ENTRY 41147 20060127 41374114700000001 SUBENT 41147001 20060127 41374114700100001 BIB 10 34 4114700100002 TITLE Measurement And Comparison With Calculation Of 4114700100003 Reaction Velocities (N,Gamma), (N,2n), (N,F) In 4114700100004 Spherical Assemblies Consisting Of Metallic Uranium 4114700100005 And Thorium At Placing In Their Center 14-MeV 4114700100006 Neutron Source 4114700100007 AUTHOR (V.A.ZAGRYADSKIY,M.I.KRAYNEV,D.V.MARKOVSKIY, 4114700100008 V.I.NOVIKOV,YU.P.SEL'DYAKOV,D.YU.CHUVILIN, 4114700100009 G.E.SHATALOV) 4114700100010 INSTITUTE (4RUSKUR) 4114700100011 REFERENCE (R,IAE-4480/8,1987) Main Ref. Data tables are given 4114700100012 (R,IAE-4197/8,1985) Experimental Details 4114700100013 FACILITY (VDG) 4114700100014 MONITOR (29-CU-65(N,2N)29-CU-64,,SIG) 4114700100015 METHOD (ACTIV) 4114700100016 STATUS Data Are Taken From Main Reference 4114700100017 ERR-ANALYS (ERR-T) Total Error 4114700100018 (ERR-1) Error Of Photon Peak Area Determination 4114700100019 (ERR-2) Error Of Gamma-spectrometer Efficiency 4114700100020 (ERR-3) Error Of Gamma-quanta Self-absorption 4114700100021 Determination 4114700100022 (ERR-4) Error Of Absolute Neutron Yield Determination4114700100023 (ERR-5) Error Of Absolute Nucleus Number 4114700100024 Determination 4114700100025 (ERR-6) Error Of Nuclear Decay Quantum Yield 4114700100026 Determination 4114700100027 (ERR-7) Error Of Fission Fragments Number 4114700100028 Determination 4114700100029 (ERR-8) Error Of Numerical Integration On The Volume 4114700100030 Of The Assembly 4114700100031 HISTORY (19940519C) + + Compiled at the centre - CJD + + 4114700100032 (20050127A) M.M. Reaction codes of Sub.2-11 were 4114700100033 corrected.Units of data were corrected in according to4114700100034 comment of author D.V.Markovskiy. 4114700100035 Dates were corrected for 4-digits Year. 4114700100036 ENDBIB 34 0 4114700100037 COMMON 8 6 4114700100038 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 4114700100039 ERR-7 ERR-8 4114700100040 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4114700100041 PER-CENT PER-CENT 4114700100042 2.5 1.5 1.5 2. 0.1 2. 4114700100043 5. 2. 4114700100044 ENDCOMMON 6 0 4114700100045 ENDSUBENT 44 0 4114700199999 SUBENT 41147002 20060127 41374114700200001 BIB 7 20 4114700200002 REACTION (90-TH-232(N,2N)90-TH-231,,SGV,,FCT/SPA) 4114700200003 Reaction rate normalized to one neutron of source, 4114700200004 averaged over assembly volume. 4114700200005 SAMPLE Thin metallic foils of 0.22 mm thicknes,10mm diameter.4114700200006 Copper foils of 0.5 mm thickness, 10 mm diameter 4114700200007 Cu-65 content is 99.8 %. 4114700200008 Foils were placed at 100 mm distance from target 4114700200009 center at angles of 0,25,50,70,100,120,140 degrees to 4114700200010 deuteron beam direction. 4114700200011 INC-SOURCE (D-T) Neutron generator in the center. 4114700200012 10E+10 neutrons/sec. 4114700200013 INC-SPECT Only direct neutrons of 14.MeV source were taken into 4114700200014 account 4114700200015 DETECTOR (GE-IN) BDR1-200 germanium detector with berylium 4114700200016 window for Th-231 activity measurement. 