ENTRY 30647 20100305 31443064700000001 SUBENT 30647001 20100305 31443064700100001 BIB 8 29 3064700100002 TITLE Measurements of the integral cross sections at 14 MeV 3064700100003 for reactions In-115(n,inl), Au-197(n,2n), Nb-93(n,2n),3064700100004 Al-27(n,a), Fe-56(n,p),U-235(n,F), Pu-239(n,F), 3064700100005 Np-237(n,F), U-238(n,F), Th-232(n,F) 3064700100006 AUTHOR (I.Garlea,Cr.Miron,D.Dobrea,C.Roth,T.Musat,H.N.Rosu) 3064700100007 INSTITUTE (3RUMPIT) The first five authors 3064700100008 (3RUMBUC) the last author 3064700100009 REFERENCE (R,INDC(ROM)-15,198301) Final report to the Internat. 3064700100010 Atomic Energy Agency on the Research Contract 3064700100011 TA/INT/1/18 3064700100012 MONITOR (92-U-235(N,F),,SIG) For average flux determination. No3064700100013 information about cross section value. 3064700100014 The characteristics of the fission chamber with 3064700100015 U-235 deposit are - total mass of deposit-96.60 3064700100016 microgramms (2.281 x 10**17 nuclei of U-235),the 3064700100017 isotopic composition U-235 - 99.89%, U-234 - 0.02%, 3064700100018 U-236 - 0.04%, U-238 - 0.07% 3064700100019 INC-SOURCE (D-T) Neutron generator Texas (model 9900) - 90.kV, 3064700100020 5*10**9 neutrons/sec 3064700100021 STATUS (TABLE) Data were taken from paper submitted at the 3064700100022 Nuclear Data Section as final report on the 3064700100023 Research Contract TA/INT/1/18 3064700100024 (SPSDD,30813001) 3064700100025 HISTORY (19830218C) VP. 3064700100026 (19850820A) DG.-This EXFOR entry is superseded by 308133064700100027 (19880307U) TMK-status code added 3064700100028 (19890310U) VOF.-Deleted duplicate lines in 3064700100029 sub. 7,8,9,10 3064700100030 (20100305A) SD:Updated to new date formats,lower case. 3064700100031 ENDBIB 29 0 3064700100032 COMMON 1 3 3064700100033 EN 3064700100034 MEV 3064700100035 14.75 3064700100036 ENDCOMMON 3 0 3064700100037 ENDSUBENT 36 0 3064700199999 SUBENT 30647002 20100305 31443064700200001 BIB 8 22 3064700200002 REACTION (49-IN-115(N,INL)49-IN-115-M,,SIG) 3064700200003 SAMPLE Pure metal foils 20.mm in diameter, 0.127 mm of 3064700200004 thickness, 0.259473 g by weight and 99.9959% 3064700200005 of purity (main impurities are Cu - 0.0002%, 3064700200006 Pb - 0.0018%, Sn - 0.0014% and Cd - 0.0007%) 3064700200007 METHOD (ACTIV) 3064700200008 DETECTOR (GELI) 100.cm**3, calibrated in absolute efficiency, 3064700200009 see I.Garlea,St.Cerc.Fizica,no.10,(1981) 3064700200010 (FISCH) For average flux determination 3064700200011 COMMENT Reaction rates were calculated by using the nuclear 3064700200012 constants from - Die Gamma-Linien der Radionuclide - 3064700200013 (1970). no further information about decay-data 3064700200014 STATUS (SPSDD,30813005) Data superseded by subentry 30813005 3064700200015 CORRECTION For gamma self-absorption and impurities 3064700200016 ERR-ANALYS (ERR-T) Total error. Partial components of the 3064700200017 error are: 3064700200018 (ERR-S,0.63,1.6) - statistics 0.63 - 1.6%, 3064700200019 (ERR-1,1.55,2.17) - calibration in absolute 3064700200020 efficiency 1.55 - 2.17%, 3064700200021 (ERR-2,0.5,1.2) - background subtraction 0.50 - 1.2%, 3064700200022 (ERR-3,2.13,2.5) - absolute flux 3064700200023 determination 2.13 - 2.50% 3064700200024 ENDBIB 