ENTRY D0047 20060726 D048D004700000001 SUBENT D0047001 20060726 D048D004700100001 BIB 12 49 D004700100002 TITLE Measurements of thick target (a,n) yields from light D004700100003 elements. -experiment- D004700100004 AUTHOR (D.West,A.C.Sherwood) D004700100005 INSTITUTE (2UK HAR) D004700100006 REFERENCE (J,ANE,9,551,1982) D004700100007 (R,AERE-R-10502,198206) D004700100008 FACILITY (VDGT,2UK HAR) D004700100009 incident alpha-particle energy range of 3.6 to 10 MeV. D004700100010 DETECTOR (PROPC) 1m long thin-walled stainless steel D004700100011 proportional gas counters(9) containing He-3(52 torr) D004700100012 argon-methane(734 torr). they are inserted into D004700100013 polyethylene moderator block. D004700100014 PART-DET (N) D004700100015 METHOD (SITA,EXTB) D004700100016 Rutherford scattering from a thin gold foil mounted onD004700100017 a carbon film was used to monitor the He-4 energy. D004700100018 .for alpha-energy calibration, Cm-244 alpha source D004700100019 (5.805 MeV) D004700100020 Am-241/Be neutrons measured absolutely at N.P.L. by D004700100021 the Mn-So(4) bath technique. D004700100022 ERR-ANALYS (DATA-ERR) accuracy achieved is between 1 and 2%.(standD004700100023 deviation). D004700100024 --source of error -- magnitude(stand.dev. D004700100025 systematic errors in percent) D004700100026 .neutron calib.source intensity 0.47 D004700100027 .neutron leakage and self absorption D004700100028 with the calibration source 0.3 D004700100029 .fast neutron absorp. in c with the D004700100030 calibration source 0.3 D004700100031 .current integrator 0.4 D004700100032 other errors D004700100033 .method of neutron density integrat'n 0.5 D004700100034 .beam pipe absorption 0.65 D004700100035 .indiv.neutron calibrat'n including D004700100036 intercalibrat'n of channels 0.07 D004700100037 .energy determinat'n +-3keV depending on D004700100038 the slope of yield curve 0.1 - 1.5 D004700100039 .statistical accuracy of counting 0.1 - 3.4 D004700100040 .deadtime correct'n used as an error 0 - 0.7 D004700100041 .error from neutron leakage assessed from D004700100042 the migration length of neutrons from the D004700100043 particular target in relation to that D004700100044 computed for am-be 0 - 1.6 D004700100045 detail of error analys is given in the text. D004700100046 CORRECTION neutron background, neutron absorption in the beam pipeD004700100047 and faraday cup and others were carefully determined. D004700100048 STATUS data taken from table of AERE-R-10502, june 1982. D004700100049 HISTORY (19831129C) KO. D004700100050 (20060726A) BIB section upgrated. Add ref. D004700100051 ENDBIB 49 0 D004700100052 NOCOMMON 0 0 D004700100053 ENDSUBENT 52 0 D004700199999 SUBENT D0047002 20060726 D048D004700200001 BIB 2 5 D004700200002 REACTION (4-BE-9(A,N)6-C-12,,PY,,TT) neutrons/alpha particle D004700200003 SAMPLE 99.8 percent purity. D004700200004 samples were examined for neutron producing impuritiesD004700200005 by examining each at beam energy of 7.5MeV with a D004700200006 large (71milli-litre) Ge-Li detector. D004700200007 ENDBIB 5 0 D004700200008 COMMON 1 3 