4114700200017 (NAICR) NaI(Tl) scincilation gamma-spectrometer for 4114700200018 copper activity measurement. 4114700200019 DECAY-DATA (90-TH-231,25.52HR,DG,84.2) 4114700200020 (29-CU-64,12.7HR,DG,511.) 4114700200021 STATUS From Table 1 of main reference. 4114700200022 ENDBIB 20 0 4114700200023 NOCOMMON 0 0 4114700200024 DATA 3 1 4114700200025 EN DATA ERR-T 4114700200026 EV 1/SEC 1/SEC 4114700200027 1.4E+07 0.198 0.009 4114700200028 ENDDATA 3 0 4114700200029 ENDSUBENT 28 0 4114700299999 SUBENT 41147003 20060127 41374114700300001 BIB 8 26 4114700300002 REACTION (90-TH-232(N,2N)90-TH-231,,SGV,,FCT/SPA) 4114700300003 Reaction rate normalized to one neutron of source, 4114700300004 averaged over assembly volume. 4114700300005 SAMPLE Thin metallic foils of 0.22 mm thicknes,10mm diameter.4114700300006 Copper foils of 0.5 mm thickness, 10 mm diameter 4114700300007 Cu-65 content is 99.8 %. 4114700300008 Foils were placed at 60,70,86,101,116,130 mm distance 4114700300009 from target.Thorium blocks between foils. 4114700300010 Thorium assembly of outside diameter- 260mm, inside 4114700300011 diameter - 120mm had a channel of 50mm(for neutron 4114700300012 generater placing) and radial channels at angles of 4114700300013 0,25,50,70,100,120,140 degrees to deuteron beam 4114700300014 direction. I 4114700300015 INC-SOURCE (D-T) Neutron generator in the center of thorium 4114700300016 assembly. 10E+10 neutrons/sec. 4114700300017 INC-SPECT Direct 14-MeV neutrons plus secondary neutrons were 4114700300018 taken into account. 4114700300019 DETECTOR (GE-IN) BDR1-200 germanium detector with berylium 4114700300020 window for Th-231 activity measurement. 4114700300021 (NAICR) NaI(Tl) crystal scincilation gamma-spectrometer4114700300022 for copper activity measurement. 4114700300023 DECAY-DATA (90-TH-231,25.52HR,DG,84.2) 4114700300024 (29-CU-64,12.7HR,DG,511.) 4114700300025 STATUS From Table 1 of main reference. 4114700300026 COMMENT Reaction rate for secondary neutrons spectrum was 4114700300027 determined to be 0.035+-0.013 1/sec. 4114700300028 ENDBIB 26 0 4114700300029 NOCOMMON 0 0 4114700300030 DATA 3 1 4114700300031 EN-DUMMY DATA ERR-T 4114700300032 EV 1/SEC 1/SEC 4114700300033 1.4E+07 0.233 0.010 4114700300034 ENDDATA 3 0 4114700300035 ENDSUBENT 34 0 4114700399999 SUBENT 41147004 20060127 41374114700400001 BIB 8 20 4114700400002 REACTION (90-TH-232(N,F),,SGV,,FCT/SPA) 4114700400003 Reaction rate normalized to one neutron of source, 4114700400004 averaged over assembly volume. 4114700400005 SAMPLE Thin metallic foils of 0.22 mm thicknes,10mm diameter.4114700400006 Copper foils of 0.5 mm thickness, 10 mm diameter 4114700400007 Cu-65 content is 99.8 % 4114700400008 INC-SOURCE (D-T) Neutron generator in the center. 4114700400009 10E+10 neutrons/sec. 4114700400010 INC-SPECT Only direct neutrons of 14.MeV source were taken into 4114700400011 account 4114700400012 DETECTOR (SISD) DKPs-25 silicon detector for determination of 4114700400013 relative distribution of reaction rate in assembly 4114700400014 volume. 