22 0 3064700200025 NOCOMMON 0 0 3064700200026 NODATA 0 0 3064700200027 ENDSUBENT 26 0 3064700299999 SUBENT 30647003 20100305 31443064700300001 BIB 8 20 3064700300002 REACTION (79-AU-197(N,2N)79-AU-196,,SIG) 3064700300003 SAMPLE Pure metal foils 20.mm in diameter, 0.127 mm of 3064700300004 thickness, 0.722206 g by weight and 99.998% of purity 3064700300005 METHOD (ACTIV) 3064700300006 DETECTOR (GELI) 100.cm**3, calibrated in absolute efficiency, 3064700300007 see I.Garlea,St.Cerc.Fizica,no.10,(1981) 3064700300008 (FISCH) For average flux determination 3064700300009 COMMENT Reaction rates were calculated by using the nuclear 3064700300010 constants from - Die Gamma-Linien der Radionuclide - 3064700300011 (1970). no further information about decay-data 3064700300012 STATUS (SPSDD,30813006)Data superseded by subentry 30813006 3064700300013 CORRECTION For gamma self-absorption and impurities 3064700300014 ERR-ANALYS (ERR-T) Total error. Partial components of the 3064700300015 error are: 3064700300016 (ERR-S,0.63,1.6) - statistics 0.63 - 1.6%, 3064700300017 (ERR-1,1.55,2.17) - calibration in absolute 3064700300018 efficiency 1.55 - 2.17%, 3064700300019 (ERR-2,0.5,1.2) - background subtraction 0.50 - 1.2%, 3064700300020 (ERR-3,2.13,2.5) - absolute flux 3064700300021 determination 2.13 - 2.50% 3064700300022 ENDBIB 20 0 3064700300023 NOCOMMON 0 0 3064700300024 NODATA 0 0 3064700300025 ENDSUBENT 24 0 3064700399999 SUBENT 30647004 20100305 31443064700400001 BIB 8 24 3064700400002 REACTION (41-NB-93(N,2N)41-NB-92,,SIG) 3064700400003 SAMPLE Pure metal foils 15.mm in diameter, 1.mm of 3064700400004 thickness, 1.574339 g by weight and 99.837% 3064700400005 of purity (main impurities are Mo, Hf -0.01%, 3064700400006 Pb,Co,V,Cu,Sn,Cr,Al,Ca,Mn,Ni - 0.002%, H,Cd - 0.005%, 3064700400007 Ta - 0.075%, Fe, Zr - 0.005%, W - 0.013%, C-0.0024%, 3064700400008 0 - 0.0074%, n - 0.0049%, B - 0.0002% 3064700400009 METHOD (ACTIV) 3064700400010 DETECTOR (GELI) 100.cm**3, calibrated in absolute efficiency, 3064700400011 see I.Garlea,St.Cerc.Fizica,no.10,(1981) 3064700400012 (FISCH) For average flux determination 3064700400013 CORRECTION For gamma self-absorption and impurities 3064700400014 ERR-ANALYS (ERR-T) Total error. Partial components of the 3064700400015 error are: 3064700400016 (ERR-S,0.63,1.6) - statistics 0.63 - 1.6%, 3064700400017 (ERR-1,1.55,2.17) - calibration in absolute 3064700400018 efficiency 1.55 - 2.17%, 3064700400019 (ERR-2,0.5,1.2) - background subtraction 0.50 - 1.2%, 3064700400020 (ERR-3,2.13,2.5) - absolute flux 3064700400021 determination 2.13 - 2.50% 3064700400022 COMMENT Reaction rates were calculated by using the nuclear 3064700400023 constants from - Die Gamma-Linien der Radionuclide - 3064700400024 (1970). no further information about decay-data 3064700400025 STATUS (SPSDD,30813004) Data superseded by subentry 30813004 3064700400026 ENDBIB 24 0 3064700400027 NOCOMMON 0 0 3064700400028 NODATA 0 0 3064700400029 ENDSUBENT 28 0 3064700499999 SUBENT 30647005 20100305 31443064700500001 BIB 8 23 3064700500002 REACTION (13-AL-27(N,A)11-NA-24,,SIG) 3064700500003 SAMPLE Pure metal foils 19.05 mm in diameter, 0.762 mm of 3064700500004 thickness, 0.580541 g by weight and 99.994% of purity 3064700500005 (main