ENTRY 21454 20160721 22522145400000001 SUBENT 21454001 20160721 22522145400100001 BIB 12 54 2145400100002 INSTITUTE (2UK HAR) 2145400100003 REFERENCE (C,65SALZBURG,2,25,196503) 2145400100004 (C,66PARIS,1,307,196610) Results confirmed with other 2145400100005 determination of efficiency (standard sources). 2145400100006 AUTHOR (D.W.Colvin,M.G.Sowerby) 2145400100007 TITLE Boron pile nu-bar measurements 2145400100008 SAMPLE .No details given. Effects from foil thickness were 2145400100009 less than 0.3%, according to the authors. 2145400100010 METHOD .Boron pile. Fission neutrons slowed down in a 2145400100011 220 cm side cubic core of a graphite stack, 2145400100012 surrounded by a 35 cm thick graphite reflector to 2145400100013 keep them inside. The whole is surrounded by a 2145400100014 neutron shield consisting of 0.4 mm cadmium inside 2145400100015 61 cm of concrete. 2145400100016 DETECTOR (BF3) 2 BF3-counters in each hole of the lattice 2145400100017 of 11*11 holes in the graphite stack of the boron 2145400100018 pile. 5 cm diam detectors, enriched boron, 2145400100019 (FISCH) fission chamber in the centre of the boron 2145400100020 pile. 2145400100021 (IOCH) For measuring the monitor reaction. It 2145400100022 contains C-D(4). 2145400100023 PART-DET (N) Fission neutrons, and 2145400100024 (FF) fission fragments. 2145400100025 REL-REF (I,22509001,D.W.Colvin+,C,58GENEVA,16,121,1958) - A 2145400100026 full description of the boron pile. 2145400100027 COMMENT .Efficiency determined by measuring the number of 2145400100028 neutrons emitted per reaction (1-H-2(gamma,n)1-H-1), 2145400100029 which is 1. this efficiency was of the order of 64% 2145400100030 Absolute measurement. 2145400100031 .A number of pitfalls is discussed in the article, 2145400100032 e.g. A 50 Hz modulation of the Van de Graaff beam 2145400100033 by the magnetic field of the belt motors, anisotropy 2145400100034 of the efficiency, (n,f)-reactions induced by the 2145400100035 prompt neutrons, foil thickness effects. 2145400100036 CORRECTION .Background correction determined with a delayed 2145400100037 coincidence technique. Seven other corrections 2145400100038 discussed in reference, viz. count-rate effect, 2145400100039 overlap correction, effect of fission chamber, 2145400100040 ionization chamber and beam tube on the boron pile 2145400100041 efficiency, neutrons captured after the gate for 2145400100042 counting the fission neutrons is closed, the 2145400100043 variation of efficiency with the position in the 2145400100044 central channel, effects of impurities in the 2145400100045 fission foils, correction for delayed neutrons. 2145400100046 HISTORY (19800305T) G.C. 2145400100047 (19800318E) 2145400100048 (19800331A) 2 Independent data from 66Paris added. 2145400100049 (19800429E) 2145400100050 (20041111A) Date is corrected. Correlation established 2145400100051 (20120917A) SD: Updated to new date formats,lower case.2145400100052 INC-SOURCE moved to Subents 002-008, 011. ERR-ANALYS 2145400100053 moved to Subents 002-011. 2145400100054 (20160721A) SD: The '//' -> '/' in REACTION code in 2145400100055 Subents 002, 003, 006 following EXFOR rules. 2145400100056 ENDBIB 54 0 2145400100057 NOCOMMON 0 0 2145400100058 ENDSUBENT 57 0 2145400199999 SUBENT 21454002 20160721 22522145400200001 BIB 7 18 2145400200002 REACTION ((92-U-233(N,F),PR,NU,,MXW)/ 2145400200003 (92-U-235(N,F),PR,NU,,MXW)) 2145400200004 INC-SPECT Neutron beam from GLEEP. 2145400200005 INC-SOURCE (REAC) For the thermal neutrons. 2145400200006 FACILITY (REAC,2UK HAR) Gleep for producing thermal neutrons. 