D004700200009 EN-ERR D004700200010 KEV D004700200011 3. D004700200012 ENDCOMMON 3 0 D004700200013 DATA 3 20 D004700200014 EN DATA DATA-ERR D004700200015 MEV PRT/INC PER-CENT D004700200016 4.004 2.286E-5 2.0 D004700200017 4.406 3.447E-5 1.9 D004700200018 4.601 4.105E-5 1.9 D004700200019 4.802 4.811E-5 1.7 D004700200020 5.022 5.678E-5 1.6 D004700200021 5.199 6.475E-5 1.6 D004700200022 5.400 7.499E-5 1.5 D004700200023 5.596 8.594E-5 1.6 D004700200024 5.800 9.814E-5 1.4 D004700200025 5.997 1.095E-4 1.4 D004700200026 6.189 1.204E-4 1.4 D004700200027 6.389 1.323E-4 1.6 D004700200028 6.793 1.557E-4 1.2 D004700200029 7.187 1.816E-4 1.4 D004700200030 7.590 2.091E-4 1.2 D004700200031 7.990 2.412E-4 1.2 D004700200032 8.484 2.807E-4 1.2 D004700200033 8.983 3.274E-4 1.3 D004700200034 9.478 3.777E-4 1.2 D004700200035 9.959 4.280E-4 1.3 D004700200036 ENDDATA 22 0 D004700200037 ENDSUBENT 36 0 D004700299999 SUBENT D0047003 20060726 D048D004700300001 BIB 2 5 D004700300002 REACTION (4-BE-OXI(A,N),,PY,,TT) neutrons/alpha particle D004700300003 SAMPLE purity unspecified. D004700300004 .samples were examined for neutron producing impuritiesD004700300005 by examining each at beam energy of 7.5MeV with a D004700300006 large ( 71 milli-litre) Ge-Li detector. D004700300007 ENDBIB 5 0 D004700300008 COMMON 1 3 D004700300009 EN-ERR D004700300010 KEV D004700300011 3. D004700300012 ENDCOMMON 3 0 D004700300013 DATA 3 20 D004700300014 EN DATA DATA-ERR D004700300015 MEV PRT/INC PER-CENT D004700300016 4.003 8.084E-6 1.9 D004700300017 4.407 1.221E-5 1.8 D004700300018 4.600 1.499E-5 1.7 D004700300019 4.801 1.774E-5 1.7 D004700300020 5.022 2.036E-5 1.6 D004700300021 5.199 2.313E-5 1.6 D004700300022 5.400 2.740E-5 1.5 D004700300023 5.596 3.102E-5 1.5 D004700300024 5.800 3.612E-5 1.4 D004700300025 5.997 3.949E-5 1.5 D004700300026 6.188 4.439E-5 1.3 D004700300027 6.390 4.825E-5 1.3 D004700300028 6.794 5.774E-5 1.4 D004700300029 7.185 6.676E-5 1.2 D004700300030 7.588 7.783E-5 1.2 D004700300031 7.989 8.895E-5 1.2 D004700300032 8.483 1.041E-5 1.2 D004700300033 8.984 1.214E-4 1.2 D004700300034 9.476 1.395E-4 1.1 D004700300035 9.960 1.581E-4 1.2 D004700300036 ENDDATA 22 0 D004700300037 ENDSUBENT 36 0 D004700399999 SUBENT D0047004 20060726 D048D004700400001 BIB 2 5 D004700400002 REACTION (5-B-CMP(A,N),,PY,,TT) neutrons/alpha particle D004700400003 SAMPLE boron nitride, bn. purity unspecified. D004700400004 .samples were examined for neutron producing impuritiesD004700400005 by examining each at beam energy of 7.5MeV with a D004700400006 large ( 71 milli-litre) Ge-Li detector. D004700400007 ENDBIB 5 0 D004700400008 COMMON 1 3 D004700400009 EN-ERR D004700400010 KEV D004700400011 3. D004700400012 ENDCOMMON 3 0 D004700400013 DATA 3 11 D004700400014 EN DATA DATA-ERR D004700400015 MEV PRT/INC PER-CENT D004700400016 4.000 2.880E-6 1.2 D004700400017 4.407 3.852E-6 1.2 D004700400018 4.800 5.464E-6 1.2 D004700400019 5.022 6.371E-6 1.2 D004700400020 5.200 7.486E-6 1.2 D004700400021 5.399 8.607E-6 1.2 D004700400022 5.596 9.369E-6 1.2 D004700400023 5.800 1.051E-5 1.2 D004700400024 5.997 1.173E-5 1.2 