200600028 7.604E+01 0.081 0.010 1126200600029 1.100E+02 0.094 0.010 1126200600030 1.582E+02 0.122 0.010 1126200600031 2.274E+02 0.130 0.013 1126200600032 3.290E+02 0.177 0.010 1126200600033 4.731E+02 0.220 0.012 1126200600034 6.763E+02 0.283 0.007 1126200600035 9.730E+02 0.378 0.016 1126200600036 1.417E+03 0.456 0.014 1126200600037 ENDDATA 14 0 1126200600038 ENDSUBENT 37 0 1126200699999 SUBENT 11262007 20220119 14961126200700001 BIB 5 13 1126200700002 REACTION (5-B-0(N,TOT),,SIG) 1126200700003 ANALYSIS These cross-sections include the scattering 1126200700004 cross-sections of boron and the elements other than 1126200700005 boron which were present in the absorbers. To extract 1126200700006 cross sections one can use a simple formula: 1126200700007 Transmission = exp(-sigma*n), where sigma is cross 1126200700008 section and n is the number of atoms in absorber. 1126200700009 ERR-ANALYS (DATA-ERR) Possibly the greatest source of error in 1126200700010 this experiment is the determination of the boron 1126200700011 content of the absorbers. 1126200700012 STATUS (DEP,11262003) 1126200700013 (CURVE) Fig. 6, page 17 of report LA-92,1944. 1126200700014 HISTORY (20220119C) BP 1126200700015 ENDBIB 13 0 1126200700016 NOCOMMON 0 0 1126200700017 DATA 3 11 1126200700018 EN DATA DATA-ERR 1126200700019 EV B B 1126200700020 1.281E-02 876.806 24.523 1126200700021 1.981E-02 863.769 21.798 1126200700022 2.955E-02 733.514 16.341 1126200700023 4.402E-02 679.553 19.081 1126200700024 5.404E-02 636.231 16.312 1126200700025 6.666E-02 631.064 16.341 1126200700026 8.143E-02 549.588 10.899 1126200700027 1.241E-01 449.336 13.624 1126200700028 1.838E-01 400.817 16.371 1126200700029 2.709E-01 314.144 19.088 1126200700030 4.038E-01 230.210 16.349 1126200700031 ENDDATA 13 0 1126200700032 ENDSUBENT 31 0 1126200799999 SUBENT 11262008 20220119 14961126200800001 BIB 5 13 1126200800002 REACTION (5-B-0(N,TOT),,SIG) 1126200800003 ANALYSIS These cross-sections include the scattering 1126200800004 cross-sections of boron and the elements other than 1126200800005 boron which were present in the absorbers. To extract 1126200800006 cross sections one can use a simple formula: 1126200800007 Transmission = exp(-sigma*n), where sigma is cross 1126200800008 section and n is the number of atoms in absorber. 1126200800009 ERR-ANALYS (DATA-ERR) Possibly the greatest source of error in 1126200800010 this experiment is the determination of the boron 1126200800011 content of the absorbers. 1126200800012 STATUS (DEP,11262004) 1126200800013 (CURVE) Fig. 7, page 18 of report LA-92,1944. 1126200800014 HISTORY (20220119C) BP 1126200800015 ENDBIB 13 0 1126200800016 NOCOMMON 0 0 1126200800017 DATA 3 12 1126200800018 EN DATA DATA-ERR 1126200800019 EV B B 1126200800020 2.869E-01 217.254 15.857 1126200800021 4.498E-01 189.022 6.567 1126200800022 7.113E-01 178.846 4.923 1126200800023 1.137E+00 157.734 4.374 1126200800024 1.443E+00 133.777 3.282 1126200800025 1.801E+00 131.694 3.280 1126200800026 2.273E+00 111.564 3.820 1126200800027 2.908E+00 110.040 4.376 1126200800028 3.668E+00 98.663 3.280 1126200800029 5.897E+00 70.442 2.735 1126200800030 9.379E+00 51.516 3.827 1126200800031 1.515E+01 27.674 3.282 1126200800032 ENDDATA 14 0 1126200800033 ENDSUBENT 32 0 1126200899999 SUBENT 11262009 20220119 14961126200900001 BIB 5 13 1126200900002 REACTION (5-B-0(N,TOT),,SIG) 1126200900003 ANALYSIS These cross-sections include the scattering 1126200900004 cross-sections of boron and the elements other than 1126200900005 boron which were present in the absorbers. To extract 1126200900006 cross sections one can use a simple formula: 1126200900007 Transmission = exp(-sigma*n), where sigma is cross 1126200900008 section and n is the number of atoms in absorber. 