2145400200007 ERR-ANALYS (ERR-T) .Two errors were always calculated, viz an 2145400200008 internal one and an external one. The biggest of them 2145400200009 was always taken. Total uncertainty includes: 2145400200010 (ERR-1) Uncertainty in U-235 efficiency of (0.31%), 2145400200011 (ERR-S) Uncertainty in value of neutrons detected per 2145400200012 counted fission event 0.40%, 2145400200013 (ERR-3) loss of fission fragments below the bias, 2145400200014 (ERR-4) effect of electrical pickup, 2145400200015 (ERR-5) anisotropy in efficiency, 2145400200016 (ERR-6) correction for neutrons captured after the gate2145400200017 STATUS (TABLE) Data from Tbl.III of 65SALZBURG,2,25,1965 2145400200018 HISTORY (20160721A) SD: The '//' -> '/' in REACTION code 2145400200019 following EXFOR rules. 2145400200020 ENDBIB 18 0 2145400200021 COMMON 6 3 2145400200022 ERR-1 ERR-S ERR-3 ERR-4 ERR-5 ERR-6 2145400200023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2145400200024 0.31 0.40 0.3 0.03 0.20 0.10 2145400200025 ENDCOMMON 3 0 2145400200026 DATA 3 1 2145400200027 EN-DUMMY DATA ERR-T 2145400200028 EV NO-DIM NO-DIM 2145400200029 2.5300E-02 1.0200E+00 6.0000E-03 2145400200030 ENDDATA 3 0 2145400200031 ENDSUBENT 30 0 2145400299999 SUBENT 21454003 20160721 22522145400300001 BIB 7 18 2145400300002 REACTION ((94-PU-239(N,F),PR,NU,,MXW)/ 2145400300003 (92-U-235(N,F),PR,NU,,MXW)) 2145400300004 INC-SPECT Thermal neutron beam from GLEEP. 2145400300005 INC-SOURCE (REAC) For the thermal neutrons. 2145400300006 FACILITY (REAC,2UK HAR) Gleep for producing thermal neutrons. 2145400300007 STATUS (TABLE) Data from Tbl.III of 65SALZBURG,2,25,1965 2145400300008 ERR-ANALYS (ERR-T) .Two errors were always calculated, viz an 2145400300009 internal one and an external one. The biggest of them 2145400300010 was always taken. Total uncertainty includes: 2145400300011 (ERR-1) Uncertainty in efficiency, 2145400300012 (ERR-S) Uncertainty in value of neutrons detected per 2145400300013 counted fission event 2145400300014 (ERR-3) loss of fission fragments below the bias, 2145400300015 (ERR-4) effect of electrical pickup, 2145400300016 (ERR-5) anisotropy in efficiency, 2145400300017 (ERR-6) correction for neutrons captured after the gate2145400300018 HISTORY (20160721A) SD: The '//' -> '/' in REACTION code 2145400300019 following EXFOR rules. 2145400300020 ENDBIB 18 0 2145400300021 COMMON 6 3 2145400300022 ERR-1 ERR-S ERR-3 ERR-4 ERR-5 ERR-6 2145400300023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2145400300024 0.31 0.40 0.3 0.03 0.20 0.10 2145400300025 ENDCOMMON 3 0 2145400300026 DATA 3 1 2145400300027 EN-DUMMY DATA ERR-T 2145400300028 EV NO-DIM NO-DIM 2145400300029 2.5300E-02 1.1820E+00 8.0000E-03 2145400300030 ENDDATA 3 0 2145400300031 ENDSUBENT 30 0 2145400399999 SUBENT 21454004 20120917 22342145400400001 BIB 7 17 2145400400002 REACTION ((94-PU-240(0,F),PR,NU)/ 2145400400003 (92-U-235(N,F),PR,NU,,MXW)) 2145400400004 INC-SPECT Thermal neutron beam from GLEEP. 2145400400005 INC-SOURCE (REAC) For the thermal neutrons. 2145400400006 FACILITY (REAC,2UK HAR) Gleep for producing thermal neutrons. 2145400400007 ERR-ANALYS (ERR-T) .Two errors were always calculated, viz an 2145400400008 internal one and an external one. The biggest of them 2145400400009 was always taken. Total uncertainty includes: 2145400400010 (ERR-1) Uncertainty in efficiency, 2145400400011 (ERR-S) Uncertainty in value of neutrons detected per 2145400400012 counted fission event, 2145400400013 (ERR-3) loss of fission fragments below the bias, 2145400400014 (ERR-4) effect of electrical pickup, 2145400400015 (ERR-5) anisotropy in efficiency, 2145400400016 (ERR-6) correction for neutrons captured after the gate2145400400017 STATUS (TABLE) Data from Tbl.III of 65SALZBURG,2,25,1965 2145400400018 HISTORY (20120917A) SD: Data were added. 