4114700400015 (GELI) Gamma-spectrometer with coaxial Ge-Li detector 4114700400016 for absolute reaction rate determination 4114700400017 PART-DET (FF) 4114700400018 (G) 4114700400019 DECAY-DATA (42-MO-99,2.7489D,DG,140.5) 4114700400020 (58-CE-143,33.039HR,DG,293.3) 4114700400021 STATUS From Table 1 of main reference. 4114700400022 ENDBIB 20 0 4114700400023 NOCOMMON 0 0 4114700400024 DATA 3 1 4114700400025 EN DATA ERR-T 4114700400026 EV 1/SEC 1/SEC 4114700400027 1.4E+07 0.0558 0.0032 4114700400028 ENDDATA 3 0 4114700400029 ENDSUBENT 28 0 4114700499999 SUBENT 41147005 20060127 41374114700500001 BIB 9 22 4114700500002 REACTION (90-TH-232(N,F),,SGV,,FCT/SPA) 4114700500003 Reaction rate normalized to one neutron of source, 4114700500004 averaged over assembly volume. 4114700500005 SAMPLE Thin metallic foils of 0.22 mm thicknes,10mm diameter.4114700500006 Copper foils of 0.5 mm thickness, 10 mm diameter, 4114700500007 Cu-65 content is 99.8 pc 4114700500008 INC-SOURCE (D-T) Neutron generator in the center of thorium 4114700500009 assembly. 10E+10 neutrons/sec. 4114700500010 INC-SPECT Direct 14-MeV neutrons plus secondary neutrons were 4114700500011 taken into account. 4114700500012 DETECTOR (SISD) DKPs-25 silicon detector for determination of 4114700500013 relative distribution of reaction rate in assembly 4114700500014 volume. 4114700500015 (GELI) Gamma-spectrometer with coaxial Ge-Li detector 4114700500016 for absolute reaction rate determination 4114700500017 PART-DET (FF) 4114700500018 (G) 4114700500019 DECAY-DATA (42-MO-99,2.7489D,DG,140.5) 4114700500020 (58-CE-143,33.039HR,DG,293.3) 4114700500021 STATUS From Table 1 of main reference 4114700500022 COMMENT Reaction rate for secondary neutrons spectrum was 4114700500023 determined to be 0.0208+-0.0047 1/sec. 4114700500024 ENDBIB 22 0 4114700500025 NOCOMMON 0 0 4114700500026 DATA 3 1 4114700500027 EN-DUMMY DATA ERR-T 4114700500028 EV 1/SEC 1/SEC 4114700500029 1.4E+07 0.0766 0.0034 4114700500030 ENDDATA 3 0 4114700500031 ENDSUBENT 30 0 4114700599999 SUBENT 41147006 20060127 41374114700600001 BIB 5 11 4114700600002 REACTION (90-TH-232(N,G)90-TH-233,,SGV,,FCT/SPA) 4114700600003 Reaction rate normalized to one neutron of source, 4114700600004 averaged over assembly volume. 4114700600005 SAMPLE Thin metallic foil, 0.22 mm thicknes, 10mm diameter 4114700600006 Copper foil 0.5 mm thickness, 10 mm diameter 4114700600007 Cu-65 content is 99.8 % 4114700600008 INC-SOURCE (D-T) Neutron generator in the center of thorium 4114700600009 assembly. 10E+10 neutrons/sec. 4114700600010 INC-SPECT Direct 14-MeV neutrons plus secondary neutrons were 4114700600011 taken into account. 