D004700400025 6.391 1.380E-5 1.2 D004700400026 6.793 1.504E-5 1.2 D004700400027 ENDDATA 13 0 D004700400028 ENDSUBENT 27 0 D004700499999 SUBENT D0047005 20060726 D048D004700500001 BIB 2 4 D004700500002 REACTION (6-C-12(A,N)8-O-15,,PY,,TT)neutrons/alpha particle D004700500003 SAMPLE .samples were examined for neutron producing impuritiesD004700500004 by examining each at beam energy of 7.5MeV with a D004700500005 large ( 71 milli-litre) Ge-Li detector. D004700500006 ENDBIB 4 0 D004700500007 COMMON 1 3 D004700500008 EN-ERR D004700500009 KEV D004700500010 3. D004700500011 ENDCOMMON 3 0 D004700500012 DATA 3 26 D004700500013 EN DATA DATA-ERR D004700500014 MEV PRT/INC PER-CENT D004700500015 3.611 4.243E-8 1.4 D004700500016 4.013 4.335E-8 1.4 D004700500017 4.194 4.480E-8 1.4 D004700500018 4.422 4.834E-8 1.4 D004700500019 4.599 5.138E-8 1.4 D004700500020 4.798 5.540E-8 1.5 D004700500021 5.005 6.498E-8 1.6 D004700500022 5.211 8.278E-8 1.5 D004700500023 5.389 1.002E-7 1.4 D004700500024 5.636 1.248E-7 1.3 D004700500025 5.803 1.414E-7 1.3 D004700500026 5.987 1.724E-7 1.3 D004700500027 6.191 2.083E-7 1.3 D004700500028 6.406 2.423E-7 1.2 D004700500029 6.616 2.707E-7 1.2 D004700500030 6.831 3.031E-7 1.2 D004700500031 6.982 3.387E-7 1.2 D004700500032 7.181 3.864E-7 1.2 D004700500033 7.378 4.244E-7 1.2 D004700500034 7.475 4.480E-7 1.2 D004700500035 7.989 6.064E-7 1.2 D004700500036 8.467 7.313E-7 1.2 D004700500037 8.968 8.627E-7 1.1 D004700500038 9.382 9.547E-7 1.1 D004700500039 9.468 9.912E-7 1.2 D004700500040 9.961 1.131E-6 1.2 D004700500041 ENDDATA 28 0 D004700500042 ENDSUBENT 41 0 D004700599999 SUBENT D0047006 20060726 D048D004700600001 BIB 2 6 D004700600002 REACTION ((92-U-CMP(A,N),,PY,,TT)= D004700600003 (6-C-CMP(A,N),,PY,,TT)) neutrons/alpha-particle D004700600004 SAMPLE uranium carbide, uc. laboratory sample. D004700600005 .samples were examined for neutron producing impuritiesD004700600006 by examining each at beam energy of 7.5MeV with a D004700600007 large ( 71 milli-litre) Ge-Li detector. D004700600008 ENDBIB 6 0 D004700600009 COMMON 1 3 D004700600010 EN-ERR D004700600011 KEV D004700600012 3. D004700600013 ENDCOMMON 3 0 D004700600014 DATA 3 18 D004700600015 EN DATA DATA-ERR D004700600016 MEV PRT/INC PER-CENT D004700600017 3.796 7.183E-9 1.7 D004700600018 4.185 7.733E-9 1.7 D004700600019 4.602 8.787E-9 1.4 D004700600020 4.779 9.475E-9 1.4 D004700600021 4.997 1.101E-8 1.6 D004700600022 5.186 1.349E-8 1.5 D004700600023 5.413 1.723E-8 1.5 D004700600024 5.597 2.027E-8 1.4 D004700600025 5.791 2.263E-8 1.3 D004700600026 5.982 2.742E-8 1.3 D004700600027 6.185 3.286E-8 1.2 D004700600028 6.590 4.241E-8 1.2 D004700600029 6.978 5.350E-8 1.2 D004700600030 7.490 7.210E-8 1.2 D004700600031 8.466 1.162E-7 1.1 D004700600032 9.381 1.541E-7 1.1 D004700600033 9.464 1.602E-7 1.1 D004700600034 9.957 1.850E-7 1.1 D004700600035 ENDDATA 20 0 D004700600036 ENDSUBENT 35 0 D004700699999 SUBENT D0047007 20060726 D048D004700700001 BIB 2 5 D004700700002 REACTION (92-U-OXI(A,N),,PY,,TT) neutrons/alpha particle D004700700003 SAMPLE uranium oxide, U-O(2).''laboratory grade sample.'' D004700700004 .samples were examined for neutron producing impuritiesD004700700005 by examining each at beam energy of 7.5MeV with a D004700700006 large ( 71 milli-litre) Ge-Li detector. D004700700007 ENDBIB 5 0 D004700700008 COMMON 1 3 D004700700009 EN-ERR D004700700010 KEV D004700700011 3. D004700700012 ENDCOMMON 3 0 D004700700013 DATA 3 14 D004700700014 EN DATA DATA-ERR D004700700015 MEV PRT/INC PER-CENT D004700700016 4.194 6.694E-9 1.4 D004700700017 4.602 1.153E-8 1.2 D004700700018 5.004 1.556E-8 1.2 D004700700019 5.389 2.010E-8 1.2 D004700700020 5.785 2.622E-8 1.2 D004700700021 5.999 3.052E-8 1.2 D004700700022 6.188 3.501E-8 1.2 D004700700023 6.591 4.206E-8 1.2 D004700700024 6.987 5.115E-8 1.2 D004700700025 7.989 7.518E-8 1.2 D004700700026 8.465 8.866E-8 1.1 D004700700027 8.968 1.033E-7 1.2 D004700700028 9.381 1.190E-7 1.2 D004700700029 9.961 1.392E-7 1.2 D004700700030 ENDDATA 16 0 D004700700031 ENDSUBENT 30 0 D004700799999 SUBENT D0047008 20060726 D048D004700800001 BIB 2 6 D004700800002 REACTION (92-U-OXI(A,N),,PY,,TT) neutrons/alpha particle D004700800003 SAMPLE uranium oxide, U-O(2). ''production grade sample.'' D004700800004 fuel pellet. D004700800005 .samples were examined for neutron producing impuritiesD004700800006 by examining each at beam energy of 7.5MeV with a D004700800007 large ( 71 milli-litre) Ge-Li detector. D004700800008 ENDBIB 6 0 D004700800009 COMMON 1 3 D004700800010 EN-ERR D004700800011 KEV D004700800012 3. D004700800013 ENDCOMMON 3 0 D004700800014 DATA 3 10 D004700800015 EN DATA DATA-ERR D004700800016 MEV PRT/INC PER-CENT D004700800017 3.797 3.947E-9 1.6 D004700800018 4.781 1.352E-8 1.2 D004700800019 4.997 1.581E-8 1.2 D004700800020 5.187 1.773E-8 1.2 D004700800021 5.597 2.379E-8 1.2 D004700800022 5.791 2.654E-8 1.2 D004700800023 5.981 3.024E-8 1.2 D004700800024 7.488 6.273E-8 1.2 D004700800025 9.464 1.167E-7 1.2 D004700800026 9.957 1.346E-7 1.2 D004700800027 ENDDATA 12 0 D004700800028 ENDSUBENT 27 0 D004700899999 SUBENT D0047009 20060726 D048D004700900001 BIB 2 5 D004700900002 REACTION (12-MG-0(A,N),,PY,,TT) neutrons/alpha particle D004700900003 SAMPLE 99.9 percent purity. D004700900004 .samples were examined for neutron producing impuritiesD004700900005 by examining each at beam energy of 7.5MeV with a D004700900006 large ( 71 milli-litre) Ge-Li detector. D004700900007 ENDBIB 5 0 D004700900008 COMMON 1 3 D004700900009 EN-ERR D004700900010 KEV D004700900011 3. D004700900012 ENDCOMMON 3 0 D004700900013 DATA 3 25 D004700900014 EN DATA DATA-ERR D004700900015 MEV PRT/INC PER-CENT D004700900016 3.611 2.569E-8 1.6 D004700900017 4.013 8.488E-8 1.4 D004700900018 4.192 1.245E-7 1.4 D004700900019 4.423 2.305E-7 1.6 D004700900020 4.598 3.740E-7 1.3 D004700900021 4.818 5.211E-7 1.3 D004700900022 5.005 7.088E-7 1.2 D004700900023 5.211 9.003E-7 1.2 D004700900024 5.389 1.162E-6 1.3 D004700900025 5.632 1.624E-6 1.2 D004700900026 5.798 1.923E-6 1.2 D004700900027 5.988 2.269E-6 1.2 D004700900028 6.185 2.803E-6 1.2 D004700900029 6.402 3.307E-6 1.2 D004700900030 6.614 3.823E-6 1.2 D004700900031 6.826 4.523E-6 1.2 D004700900032 6.985 4.969E-6 