impurities are Mg - less than 0.001%, 3064700500006 Fe - less than 0.002%, Cu- less than 0.001% 3064700500007 and Ca- less than 0.002%)3064700500008 METHOD (ACTIV) 3064700500009 DETECTOR (GELI) 100.cm**3, calibrated in absolute efficiency, 3064700500010 see I.Garlea,St.Cerc.Fizica,no.10,(1981) 3064700500011 (FISCH) For average flux determination 3064700500012 COMMENT Reaction rates were calculated by using the nuclear 3064700500013 constants from - Die Gamma-Linien der Radionuclide - 3064700500014 (1970). no further information about decay-data 3064700500015 STATUS (SPSDD,30813002) Data superseded by subentry 30813002 3064700500016 CORRECTION For gamma self-absorption and impurities 3064700500017 ERR-ANALYS (ERR-T) Total error. Partial components of the 3064700500018 error are: 3064700500019 (ERR-S,0.63,1.6) - statistics 0.63 - 1.6%, 3064700500020 (ERR-1,1.55,2.17) - calibration in absolute 3064700500021 efficiency 1.55 - 2.17%, 3064700500022 (ERR-2,0.5,1.2) - background subtraction 0.50 - 1.2%, 3064700500023 (ERR-3,2.13,2.5) - absolute flux 3064700500024 determination 2.13 - 2.50% 3064700500025 ENDBIB 23 0 3064700500026 NOCOMMON 0 0 3064700500027 NODATA 0 0 3064700500028 ENDSUBENT 27 0 3064700599999 SUBENT 30647006 20100305 31443064700600001 BIB 8 22 3064700600002 REACTION (26-FE-56(N,P)25-MN-56,,SIG) 3064700600003 SAMPLE Pure metal foils 12.7 mm in diameter, 0.127 mm of 3064700600004 thickness, 0.136748 g by weight and 99.823% of purity 3064700600005 (main impurities are Cr- 0.02%,Mn- 0.025%, Co- 0.07%, 3064700600006 Ni- 0.06%, Cu- 0.05%, Mo- 0.007%, Sn- 0.008%) 3064700600007 METHOD (ACTIV) 3064700600008 DETECTOR (GELI) 100.cm**3, calibrated in absolute efficiency, 3064700600009 see I.Garlea,St.Cerc.Fizica,no.10,(1981) 3064700600010 (FISCH) For average flux determination 3064700600011 COMMENT Reaction rates were calculated by using the nuclear 3064700600012 constants from - Die Gamma-Linien der Radionuclide - 3064700600013 (1970). no further information about decay-data 3064700600014 STATUS (SPSDD,30813003) Data superseded by subentry 30813003 3064700600015 CORRECTION For gamma self-absorption and impurities 3064700600016 ERR-ANALYS (ERR-T) Total error. Partial components of the 3064700600017 error are: 3064700600018 (ERR-S,0.63,1.6) - statistics 0.63 - 1.6%, 3064700600019 (ERR-1,1.55,2.17) - calibration in absolute 3064700600020 efficiency 1.55 - 2.17%, 3064700600021 (ERR-2,0.5,1.2) - background subtraction 0.50 - 1.2%, 3064700600022 (ERR-3,2.13,2.5) - absolute flux 3064700600023 determination 2.13 - 2.50% 3064700600024 ENDBIB 22 0 3064700600025 NOCOMMON 0 0 3064700600026 NODATA 0 0 3064700600027 ENDSUBENT 26 0 3064700699999 SUBENT 30647007 20100305 31443064700700001 BIB 7 26 3064700700002 REACTION (94-PU-239(N,F),,SIG) 3064700700003 SAMPLE The fission chamber with outer diameters of 20 and 3064700700004 12. mm and total mass of deposit-95.24 (+-.15%) 3064700700005 microgrammes (or (2.367 x 10**17)+-1.8% of main 3064700700006 isotope). The isotopic composition of the sample 3064700700007 is Pu-239 - 99.88%, Pu-240 - 0.12%. 3064700700008 The accuracy of fissionable deposit mass calibration 3064700700009 was between 1.6 and 3.5%. 