ENTRY 40092 20210728 42004009200000001 SUBENT 40092001 20210728 42004009200100001 BIB 10 41 4009200100002 TITLE Measurement of alpha for 239Pu in filtered beams of 4009200100003 reactor neutrons. 4009200100004 AUTHOR (V.G.Dvukhsherstnov,Yu.A.Kazansky,E.A.Plaksin, 4009200100005 V.M.Furmanov,V.L.Petrov) 4009200100006 INSTITUTE (4RUSFEI) 4009200100007 REFERENCE (R,YFI-18,3,1974) Final data for Pu-239 ALFA at 2, 4009200100008 24,5 and 140 keV neutron energy are given 4009200100009 (R,INDC(CCP)-49,1,1975) 4009200100010 Engl.translation of YFI-18,3,1974 4009200100011 ((C,71KIEV,1,318,1971)= 4009200100012 (R,INDC(CCP)-456,(1),318,1972)) 4009200100013 Prelim.data for EN=2 keV. 4009200100014 (R,YFI-12,7,1971) Prelim.data for EN=2. and 24.5 keV . 4009200100015 (R,INDC(CCP)-30,5,1972) 4009200100016 Engl.translation of YFI-12,7,1971 4009200100017 (R,FEI-285,1971) Data for EN=2 keV are given 4009200100018 FACILITY (REAC,4RUSFEI) APS reactor. 4009200100019 DETECTOR (FISCH) Plutonium and uranium fission chambers were 4009200100020 used at measurements on thermal neutron spectrum 4009200100021 (SCIN) Scintillation detector with stilbene crystal 4009200100022 was used for neutron and gammas registration 4009200100023 CORRECTION Calculated corrections were introduced on 4009200100024 gammas and neutron absorption and scattering, 4009200100025 neutron multiplication in sample, 4009200100026 admixture of their isotopes, 4009200100027 nonmonochromatic neutron beam. 4009200100028 METHOD (COINC) Gammas and neutron count quantities 4009200100029 in coincidence with fissions were determined. 4009200100030 Total gammas and neutron count quantities 4009200100031 and count quantity of delayed irradiation gammas of 4009200100032 fission fragments were also determined. 4009200100033 PART-DET (N,FF) 4009200100034 HISTORY (19731204C) Compiled at the centre 4009200100035 (19750210A) Corrections in SUBENTRies 001,004,005 made.4009200100036 SUBENTRies 006 and 007 added. 4009200100037 (19870619A) SUBENTRies 002 and 003 superceded due to 4009200100038 data repetition in SUBENTs 40310002,003,004. 4009200100039 Obsolete keywords changed and ISO-QUANT into REACTION 4009200100040 converted. 4009200100041 (20210728A) Refs. INDC(CCP)-49,1,1975, 4009200100042 INDC(CCP)-30,5,1972 were added. 4009200100043 ENDBIB 41 0 4009200100044 NOCOMMON 0 0 4009200100045 ENDSUBENT 44 0 4009200199999 SUBENT 40092002 20210728 42004009200200001 BIB 7 15 4009200200002 REACTION (92-U-235(N,ABS),,ALF) 4009200200003 MONITOR (92-U-235(N,ABS),,ALF) Normalization was made on 4009200200004 calculated value alpha-thermal. Alpha-value was 4009200200005 calculated from evaluated capture and fission 4009200200006 cross-sections. 4009200200007 INC-SOURCE (REAC) 4009200200008 METHOD (FNB) 2.0 keV energy neutrons beam was obtained by 4009200200009 transmission of reactor neutron spectrum through 4009200200010 scandium and titanium filters 4009200200011 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4009200200012 article. 4009200200013 STATUS (TABLE) Table 1 of YFI-12,7,1971 4009200200014 (SPSDD,40310002) Newer publication (1975 year) 4009200200015 (SPSDD,40310003) Newer publication (1975 year) 4009200200016 HISTORY (20210728S) M.M. 4009200200017 ENDBIB 15 0 4009200200018 COMMON 3 3 4009200200019 EN-NRM MONIT MONIT-ERR 4009200200020 EV NO-DIM NO-DIM 4009200200021 0.025 0.187 0.007 4009200200022 ENDCOMMON 3 0 4009200200023 DATA 4 1 4009200200024 EN EN-ERR DATA DATA-ERR 4009200200025 KEV KEV NO-DIM NO-DIM 4009200200026 2.0 0.35 0.49 0.04 4009200200027 ENDDATA 3 0 4009200200028 ENDSUBENT 27 0 4009200299999 SUBENT 40092003 20210728 42004009200300001 BIB 7 15 4009200300002 REACTION (92-U-235(N,ABS),,ALF) 4009200300003 MONITOR (92-U-235(N,ABS),,ALF) Normalization was made on 4009200300004 calculated value alpha thermal. 