1.2 D004700900033 7.180 5.639E-6 1.2 D004700900034 7.372 6.412E-6 1.2 D004700900035 7.474 6.782E-6 1.2 D004700900036 7.975 9.037E-6 1.2 D004700900037 8.467 1.140E-5 1.2 D004700900038 8.963 1.427E-5 1.2 D004700900039 9.383 1.675E-5 1.2 D004700900040 9.954 2.063E-5 1.2 D004700900041 ENDDATA 27 0 D004700900042 ENDSUBENT 41 0 D004700999999 SUBENT D0047010 20060726 D048D004701000001 BIB 2 5 D004701000002 REACTION (13-AL-27(A,N)15-P-30,,PY,,TT) neutrons/a-particle D004701000003 SAMPLE 99.99 percent purity. D004701000004 .samples were examined for neutron producing impuritiesD004701000005 by examining each at beam energy of 7.5MeV with a D004701000006 large ( 71 milli-litre) Ge-Li detector. D004701000007 ENDBIB 5 0 D004701000008 COMMON 1 3 D004701000009 EN-ERR D004701000010 KEV D004701000011 3. D004701000012 ENDCOMMON 3 0 D004701000013 DATA 3 25 D004701000014 EN DATA DATA-ERR D004701000015 MEV PRT/INC PER-CENT D004701000016 3.611 2.033E-9 3.2 D004701000017 4.013 1.748E-8 1.9 D004701000018 4.193 3.382E-8 1.6 D004701000019 4.423 6.598E-8 1.5 D004701000020 4.598 1.066E-7 1.5 D004701000021 4.817 1.925E-7 1.3 D004701000022 5.004 2.836E-7 1.3 D004701000023 5.211 4.247E-7 1.3 D004701000024 5.388 6.133E-7 1.3 D004701000025 5.630 9.233E-7 1.2 D004701000026 5.799 1.149E-6 1.2 D004701000027 5.988 1.520E-6 1.2 D004701000028 6.184 2.020E-6 1.2 D004701000029 6.403 2.663E-6 1.2 D004701000030 6.615 3.456E-6 1.2 D004701000031 6.827 4.252E-6 1.2 D004701000032 6.985 4.930E-6 1.2 D004701000033 7.179 5.903E-6 1.2 D004701000034 7.373 6.976E-6 1.2 D004701000035 7.474 7.557E-6 1.2 D004701000036 7.976 1.081E-5 1.2 D004701000037 8.466 1.473E-5 1.1 D004701000038 8.963 1.926E-5 1.1 D004701000039 9.381 2.361E-5 1.2 D004701000040 9.955 3.079E-5 1.1 D004701000041 ENDDATA 27 0 D004701000042 ENDSUBENT 41 0 D004701099999 SUBENT D0047011 20060726 D048D004701100001 BIB 2 5 D004701100002 REACTION (14-SI-0(A,N),,PY,,TT) neutrons/alpha-particle D004701100003 SAMPLE ''single crystal'', semi-conductor grade. D004701100004 .samples were examined for neutron producing impuritiesD004701100005 by examining each at beam energy of 7.5MeV with a D004701100006 large ( 71 milli-litre) Ge-Li detector. D004701100007 ENDBIB 5 0 D004701100008 COMMON 1 3 D004701100009 EN-ERR D004701100010 KEV D004701100011 3. D004701100012 ENDCOMMON 3 0 D004701100013 DATA 3 20 D004701100014 EN DATA DATA-ERR D004701100015 MEV PRT/INC PER-CENT D004701100016 3.611 6.511E-1 3.9 D004701100017 4.013 4.128E-9 2.0 D004701100018 4.194 7.070E-9 1.6 D004701100019 4.422 1.311E-8 1.4 D004701100020 4.818 3.645E-8 1.5 D004701100021 5.004 5.690E-8 1.2 D004701100022 5.211 7.757E-8 1.2 D004701100023 5.390 1.042E-7 1.2 D004701100024 5.635 1.522E-7 1.2 D004701100025 5.785 1.871E-7 1.2 D004701100026 5.995 2.490E-7 1.2 D004701100027 6.191 3.072E-7 1.2 D004701100028 6.404 3.749E-7 1.2 D004701100029 6.592 4.524E-7 1.2 D004701100030 6.830 5.640E-7 1.2 D004701100031 6.986 6.466E-7 1.2 D004701100032 7.378 8.629E-7 1.2 D004701100033 7.975 1.314E-6 1.1 D004701100034 8.968 2.334E-6 1.2 D004701100035 9.964 3.652E-6 1.2 D004701100036 ENDDATA 22 0 