2145400400019 ENDBIB 17 0 2145400400020 COMMON 6 3 2145400400021 ERR-1 ERR-S ERR-3 ERR-4 ERR-5 ERR-6 2145400400022 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2145400400023 0.31 0.40 0.3 0.03 0.20 0.10 2145400400024 ENDCOMMON 3 0 2145400400025 DATA 3 1 2145400400026 EN-DUMMY DATA ERR-T 2145400400027 EV NO-DIM NO-DIM 2145400400028 2.5300E-02 0.888 0.005 2145400400029 ENDDATA 3 0 2145400400030 ENDSUBENT 29 0 2145400499999 SUBENT 21454005 20120917 22342145400500001 BIB 7 15 2145400500002 REACTION ((98-CF-252(0,F),PR,NU)/(92-U-235(N,F),PR,NU,,MXW)) 2145400500003 INC-SPECT Thermal neutron beam from GLEEP. 2145400500004 INC-SOURCE (REAC) For the thermal neutrons. 2145400500005 FACILITY (REAC,2UK HAR) Gleep for producing thermal neutrons. 2145400500006 ERR-ANALYS (ERR-T) .Two errors were always calculated, viz an 2145400500007 internal one and an external one. The biggest of them 2145400500008 was always taken. Total uncertainty includes: 2145400500009 (ERR-1) Uncertainty in efficiency, 2145400500010 (ERR-S) Uncertainty in value of neutrons detected per 2145400500011 counted fission event, 2145400500012 (ERR-4) effect of electrical pickup, 2145400500013 (ERR-5) anisotropy in efficiency, 2145400500014 (ERR-6) correction for neutrons captured after the gate2145400500015 STATUS (TABLE) Data from Tbl.III of 65SALZBURG,2,25,1965 2145400500016 HISTORY (20120917A) SD: Data were added. 2145400500017 ENDBIB 15 0 2145400500018 COMMON 5 3 2145400500019 ERR-1 ERR-S ERR-4 ERR-5 ERR-6 2145400500020 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2145400500021 0.31 0.11 0.03 0.20 0.10 2145400500022 ENDCOMMON 3 0 2145400500023 DATA 3 1 2145400500024 EN-DUMMY DATA ERR-T 2145400500025 EV NO-DIM NO-DIM 2145400500026 2.5300E-02 1.557 0.007 2145400500027 ENDDATA 3 0 2145400500028 ENDSUBENT 27 0 2145400599999 SUBENT 21454006 20160721 22522145400600001 BIB 6 17 2145400600002 REACTION ((94-PU-241(N,F),PR,NU,,MXW)/ 2145400600003 (92-U-235(N,F),PR,NU,,MXW)) 2145400600004 INC-SPECT Thermal neutron beam from GLEEP. 2145400600005 FACILITY (REAC,2UK HAR) Gleep for producing thermal neutrons. 2145400600006 ERR-ANALYS (ERR-T) .Two errors were always calculated, viz an 2145400600007 internal one and an external one. The biggest of them 2145400600008 was always taken. Total uncertainty includes: 2145400600009 (ERR-1) Uncertainty in efficiency, 2145400600010 (ERR-S) Uncertainty in value of neutrons detected per 2145400600011 counted fission event, 2145400600012 (ERR-3) loss of fission fragments below the bias, 2145400600013 (ERR-4) effect of electrical pickup, 2145400600014 (ERR-5) anisotropy in efficiency, 2145400600015 (ERR-6) correction for neutrons captured after the gate2145400600016 STATUS (TABLE) Data from Tbl.III of 65SALZBURG,2,25,1965 2145400600017 HISTORY (20160721A) SD: The '//' -> '/' in REACTION code 2145400600018 following EXFOR rules. 2145400600019 ENDBIB 17 0 2145400600020 COMMON 6 3 2145400600021 ERR-1 ERR-S ERR-3 ERR-4 ERR-5 ERR-6 2145400600022 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2145400600023 0.31 0.40 0.3 0.03 0.20 0.10 2145400600024 ENDCOMMON 3 0 2145400600025 DATA 3 1 2145400600026 EN-DUMMY DATA ERR-T 2145400600027 EV NO-DIM NO-DIM 2145400600028 2.5300E-02 1.2100E+00 1.1000E-02 2145400600029 ENDDATA 3 0 2145400600030 ENDSUBENT 29 0 2145400699999 SUBENT 21454007 20120917 22342145400700001 BIB 5 16 2145400700002 REACTION ((92-U-235(N,F),PR,NU)/(98-CF-252(0,F),PR,NU)) 2145400700003 FACILITY (VDG,2UK HAR) 5 MeV Van de Graaff. 2145400700004 INC-SOURCE (P-T) Proton-tritium reaction and 2145400700005 (P-LI7) proton-lithium reaction for fast neutrons. 