4009200300005 Alpha value was calculated from evaluated capture 4009200300006 and fission cross-sections. 4009200300007 INC-SOURCE (REAC) 4009200300008 METHOD (FNB) 24.5 keV Energy neutron beam was obtained by 4009200300009 transmission of reactor neutron spectrum through iron,4009200300010 aluminum and sulphur filters 4009200300011 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the 4009200300012 article. 4009200300013 STATUS (TABLE) Table 1 of YFI-12,7,1971 4009200300014 (PRELM) Preliminary data. 4009200300015 (SPSDD,40310004) Newer publication (1975 year) 4009200300016 HISTORY (20210728S) M.M. 4009200300017 ENDBIB 15 0 4009200300018 COMMON 3 3 4009200300019 EN-NRM MONIT MONIT-ERR 4009200300020 EV NO-DIM NO-DIM 4009200300021 0.025 0.187 0.007 4009200300022 ENDCOMMON 3 0 4009200300023 DATA 4 1 4009200300024 EN EN-ERR DATA DATA-ERR 4009200300025 KEV KEV NO-DIM NO-DIM 4009200300026 24.5 1.0 0.43 0.14 4009200300027 ENDDATA 3 0 4009200300028 ENDSUBENT 27 0 4009200399999 SUBENT 40092004 20210728 42004009200400001 BIB 8 19 4009200400002 REACTION (94-PU-239(N,ABS),,ALF) 4009200400003 SAMPLE Sample thickness was equal to 1.45E-2 nuclei/barn 4009200400004 MONITOR (94-PU-239(N,ABS),,ALF) Normalization was made on 4009200400005 calculated value of alpha thermal. 4009200400006 Alpha thermal value was calculated from evaluated 4009200400007 capture and fission cross-section. 4009200400008 INC-SOURCE (REAC) 4009200400009 METHOD (FNB) 2.0 keV energy neutron beam was obtained by 4009200400010 transmission of reactor neutron spectrum through 4009200400011 Sc(219 g/cm2), Ti(6.7 g/cm2) and Cd(0.6 g/cm2) filters 4009200400012 ERR-ANALYS (DATA-ERR) Mean-squared error consists of statistical 4009200400013 measurement error,alpha thermal value uncertainty and 4009200400014 correction on non-monochromatic neutron beam. 4009200400015 HISTORY (19750210A) Final data given 4009200400016 STATUS (TABLE) Table 2 of INDC(CCP)-49,1,1975 4009200400017 Prelim.data in Table 1 of YFI-12,7,1971 - 4009200400018 EN=2.+-0.35 keV, ALF=1.35+-0.09 4009200400019 (COREL,40092007) Data for sample thickness 4009200400020 4.85E-3 nuclei/barn 4009200400021 ENDBIB 19 0 4009200400022 COMMON 3 3 4009200400023 EN-NRM MONIT MONIT-ERR 4009200400024 EV NO-DIM NO-DIM 4009200400025 0.025 0.589 0.027 4009200400026 ENDCOMMON 3 0 4009200400027 DATA 5 1 4009200400028 EN +EN-ERR -EN-ERR DATA DATA-ERR 4009200400029 KEV KEV KEV NO-DIM NO-DIM 4009200400030 2.0 0.3 0.5 1.284 0.066 4009200400031 ENDDATA 3 0 4009200400032 ENDSUBENT 31 0 4009200499999 SUBENT 40092005 20210728 42004009200500001 BIB 8 18 4009200500002 REACTION (94-PU-239(N,ABS),,ALF) 4009200500003 SAMPLE Sample thickness was equal to 4.85E-3 nuclei/barn 4009200500004 MONITOR (94-PU-239(N,ABS),,ALF) Normalization was made on 4009200500005 calculated value of alpha thermal. 4009200500006 Alpha thermal value was calculated from evaluated 4009200500007 capture and fission cross-section. 