D004701100037 ENDSUBENT 36 0 D004701199999 SUBENT D0047012 20060726 D048D004701200001 BIB 2 5 D004701200002 REACTION (14-SI-0(A,N),,PY,,TT) neutrons/alpha-particle D004701200003 SAMPLE ''polycrystalline''. purity unspecified. D004701200004 .samples were examined for neutron producing impuritiesD004701200005 by examining each at beam energy of 7.5MeV with a D004701200006 large ( 71 milli-litre) Ge-Li detector. D004701200007 ENDBIB 5 0 D004701200008 COMMON 1 3 D004701200009 EN-ERR D004701200010 KEV D004701200011 3. D004701200012 ENDCOMMON 3 0 D004701200013 DATA 3 5 D004701200014 EN DATA DATA-ERR D004701200015 MEV PRT/INC PER-CENT D004701200016 4.602 1.993E-8 1.5 D004701200017 6.186 3.002E-7 1.2 D004701200018 6.976 6.359E-7 1.2 D004701200019 8.464 1.770E-6 1.1 D004701200020 9.381 2.807E-6 1.1 D004701200021 ENDDATA 7 0 D004701200022 ENDSUBENT 21 0 D004701299999 SUBENT D0047013 20060726 D048D004701300001 BIB 2 5 D004701300002 REACTION (26-FE-0(A,N),,PY,,TT) neutrons/alpha-particle D004701300003 SAMPLE 99.9 percent purity. D004701300004 .samples were examined for neutron producing impuritiesD004701300005 by examining each at beam energy of 7.5MeV with a D004701300006 large ( 71 milli-litre) Ge-Li detector. D004701300007 ENDBIB 5 0 D004701300008 COMMON 1 3 D004701300009 EN-ERR D004701300010 KEV D004701300011 3. D004701300012 ENDCOMMON 3 0 D004701300013 DATA 3 16 D004701300014 EN DATA DATA-ERR D004701300015 MEV PRT/INC PER-CENT D004701300016 4.603 1.558E-10 3.7 D004701300017 5.004 2.054E-10 4.4 D004701300018 5.389 2.813E-10 3.0 D004701300019 5.633 7.515E-10 4.1 D004701300020 5.802 2.105E-9 2.0 D004701300021 6.189 8.208E-9 1.7 D004701300022 6.403 1.631E-8 1.5 D004701300023 6.591 2.673E-8 1.6 D004701300024 6.830 5.663E-8 1.5 D004701300025 6.987 8.675E-8 1.5 D004701300026 7.378 2.397E-7 1.3 D004701300027 7.976 7.336E-7 1.2 D004701300028 8.464 1.534E-6 1.2 D004701300029 8.969 3.017E-6 1.2 D004701300030 9.381 5.012E-6 1.2 D004701300031 9.961 8.939E-6 1.2 D004701300032 ENDDATA 18 0 D004701300033 ENDSUBENT 32 0 D004701399999 SUBENT D0047014 20060726 D048D004701400001 BIB 2 5 D004701400002 REACTION (26-FE-0(A,N),,PY,,TT) neutrons/alpha-particle D004701400003 SAMPLE ''stainless steel''. m316 specification. D004701400004 .samples were examined for neutron producing impuritiesD004701400005 by examining each at beam energy of 7.5MeV with a D004701400006 large (71 milli-litre) Ge-Li detector. D004701400007 ENDBIB 5 0 D004701400008 COMMON 1 3 D004701400009 EN-ERR D004701400010 KEV D004701400011 3. D004701400012 ENDCOMMON 3 0 D004701400013 DATA 3 11 D004701400014 EN DATA DATA-ERR D004701400015 MEV PRT/INC PER-CENT D004701400016 4.602 3.253E-10 2.6 D004701400017 4.996 7.018E-10 2.2 D004701400018 5.413 1.420E-9 1.8 D004701400019 5.792 4.530E-9 1.6 D004701400020 6.184 1.361E-8 1.5 D004701400021 6.590 4.032E-8 1.4 D004701400022 6.980 1.114E-7 1.4 D004701400023 7.490 3.445E-7 1.3 D004701400024 8.466 1.630E-6 1.2 D004701400025 9.382 5.065E-6 1.2 D004701400026 9.960 8.834E-6 1.2 D004701400027 ENDDATA 13 0 D004701400028 ENDSUBENT 27 0 D004701499999 ENDENTRY 14 0 D004799999999