ENTRY 40310 20151010 41754031000000001 SUBENT 40310001 20151010 41754031000100001 BIB 11 37 4031000100002 INSTITUTE (4RUSFEI) 4031000100003 REFERENCE (J,SJA,39,670,1975) Eng.transl.of AE,39,(2),86,1975 4031000100004 (J,AE,39,(2),86,197508) Data are given 4031000100005 AUTHOR (V.G.Dvukhsherstnov,Yu.A.Kazanskii,V.M.Furmanov, 4031000100006 V.L.Petrov) 4031000100007 TITLE Measurement of the capture - fission cross-sectional 4031000100008 ratio alpha for U-235 in the filtered neutron beams 4031000100009 of the Obninsk Nuclear Power Station reactor 4031000100010 METHOD (COINC) Gammas and neutron count quantities 4031000100011 in coincidence with fissions were determined. 4031000100012 Total gammas and neutron count quantities 4031000100013 and count quantity of delayed irradiation gammas of 4031000100014 fission fragments were also determined 4031000100015 FACILITY (REAC,4RUSFEI) 4031000100016 DETECTOR (FISCH) Plutonium and uranium fission chambers were 4031000100017 used at measurements on thermal neutron spectrum 4031000100018 (SCIN) scintillation detector with stilbene crystal4031000100019 was used for neutron and gammas registration 4031000100020 PART-DET (N) Neutrons 4031000100021 (FF) fission fragments 4031000100022 (G) gammas 4031000100023 CORRECTION Calculated corrections were introduced on gammas and 4031000100024 neutron absorption and scattering, 4031000100025 neutron multiplication of sample, 4031000100026 admixture of their isotopes, 4031000100027 nonmonochromatic neutron beam 4031000100028 STATUS (TABLE) Data from J,AE,39,(2),86,1975. 4031000100029 See also entry 40092 4031000100030 HISTORY (19760225C) Compiled at the centre 4031000100031 (19870522A) subents 40310002,003,004 superseded subents4031000100032 40092002 and 40092003. 4031000100033 iso-quant into reaction converted 4031000100034 (20150208U) SD: Updated to new date formats,lower case.4031000100035 Ref. on Engl.transl. of AE added. SAMPLE updated 4031000100036 in Subents 2-6. 4031000100037 (20151010A) M.M. BIB information was updated in STATUS,4031000100038 SAMPLE 4031000100039 ENDBIB 37 0 4031000100040 NOCOMMON 0 0 4031000100041 ENDSUBENT 40 0 4031000199999 SUBENT 40310002 20151010 41754031000200001 BIB 7 17 4031000200002 REACTION (92-U-235(N,ABS),,ALF,,AV) 4031000200003 INC-SOURCE (REAC) Reactor. Neutron beam was obtained by 4031000200004 transmission of reactor neutron spectrum through 4031000200005 scandium and titanium filters 4031000200006 SAMPLE (92-U-235,ENR=0.90) Sample thickness was equal to about4031000200007 4. x 10.**(-3) nuclei/barn; 8 gr in weight; 4031000200008 sealed in a 0.2-mm thick stainless-steel can. 4031000200009 MONITOR (92-U-235(N,ABS),,ALF) Normalization was made on 4031000200010 calculated value Alpha-thermal. 4031000200011 Alpha value was calculated from evaluated capture and 4031000200012 fission cross-sections. 4031000200013 ERR-ANALYS (DATA-ERR) Given mean-squared error consists of 4031000200014 statistical measurement error, alpha-thermal-bar value 4031000200015 uncertainty, uncertainty of nu-bar to nu-thermal-bar 4031000200016 ratio and uncertainties of calculated corrections. 4031000200017 STATUS (TABLE) Table 1 of J,SJA,39,670,1975 4031000200018 HISTORY (19870522A) This San supersedes 40092002 4031000200019 ENDBIB 17 0 4031000200020 COMMON 3 3 4031000200021 EN-NRM MONIT MONIT-ERR 4031000200022 EV NO-DIM NO-DIM 4031000200023 0.0253 0.187 0.007 4031000200024 ENDCOMMON 3 0 4031000200025 DATA 4 1 4031000200026 EN-MIN EN-MAX DATA DATA-ERR 4031000200027 KEV KEV NO-DIM NO-DIM 4031000200028 1.5 2.3 0.468 0.033 4031000200029 ENDDATA 3 0 4031000200030 ENDSUBENT 29 0 4031000299999 SUBENT 40310003 20151010 41754031000300001 BIB 6 16 4031000300002 REACTION (92-U-235(N,ABS),,ALF,,AV) 4031000300003 INC-SOURCE (REAC) Reactor. Neutron beam was obtained by 4031000300004 transmission of reactor neutron spectrum through 4031000300005 scandium and titanium filters 4031000300006 SAMPLE (92-U-235,ENR=0.90) Sample thickness was equal to about4031000300007 6. x 10.**(-3) nuclei/barn; 12 gr in weight; 4031000300008 sealed in a 0.2-mm thick stainless-steel can. 4031000300009 MONITOR (92-U-235(N,ABS),,ALF) Normalization was made on 4031000300010 calculated value alpha thermal. 4031000300011 Alpha value was calculated from evaluated capture and 4031000300012 fission cross-sections. 