4114700600012 STATUS From Table 1 of main reference 4114700600013 ENDBIB 11 0 4114700600014 NOCOMMON 0 0 4114700600015 DATA 3 1 4114700600016 EN-DUMMY DATA ERR-T 4114700600017 EV 1/SEC 1/SEC 4114700600018 1.4E+07 0.0506 0.002 4114700600019 ENDDATA 3 0 4114700600020 ENDSUBENT 19 0 4114700699999 SUBENT 41147007 20060127 41374114700700001 BIB 8 15 4114700700002 REACTION (92-U-238(N,2N)92-U-237,,SGV,,FCT/SPA) 4114700700003 Reaction rate normalized to one neutron of source, 4114700700004 averaged over assembly volume. 4114700700005 SAMPLE Thin metallic foils,0.15 mm thickness, 10 mm diameter 4114700700006 U-238 content is 99.6 %, U-235 - 0.4%. 4114700700007 Copper foil 0.5 mm thickness, 10 mm diameter 4114700700008 Cu-65 content is 99.8 % 4114700700009 DETECTOR (GELI) Gamma-spectrometer with coaxial Ge-Li detector 4114700700010 for activity determination 4114700700011 PART-DET (G) 4114700700012 DECAY-DATA (92-U-237,,DG,208.) 4114700700013 INC-SOURCE (D-T) Neutron generator in the center of uranium 4114700700014 assembly. 10E+10 neutrons/sec. 4114700700015 INC-SPECT Direct 14-MeV neutrons were taken into account. 4114700700016 STATUS From Table 3 of main reference 4114700700017 ENDBIB 15 0 4114700700018 NOCOMMON 0 0 4114700700019 DATA 3 1 4114700700020 EN DATA ERR-T 4114700700021 EV 1/SEC 1/SEC 4114700700022 1.4E+07 0.199 0.010 4114700700023 ENDDATA 3 0 4114700700024 ENDSUBENT 23 0 4114700799999 SUBENT 41147008 20060127 41374114700800001 BIB 9 18 4114700800002 REACTION (92-U-238(N,2N)92-U-237,,SGV,,FCT/SPA) 4114700800003 Reaction rate normalized to one neutron of source, 4114700800004 averaged over assembly volume. 4114700800005 SAMPLE Thin metallic foils,0.15 mm thickness, 10 mm diameter 4114700800006 U-238 content is 99.6 %, U-235 - 0.4%. 4114700800007 Copper foil 0.5 mm thickness, 10 mm diameter 4114700800008 Cu-65 content is 99.8 % 4114700800009 DETECTOR (GELI) Gamma-spectrometer with coaxial Ge-Li detector 4114700800010 for activity determination 4114700800011 PART-DET (G) 4114700800012 DECAY-DATA (92-U-237,,DG,208.) 4114700800013 INC-SOURCE (D-T) Neutron generator in the center of uranium 4114700800014 assembly. 10E+10 neutrons/sec. 4114700800015 INC-SPECT Direct 14-MeV neutrons plus secondary neutrons were 4114700800016 taken into account. 4114700800017 STATUS From Table 3 of main reference 4114700800018 COMMENT Reaction rate for secondary neutrons spectrum was 4114700800019 determined to be 0.055+-0.016 1/sec. 4114700800020 ENDBIB 18 0 4114700800021 NOCOMMON 0 0 4114700800022 DATA 3 1 4114700800023 EN-DUMMY DATA ERR-T 4114700800024 EV 1/SEC 1/SEC 4114700800025 1.4E+07 0.254 0.012 4114700800026 ENDDATA 3 0 4114700800027 ENDSUBENT 26 0 4114700899999 SUBENT 41147009 20060127 41374114700900001 BIB 7 15 4114700900002 REACTION (92-U-238(N,F),,SGV,,FCT/SPA) 4114700900003 Reaction rate normalized to one neutron of source, 4114700900004 averaged over assembly volume. 4114700900005 SAMPLE Metallic plate, 1 mm thickness, 10 mm diameter 4114700900006 U-238 content is 99.6 %, U-235 -0.4%. 4114700900007 Copper foil 0.5 mm thickness, 10 mm diameter 4114700900008 Cu-65 content is 99.8 % 4114700900009 DETECTOR (GELI) Gamma-spectrometer with coaxial Ge-Li detector 4114700900010 for activity determination 4114700900011 DECAY-DATA (58-CE-143,,DG,293.3) 4114700900012 (57-LA-140,,DG,1596.5) 4114700900013 INC-SOURCE (D-T) Neutron generator in the center of uranium 4114700900014 assembly. 