3064700700010 METHOD Grundl method of fission rate measurement, see J. 3064700700011 Grundl et al. Nucl.Technol.,Vol.25,(1975) 3064700700012 DETECTOR (FISCH) Three different fission chambers for average 3064700700013 flux determination + fission chamber for measured 3064700700014 fissionable deposit 3064700700015 CORRECTION The following corrections have been applied 3064700700016 extrapolation to zero 3064700700017 fissionable impurities in deposit 3064700700018 fission fragment absorbtion in deposit 3064700700019 ERR-ANALYS (ERR-T) Total error consisting from main components 3064700700020 (ERR-S,0.56,1.81) counting statistics +-(0.56 - 1.81)%3064700700021 (ERR-1) correction to extrapolation to zero +-0.4% 3064700700022 (ERR-2) absorption in deposit +-0.35% 3064700700023 (ERR-3) fission of impurities +-0.2% 3064700700024 (ERR-4,0.97,1.13) flux level (run to run monitoring) 3064700700025 +-(0.97 - 1.13)% 3064700700026 (ERR-5,1.6,3.5) deposit mass calibration +-(1.6 - 3.5)%3064700700027 STATUS (SPSDD,30813010) Superseded by subentry 30813010 3064700700028 ENDBIB 26 0 3064700700029 COMMON 3 3 3064700700030 ERR-1 ERR-2 ERR-3 3064700700031 PER-CENT PER-CENT PER-CENT 3064700700032 0.4 0.35 0.2 3064700700033 ENDCOMMON 3 0 3064700700034 NODATA 0 0 3064700700035 ENDSUBENT 34 0 3064700799999 SUBENT 30647008 20100305 31443064700800001 BIB 7 26 3064700800002 REACTION (92-U-238(N,F),,SIG) 3064700800003 SAMPLE The fission chamber with outer diameters of 20 and 12mm3064700800004 and total mass of deposit-84.0(+-0.9%) microgrammes 3064700800005 (or(2.178e+17)+-3.% of nuclei of main isotope). 3064700800006 The isotopic composition of the sample 3064700800007 is U-238 - about 100.% 3064700800008 The accuracy of fissionable deposit mass calibration 3064700800009 was between 1.6 and 3.5%. 3064700800010 METHOD Grundl method of fission rate measurement, see J. 3064700800011 Grundl et al. Nucl.Technol.,Vol.25,(1975) 3064700800012 DETECTOR (FISCH) Three different fission chambers for average 3064700800013 flux determination + fission chamber for measured 3064700800014 fissionable deposit 3064700800015 CORRECTION The following corrections have been applied 3064700800016 extrapolation to zero 3064700800017 fissionable impurities in deposit 3064700800018 fission fragment absorbtion in deposit 3064700800019 ERR-ANALYS (ERR-T) Total error consisting from main components 3064700800020 (ERR-S,0.56,1.81) counting statistics +-(0.56 - 1.81)%3064700800021 (ERR-1) correction to extrapolation to zero +-0.4% 3064700800022 (ERR-2) absorption in deposit +-0.35% 3064700800023 (ERR-3) fission of impurities +-0.2% 3064700800024 (ERR-4,0.97,1.13) flux level (run to run monitoring) 3064700800025 +-(0.97 - 1.13)% 3064700800026 (ERR-5,1.6,3.5) deposit mass calibration +-(1.6 - 3.5)%3064700800027 STATUS (SPSDD,30813008) Superseded by subentry 30813008 3064700800028 ENDBIB 26 0 3064700800029 COMMON 3 3 3064700800030 ERR-1 ERR-2 ERR-3 3064700800031 PER-CENT PER-CENT PER-CENT 3064700800032 0.4 0.35 0.2 3064700800033 ENDCOMMON 3 0 3064700800034 NODATA 0 0 3064700800035 ENDSUBENT 34 0 3064700899999 SUBENT 30647009 20100305 31443064700900001 BIB 7 24 3064700900002 REACTION (93-NP-237(N,F),,SIG) 3064700900003 SAMPLE The fission chamber with outer diameters of 20 and 3064700900004 12. mm and total mass of deposit-83.50 (+-0.3%) 3064700900005 microgrammes (or (2.123 x 10**17)+-2.4% of nuclei of 3064700900006 main isotope). The isotopic composition of the sample 3064700900007 is Np-237- about 100.