4009200500008 INC-SOURCE (REAC) 4009200500009 METHOD (FNB) 24.5 keV energy neutron beam was obtained 4009200500010 by transmission of reactor neutron spectrum through 4009200500011 Fe(162 g/cm2), Al(40.5 g/cm2), S(5.7 g/cm2), 4009200500012 B-10(0.2 g/cm2) filters 4009200500013 ERR-ANALYS (DATA-ERR) Mean-squared error consists of statistical 4009200500014 measurement error,alpha thermal value uncertainty and 4009200500015 correction on non-monochromatic neutron beam. 4009200500016 STATUS (TABLE) Table 2 of INDC(CCP)-49,1,1975 4009200500017 Prelim.data in Table 1 of YFI-12,7,1971 - 4009200500018 EN=24.5+-1.0 keV, ALF=0.30+-0.09 4009200500019 HISTORY (19750210A) Final data given 4009200500020 ENDBIB 18 0 4009200500021 COMMON 3 3 4009200500022 EN-NRM MONIT MONIT-ERR 4009200500023 EV NO-DIM NO-DIM 4009200500024 0.25 0.589 0.027 4009200500025 ENDCOMMON 3 0 4009200500026 DATA 5 1 4009200500027 EN +EN-ERR -EN-ERR DATA DATA-ERR 4009200500028 KEV KEV KEV NO-DIM NO-DIM 4009200500029 24.5 0.9 1.6 0.384 0.036 4009200500030 ENDDATA 3 0 4009200500031 ENDSUBENT 30 0 4009200599999 SUBENT 40092006 20210728 42004009200600001 BIB 8 15 4009200600002 REACTION (94-PU-239(N,ABS),,ALF) 4009200600003 SAMPLE Sample thickness was equal to 4.85E-3 nuclei/barn 4009200600004 MONITOR (94-PU-239(N,ABS),,ALF) Normalization was made on 4009200600005 calculated value of alpha thermal. 4009200600006 Alpha thermal value was calculated from evaluated 4009200600007 capture and fission cross-section. 4009200600008 INC-SOURCE (REAC) 4009200600009 METHOD (FNB) 140.0 keV energy neutron beam was obtained 4009200600010 by transmission of reactor neutron spectrum through 4009200600011 Si(118 g/cm2),Ti(7.9 g/cm2) and B-10(2.5 g/cm2) filters4009200600012 ERR-ANALYS (DATA-ERR) Mean-squared error consists of statistical 4009200600013 measurement error,alpha thermal value uncertainty and 4009200600014 correction on non-monochromatic neutron beam. 4009200600015 HISTORY (19750210C) Compiled at the centre 4009200600016 STATUS (TABLE) Table 2 of INDC(CCP)-49,1,1975 4009200600017 ENDBIB 15 0 4009200600018 COMMON 3 3 4009200600019 EN-NRM MONIT MONIT-ERR 4009200600020 EV NO-DIM NO-DIM 4009200600021 0.025 0.589 0.027 4009200600022 ENDCOMMON 3 0 4009200600023 DATA 5 1 4009200600024 EN +EN-ERR -EN-ERR DATA DATA-ERR 4009200600025 KEV KEV KEV NO-DIM NO-DIM 4009200600026 140.0 11.0 17.0 0.122 0.021 4009200600027 ENDDATA 3 0 4009200600028 ENDSUBENT 27 0 4009200699999 SUBENT 40092007 20210728 42004009200700001 BIB 8 17 4009200700002 REACTION (94-PU-239(N,ABS),,ALF) 4009200700003 SAMPLE Sample thickness was equal to 4.85E-3 nuclei/barn 4009200700004 MONITOR (94-PU-239(N,ABS),,ALF) Normalization was made on 4009200700005 calculated value of alpha thermal. 4009200700006 Alpha thermal value was calculated from evaluated 4009200700007 capture and fission cross-section. 4009200700008 INC-SOURCE (REAC) 4009200700009 METHOD (FNB) 2.0 keV energy neutron beam was obtained by 4009200700010 transmission of reactor neutron spectrum through 4009200700011 Sc(219 g/cm2), Ti(6.7 g/cm2) and Cd(0.6 g/cm2) filters 4009200700012 ERR-ANALYS (DATA-ERR) Mean-squared error consists of statistical 4009200700013 measurement error,alpha thermal value uncertainty and 4009200700014 correction on non-monochromatic neutron beam. 4009200700015 HISTORY (19750210C) Compiled at the centre 4009200700016 STATUS (TABLE) Table 2 of YFI-18,3,1974 4009200700017 (COREL,40092004) Data for sample thickness 4009200700018 1.45E-3 nuclei/barn 4009200700019 ENDBIB 17 0 4009200700020 COMMON 3 3 4009200700021 EN-NRM MONIT MONIT-ERR 4009200700022 EV NO-DIM NO-DIM 4009200700023 0.025 0.589 0.027 4009200700024 ENDCOMMON 3 0 4009200700025 DATA 5 1 4009200700026 EN +EN-ERR -EN-ERR DATA DATA-ERR 4009200700027 KEV KEV KEV NO-DIM NO-DIM 4009200700028 2. 0.3 0.5 1.346 0.078 4009200700029 ENDDATA 3 0 4009200700030 ENDSUBENT 29 0 4009200799999 ENDENTRY 7 0 4009299999999