2145400700006 ERR-ANALYS (ERR-T) .Two errors were always calculated, viz an 2145400700007 internal one and an external one. The biggest of them 2145400700008 was always taken. Total uncertainty includes: 2145400700009 (ERR-1) Uncertainty in efficiency, 2145400700010 (ERR-S) Uncertainty in value of neutrons detected per 2145400700011 counted fission event, 2145400700012 (ERR-3) loss of fission fragments below the bias, 2145400700013 (ERR-4) effect of electrical pickup, 2145400700014 (ERR-5) anisotropy in efficiency, 2145400700015 (ERR-6) correction for neutrons captured after the gate2145400700016 (ERR-7) Van de Graaff beam modulation 2145400700017 STATUS (TABLE) Data from Tbl.IV of 65SALZBURG,2,25,1965 2145400700018 ENDBIB 16 0 2145400700019 COMMON 7 6 2145400700020 ERR-1 ERR-S ERR-3 ERR-4 ERR-5 ERR-6 2145400700021 ERR-7 2145400700022 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2145400700023 PER-CENT 2145400700024 0.31 0.40 0.3 0.03 0.20 0.10 2145400700025 0.05 2145400700026 ENDCOMMON 6 0 2145400700027 DATA 4 9 2145400700028 EN EN-RSL DATA ERR-T 2145400700029 MEV MEV NO-DIM NO-DIM 2145400700030 1.0100E-01 6.0000E-02 6.5660E-01 1.2600E-02 2145400700031 5.1400E-01 5.4000E-02 6.6790E-01 1.1800E-02 2145400700032 5.7100E-01 1.5600E-01 6.6480E-01 6.9000E-03 2145400700033 5.7200E-01 1.5000E-02 6.6250E-01 7.7000E-03 2145400700034 6.0400E-01 5.3000E-02 6.6600E-01 6.0000E-03 2145400700035 9.4600E-01 1.2800E-01 6.6950E-01 5.2000E-03 2145400700036 1.4970E+00 1.0900E-01 6.8510E-01 5.2000E-03 2145400700037 2.1230E+00 9.5000E-02 7.0920E-01 5.7000E-03 2145400700038 2.5720E+00 8.5000E-02 7.2090E-01 6.3000E-03 2145400700039 ENDDATA 11 0 2145400700040 ENDSUBENT 39 0 2145400799999 SUBENT 21454008 20120917 22342145400800001 BIB 6 17 2145400800002 REACTION (92-U-235(N,F),PR,NU,,MXW) 2145400800003 INC-SPECT Thermal neutron beam from GLEEP. 2145400800004 METHOD Obtained with pile efficiency measured by 2145400800005 D(gamma,n)H reaction 2145400800006 FACILITY (REAC,2UK HAR) Gleep for producing thermal neutrons. 2145400800007 ERR-ANALYS (ERR-T) .Two errors were always calculated, viz an 2145400800008 internal one and an external one. The biggest of them 2145400800009 was always taken. Total uncertainty includes: 2145400800010 (ERR-1) Uncertainty in efficiency, 2145400800011 (ERR-S) Uncertainty in value of neutrons detected per 2145400800012 counted fission event, 2145400800013 (ERR-3) loss of fission fragments below the bias, 2145400800014 (ERR-4) effect of electrical pickup, 2145400800015 (ERR-5) anisotropy in efficiency, 2145400800016 (ERR-6) correction for neutrons captured after the gate2145400800017 STATUS (TABLE) Data from the text on p.33 of 65SALZBURG,2,25 2145400800018 The same data is given at 66PARIS,1,307. 2145400800019 ENDBIB 17 0 2145400800020 COMMON 6 3 2145400800021 ERR-1 ERR-S ERR-3 ERR-4 ERR-5 ERR-6 2145400800022 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2145400800023 0.31 0.40 0.3 0.03 0.20 0.10 2145400800024 ENDCOMMON 3 0 2145400800025 DATA 3 1 2145400800026 EN-DUMMY DATA ERR-T 2145400800027 EV PRT/FIS PRT/FIS 2145400800028 2.5300E-02 2.3850E+00 1.5000E-02 2145400800029 ENDDATA 3 0 2145400800030 ENDSUBENT 29 0 2145400899999 SUBENT 21454009 20120917 22342145400900001 BIB 4 14 2145400900002 REACTION (98-CF-252(0,F),PR,NU) 2145400900003 METHOD Obtained with pile efficiency measured by 2145400900004 D(gamma,n)H reaction 2145400900005 ERR-ANALYS (ERR-T) .Two errors were always calculated, viz an 2145400900006 internal one and an external one. The biggest of them 2145400900007 was always taken. Total uncertainty includes: 2145400900008 (ERR-1) Uncertainty in efficiency, 2145400900009 (ERR-S) Uncertainty in value of neutrons detected per 2145400900010 counted fission event, 2145400900011 (ERR-4) effect of electrical pickup, 2145400900012 (ERR-5) anisotropy in efficiency, 2145400900013 (ERR-6) correction for neutrons captured after the gate2145400900014 STATUS (TABLE) Data from the text on p.33 of 65SALZBURG,2,25 2145400900015 The same data is given at 66PARIS,1,307. 