10E+10 neutrons/sec. 4114700900015 INC-SPECT Direct 14-MeV neutrons were taken into account. 4114700900016 STATUS From Table 3 of main reference 4114700900017 ENDBIB 15 0 4114700900018 NOCOMMON 0 0 4114700900019 DATA 3 1 4114700900020 EN DATA ERR-T 4114700900021 EV 1/SEC 1/SEC 4114700900022 1.4E+07 0.250 0.013 4114700900023 ENDDATA 3 0 4114700900024 ENDSUBENT 23 0 4114700999999 SUBENT 41147010 20060127 41374114701000001 BIB 8 18 4114701000002 REACTION (92-U-238(N,F),,SGV,,FCT/SPA) 4114701000003 Reaction rate normalized to one neutron of source, 4114701000004 averaged over assembly volume. 4114701000005 SAMPLE Metallic plate, 1 mm thickness, 10 mm diameter 4114701000006 U-238 content is 99.6 %, U-235 -0.4%. 4114701000007 Copper foil 0.5 mm thickness, 10 mm diameter 4114701000008 Cu-65 content is 99.8 % 4114701000009 DETECTOR (GELI) Gamma-spectrometer with coaxial Ge-Li detector 4114701000010 for activity determination 4114701000011 DECAY-DATA (58-CE-143,,DG,293.3) 4114701000012 (57-LA-140,,DG,1596.5) 4114701000013 INC-SOURCE (D-T) Neutron generator in the center of uranium 4114701000014 assembly. 10E+10 neutrons/sec. 4114701000015 INC-SPECT Direct 14-MeV neutrons plus secondary neutrons were 4114701000016 taken into account. 4114701000017 STATUS From Table 3 of main reference 4114701000018 COMMENT Reaction rate for secondary neutrons spectrum was 4114701000019 determined to be 0.237+-0.024 1/sec. 4114701000020 ENDBIB 18 0 4114701000021 NOCOMMON 0 0 4114701000022 DATA 3 1 4114701000023 EN-DUMMY DATA ERR-T 4114701000024 EV 1/SEC 1/SEC 4114701000025 1.4E+07 0.487 0.020 4114701000026 ENDDATA 3 0 4114701000027 ENDSUBENT 26 0 4114701099999 SUBENT 41147011 20060127 41374114701100001 BIB 7 15 4114701100002 REACTION (92-U-238(N,G)92-U-239,,SGV,,FCT/SPA) 4114701100003 Reaction rate normalized to one neutron of source, 4114701100004 averaged over assembly volume. 4114701100005 SAMPLE Thin metallic foil, 0.15 mm thicknes, 10 mm diameter 4114701100006 U-238 content is 99.6 %, U-235 -0.4%. 4114701100007 Copper foil 0.5 mm thickness, 10 mm diameter 4114701100008 Cu-65 content is 99.8 % 4114701100009 DETECTOR (GELI) Gamma-spectrometer with coaxial Ge-Li detector 4114701100010 for activity determination 4114701100011 INC-SOURCE (D-T) Neutron generator in the center of uranium 4114701100012 assembly. 10E+10 neutrons/sec. 4114701100013 INC-SPECT Direct 14-MeV neutrons plus secondary neutrons were 4114701100014 taken into account. 4114701100015 DECAY-DATA (93-NP-239,,DG,277.6) 4114701100016 STATUS From Table 3 of main reference 4114701100017 ENDBIB 15 0 4114701100018 NOCOMMON 0 0 4114701100019 DATA 3 1 4114701100020 EN-DUMMY DATA ERR-T 4114701100021 EV 1/SEC 1/SEC 4114701100022 1.4E+07 0.295 0.012 4114701100023 ENDDATA 3 0 4114701100024 ENDSUBENT 23 0 4114701199999 ENDENTRY 11 0 4114799999999