1126200900009 ERR-ANALYS (DATA-ERR) Possibly the greatest source of error in 1126200900010 this experiment is the determination of the boron 1126200900011 content of the absorbers. 1126200900012 STATUS (DEP,11262005) 1126200900013 (CURVE) Fig. 8, page 19 of report LA-92,1944. 1126200900014 HISTORY (20220119C) BP 1126200900015 ENDBIB 13 0 1126200900016 NOCOMMON 0 0 1126200900017 DATA 3 11 1126200900018 EN DATA DATA-ERR 1126200900019 EV B B 1126200900020 9.024E+00 44.413 1.373 1126200900021 1.329E+01 38.749 1.083 1126200900022 1.962E+01 34.169 1.084 1126200900023 2.855E+01 31.173 1.016 1126200900024 3.445E+01 32.529 1.087 1126200900025 4.177E+01 27.096 1.010 1126200900026 5.053E+01 26.647 0.872 1126200900027 7.445E+01 20.549 0.864 1126200900028 1.091E+02 18.134 1.083 1126200900029 1.603E+02 14.491 0.868 1126200900030 2.353E+02 7.887 0.718 1126200900031 ENDDATA 13 0 1126200900032 ENDSUBENT 31 0 1126200999999 SUBENT 11262010 20220119 14961126201000001 BIB 5 13 1126201000002 REACTION (5-B-0(N,TOT),,SIG) 1126201000003 ANALYSIS These cross-sections include the scattering 1126201000004 cross-sections of boron and the elements other than 1126201000005 boron which were present in the absorbers. To extract 1126201000006 cross sections one can use a simple formula: 1126201000007 Transmission = exp(-sigma*n), where sigma is cross 1126201000008 section and n is the number of atoms in absorber. 1126201000009 ERR-ANALYS (DATA-ERR) Possibly the greatest source of error in 1126201000010 this experiment is the determination of the boron 1126201000011 content of the absorbers. 1126201000012 STATUS (DEP,11262006) 1126201000013 (CURVE) Fig. 9, page 20 of report LA-92,1944. 1126201000014 HISTORY (20220119C) BP 1126201000015 ENDBIB 13 0 1126201000016 NOCOMMON 0 0 1126201000017 DATA 3 12 1126201000018 EN DATA DATA-ERR 1126201000019 EV B B 1126201000020 2.523E+01 30.326 1.971 1126201000021 3.653E+01 27.439 1.753 1126201000022 5.279E+01 26.851 1.479 1126201000023 7.638E+01 25.004 1.150 1126201000024 1.096E+02 23.868 1.260 1126201000025 1.562E+02 21.144 0.766 1126201000026 2.275E+02 20.502 1.041 1126201000027 3.320E+02 17.505 0.547 1126201000028 4.731E+02 15.220 0.547 1126201000029 6.849E+02 12.551 0.492 1126201000030 9.839E+02 9.773 0.494 1126201000031 1.424E+03 7.871 0.438 1126201000032 ENDDATA 14 0 1126201000033 ENDSUBENT 32 0 1126201099999 SUBENT 11262011 20220119 14961126201100001 BIB 6 20 1126201100002 REACTION (5-B-0(N,SCT)5-B-0,,SIG,,AV) 1126201100003 REL-REF (R,,H.C.Uchiyamada,R,CP-1330,1944) Table of assumed 1126201100004 cross sections. 1126201100005 ANALYSIS The scattering cross section is obtained by taking 1126201100006 the extrapolated value of the total cross section at 1126201100007 zero time of flight. Since these scattering 1126201100008 cross-sections include the scattering of elements 1126201100009 other than boron, in order to determine the boron 1126201100010 scattering, it is necessary to subtract the 1126201100011 contribution of the other elements to the scattering. 1126201100012 ASSUMED (ASSUM1,6-C-0(N,SCT)6-C-0,,SIG) 1126201100013 (ASSUM2,8-O-0(N,SCT)8-O-0,,SIG) 1126201100014 (ASSUM3,82-PB-0(N,SCT)82-PB-0,,SIG) 1126201100015 (ASSUM4,9-F-19(N,SCT)9-F-19,,SIG) 1126201100016 STATUS (DEP,11262007) 1126201100017 (DEP,11262008) 1126201100018 (DEP,11262009) 1126201100019 (DEP,11262010) 1126201100020 (TABLE) page 9 of report LA-92,1944. 1126201100021 HISTORY (20220118C) BP 1126201100022 ENDBIB 20 0 1126201100023 NOCOMMON 0 0 1126201100024 DATA 7 1 1126201100025 EN-MIN EN-MAX DATA-APRX ASSUM1 ASSUM2 ASSUM3 1126201100026 ASSUM4 1126201100027 EV EV B B B B 1126201100028 B 1126201100029 0.01 1000.0 4.2 4.85 4.2 9.61126201100030 4.1 1126201100031 ENDDATA 6 0 1126201100032 ENDSUBENT 31 0 1126201199999 ENDENTRY 11 0 1126299999999