%, Pu-239 - 0.4 ppm. 3064700900008 METHOD Grundl method of fission rate measurement, see J. 3064700900009 Grundl et al. Nucl.Technol.,Vol.25,(1975) 3064700900010 DETECTOR (FISCH) Three different fission chambers for average 3064700900011 flux determination + fission chamber for measured 3064700900012 fissionable deposit 3064700900013 CORRECTION The following corrections have been applied 3064700900014 extrapolation to zero 3064700900015 fissionable impurities in deposit 3064700900016 fission fragment absorbtion in deposit 3064700900017 ERR-ANALYS (ERR-T) Total error consisting from main components 3064700900018 (ERR-S,0.56,1.81) counting statistics +-(0.56 - 1.81)%3064700900019 (ERR-1) correction to extrapolation to zero +-0.4% 3064700900020 (ERR-2) absorption in deposit +-0.35% 3064700900021 (ERR-3) fission of impurities +-0.2% 3064700900022 (ERR-4,0.97,1.13) flux level (run to run monitoring) 3064700900023 +-(0.97 - 1.13)% 3064700900024 (ERR-5,1.6,3.5) deposit mass calibration +-(1.6 - 3.5)%3064700900025 STATUS (SPSDD,30813009) Superseded by subentry 30813009 3064700900026 ENDBIB 24 0 3064700900027 COMMON 3 3 3064700900028 ERR-1 ERR-2 ERR-3 3064700900029 PER-CENT PER-CENT PER-CENT 3064700900030 0.4 0.35 0.2 3064700900031 ENDCOMMON 3 0 3064700900032 NODATA 0 0 3064700900033 ENDSUBENT 32 0 3064700999999 SUBENT 30647010 20100305 31443064701000001 BIB 7 24 3064701000002 REACTION (90-TH-232(N,F),,SIG) 3064701000003 SAMPLE The fission chamber with outer diameters of 20 and 12mm3064701000004 and total mass of deposit- 65.49 (+-3.5%) 3064701000005 microgrammes (or (1.700 x 10**17)+-3.5% of nuclei of 3064701000006 main isotope). The isotopic composition of the sample 3064701000007 is Th-232- about 100.%, U-natural-0.16%) 3064701000008 METHOD Grundl method of fission rate measurement, see J. 3064701000009 Grundl et al. Nucl.Technol.,Vol.25,(1975) 3064701000010 DETECTOR (FISCH) Three different fission chambers for average 3064701000011 flux determination + fission chamber for measured 3064701000012 fissionable deposit 3064701000013 CORRECTION The following corrections have been applied 3064701000014 extrapolation to zero 3064701000015 fissionable impurities in deposit 3064701000016 fission fragment absorbtion in deposit 3064701000017 ERR-ANALYS (ERR-T) Total error consisting from main components 3064701000018 (ERR-S,0.56,1.81) counting statistics +-(0.56 - 1.81)%3064701000019 (ERR-1) correction to extrapolation to zero +-0.4% 3064701000020 (ERR-2) absorption in deposit +-0.35% 3064701000021 (ERR-3) fission of impurities +-0.2% 3064701000022 (ERR-4,0.97,1.13) flux level (run to run monitoring) 3064701000023 +-(0.97 - 1.13)% 3064701000024 (ERR-5,1.6,3.5) deposit mass calibration +-(1.6 - 3.5)%3064701000025 STATUS (SPSDD,30813007) Superseded by subentry 30813007 3064701000026 ENDBIB 24 0 3064701000027 COMMON 3 3 3064701000028 ERR-1 ERR-2 ERR-3 3064701000029 PER-CENT PER-CENT PER-CENT 3064701000030 0.4 0.35 0.2 3064701000031 ENDCOMMON 3 0 3064701000032 NODATA 0 0 3064701000033 ENDSUBENT 32 0 3064701099999 ENDENTRY 10 0 3064799999999