2145400900016 ENDBIB 14 0 2145400900017 COMMON 5 3 2145400900018 ERR-1 ERR-S ERR-4 ERR-5 ERR-6 2145400900019 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2145400900020 0.31 0.11 0.03 0.20 0.10 2145400900021 ENDCOMMON 3 0 2145400900022 DATA 2 1 2145400900023 DATA ERR-T 2145400900024 PRT/FIS PRT/FIS 2145400900025 3.7130E+00 1.5000E-02 2145400900026 ENDDATA 3 0 2145400900027 ENDSUBENT 26 0 2145400999999 SUBENT 21454010 20120917 22342145401000001 BIB 5 15 2145401000002 REACTION (98-CF-252(0,F),PR,NU) 2145401000003 METHOD .Data obtained with a measurement where the pile 2145401000004 efficiency was determined with standard sources. 2145401000005 ERR-ANALYS (ERR-T) .Two errors were always calculated, viz an 2145401000006 internal one and an external one. The biggest of them 2145401000007 was always taken. Total uncertainty includes: 2145401000008 (ERR-1) Uncertainty in efficiency, 2145401000009 (ERR-S) Uncertainty in value of neutrons detected per 2145401000010 counted fission event, 2145401000011 (ERR-4) effect of electrical pickup, 2145401000012 (ERR-5) anisotropy in efficiency, 2145401000013 (ERR-6) correction for neutrons captured after the gate2145401000014 STATUS (TABLE) Data from Tbl.III of 66PARIS,1,307,1966 2145401000015 HISTORY (19800331A) G.C., Added data set. 2145401000016 (19800429E) 2145401000017 ENDBIB 15 0 2145401000018 COMMON 5 3 2145401000019 ERR-1 ERR-S ERR-4 ERR-5 ERR-6 2145401000020 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2145401000021 0.31 0.11 0.03 0.20 0.10 2145401000022 ENDCOMMON 3 0 2145401000023 DATA 2 1 2145401000024 DATA ERR-T 2145401000025 PRT/FIS PRT/FIS 2145401000026 3.7000E+00 3.1000E-02 2145401000027 ENDDATA 3 0 2145401000028 ENDSUBENT 27 0 2145401099999 SUBENT 21454011 20120917 22342145401100001 BIB 7 18 2145401100002 REACTION (92-U-235(N,F),PR,NU,,MXW) 2145401100003 INC-SPECT Thermal neutron beam from GLEEP. 2145401100004 METHOD .Data obtained with a measurement where the pile 2145401100005 efficiency was determined with standard sources. 2145401100006 FACILITY (REAC,2UK HAR) Gleep for producing thermal neutrons. 2145401100007 ERR-ANALYS (ERR-T) .Two errors were always calculated, viz an 2145401100008 internal one and an external one. The biggest of them 2145401100009 was always taken. Total uncertainty includes: 2145401100010 (ERR-1) Uncertainty in efficiency, 2145401100011 (ERR-S) Uncertainty in value of neutrons detected per 2145401100012 counted fission event, 2145401100013 (ERR-3) loss of fission fragments below the bias, 2145401100014 (ERR-4) effect of electrical pickup, 2145401100015 (ERR-5) anisotropy in efficiency, 2145401100016 (ERR-6) correction for neutrons captured after the gate2145401100017 STATUS (TABLE) Data from Tbl.III of 66PARIS,1,307,1966 2145401100018 HISTORY (19800331A) Added data set. 2145401100019 (19800429E) 2145401100020 ENDBIB 18 0 2145401100021 COMMON 6 3 2145401100022 ERR-1 ERR-S ERR-3 ERR-4 ERR-5 ERR-6 2145401100023 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2145401100024 0.31 0.40 0.3 0.03 0.20 0.10 2145401100025 ENDCOMMON 3 0 2145401100026 DATA 3 1 2145401100027 EN-DUMMY DATA ERR-T 2145401100028 EV PRT/FIS PRT/FIS 2145401100029 2.5300E-02 2.3770E+00 2.3000E-02 2145401100030 ENDDATA 3 0 2145401100031 ENDSUBENT 30 0 2145401199999 ENDENTRY 11 0 2145499999999