4031000300013 ERR-ANALYS (DATA-ERR) Given mean-squared error consists of 4031000300014 statistical measurement error, alpha-thermal-bar 4031000300015 value uncertainty, uncertainty of nu-bar to nu-thermal-4031000300016 bar ratio and uncertainties of calculated corrections. 4031000300017 STATUS (TABLE) Table 1 of J,SJA,39,670,1975 4031000300018 ENDBIB 16 0 4031000300019 COMMON 3 3 4031000300020 EN-NRM MONIT MONIT-ERR 4031000300021 EV NO-DIM NO-DIM 4031000300022 0.0253 0.187 0.007 4031000300023 ENDCOMMON 3 0 4031000300024 DATA 4 1 4031000300025 EN-MIN EN-MAX DATA DATA-ERR 4031000300026 KEV KEV NO-DIM NO-DIM 4031000300027 1.5 2.3 0.454 0.031 4031000300028 ENDDATA 3 0 4031000300029 ENDSUBENT 28 0 4031000399999 SUBENT 40310004 20151010 41754031000400001 BIB 7 17 4031000400002 REACTION (92-U-235(N,ABS),,ALF,,AV) 4031000400003 INC-SOURCE (REAC) Reactor. Neutron beam was obtained by 4031000400004 transmission of reactor neutron spectrum through iron, 4031000400005 aluminum and sulphur filters 4031000400006 SAMPLE (92-U-235,ENR=0.90) Sample thickness was equal to about4031000400007 4. x 10.**(-3) nuclei/barn; 8 gr in weight; 4031000400008 sealed in a 0.2-mm thick stainless-steel can. 4031000400009 MONITOR (92-U-235(N,ABS),,ALF) Normalization was made on 4031000400010 calculated value alpha thermal. 4031000400011 Alpha value was calculated from evaluated capture and 4031000400012 fission cross-sections 4031000400013 ERR-ANALYS (DATA-ERR) Given mean-squared error consists of 4031000400014 statistical measurement error, alpha-thermal-bar value 4031000400015 uncertainty, uncertainty of nu-bar to nu-thermal-bar 4031000400016 ratio and uncertainties of calculated corrections 4031000400017 STATUS (TABLE) Table 1 of J,SJA,39,670,1975 4031000400018 HISTORY (19870522A) This subent supersedes 40092003 4031000400019 ENDBIB 17 0 4031000400020 COMMON 3 3 4031000400021 EN-NRM MONIT MONIT-ERR 4031000400022 EV NO-DIM NO-DIM 4031000400023 0.0253 0.187 0.007 4031000400024 ENDCOMMON 3 0 4031000400025 DATA 4 1 4031000400026 EN-MIN EN-MAX DATA DATA-ERR 4031000400027 KEV KEV NO-DIM NO-DIM 4031000400028 22.9 25.4 0.361 0.038 4031000400029 ENDDATA 3 0 4031000400030 ENDSUBENT 29 0 4031000499999 SUBENT 40310005 20151010 41754031000500001 BIB 6 17 4031000500002 REACTION (92-U-235(N,ABS),,ALF,,AV) 4031000500003 INC-SOURCE (REAC) Reactor neutron beam was obtained by 4031000500004 transmission of reactor neutron spectrum through 4031000500005 silicon, titanium and boron filters 4031000500006 SAMPLE (92-U-235,ENR=0.90) Sample thickness was equal to about4031000500007 4. x 10.**(-3) nuclei/barn ; 8 gr in weight; 4031000500008 sealed in a 0.2-mm thick stainless-steel can. 4031000500009 MONITOR (92-U-235(N,ABS),,ALF) Normalization was made on 4031000500010 calculated value alpha thermal. 4031000500011 Alpha value was calculated from evaluated capture and 4031000500012 fission cross-sections 4031000500013 ERR-ANALYS (DATA-ERR) Given mean-squared error consists of 4031000500014 statistical measurement error, alpha-thermal-bar 4031000500015 value uncertainty, uncertainty of nu-bar to 4031000500016 nu-thermal-bar ratio and uncertainties of calculated 4031000500017 corrections 4031000500018 STATUS (TABLE) Table 1 of J,SJA,39,670,1975 4031000500019 ENDBIB 17 0 4031000500020 COMMON 3 3 4031000500021 EN-NRM MONIT MONIT-ERR 4031000500022 EV NO-DIM NO-DIM 4031000500023 0.0253 0.187 0.007 4031000500024 ENDCOMMON 3 0 4031000500025 DATA 4 1 4031000500026 EN-MIN EN-MAX DATA DATA-ERR 4031000500027 KEV KEV NO-DIM NO-DIM 4031000500028 123. 151. 0.214 0.030 4031000500029 ENDDATA 3 0 4031000500030 ENDSUBENT 29 0 4031000599999 SUBENT 40310006 20151010 41754031000600001 BIB 5 7 4031000600002 REACTION (92-U-235(N,ABS),,ALF,,SPA) 4031000600003 INC-SOURCE (REAC) Reactor 4031000600004 INC-SPECT Continuous spectrum of neutron beam was obtained by 4031000600005 transmission of reactor neutron spectrum through 4031000600006 boron filters 4031000600007 ERR-ANALYS (DATA-ERR) No information available on type of error 4031000600008 STATUS (TABLE) Table 2 of J,SJA,39,670,1975 4031000600009 ENDBIB 7 0 4031000600010 NOCOMMON 0 0 4031000600011 DATA 3 1 4031000600012 EN-MIN DATA DATA-ERR 4031000600013 EV NO-DIM NO-DIM 4031000600014 0.18 0.362 0.022 4031000600015 ENDDATA 3 0 4031000600016 ENDSUBENT 15 0 4031000699999 ENDENTRY 6 0 4031099999999