ENTRY 20521 20230228 2052100000001 SUBENT 20521001 20230228 20231011 2052100100001 BIB 13 37 2052100100002 TITLE Delayed-neutrons from arsenic isotopes 84As, 85As 2052100100003 and 86As 2052100100004 AUTHOR (J.-V.Kratz, H.Franz, G.Herrmann) 2052100100005 REFERENCE (J,JIN,35,1407,1973) 2052100100006 REL-REF (O,21273001,J.-V.Kratz+,C,73ROCH,2,95,1973) - new exp.,2052100100007 additional data for As isotopes. 2052100100008 INSTITUTE (2GERMNZ) 2052100100009 FACILITY (REAC,2GERMNZ) Fast pneumatic tube system of the Mainz 2052100100010 reactor 2052100100011 INC-SPECT Thermal neutron flashes of 0.1 sec duration and 2052100100012 about 1.E+14 neutrons/cm2 maximum flux. 2052100100013 SAMPLE 0.50 mg of U-235 and known activity of As-74 (17.7 d)2052100100014 dissolved in 0.1 ml of 0.1 N HNO3 and sealed in small 2052100100015 glass capsules. 2052100100016 METHOD (CHSEP) Two chemical separations : 2052100100017 - by selective absorption, complete within 2.5sec, 2052100100018 - solvent extraction step added, complete within 5.0sec2052100100019 DETECTOR (PROPC) He-3 counter of about 4% efficiency and 2052100100020 3 counts/min background - for neutrons counting. 2052100100021 (NAICR) 3 * 3 inch NaI(Tl) scintillator for As-74 2052100100022 activities. 2052100100023 (GELI) Gamma-ray spectra of short-lived arsenic, 2052100100024 selenium and bromine isotopes by a 40 cm3 Ge(Li) 2052100100025 detector with a resolution of 2.8 keV FWHM at 1332 keV.2052100100026 COMMENT Of authors.The neutron flux was not monitored since the2052100100027 integrated fluxes recorded with a fission chamber were2052100100028 found to be reproducible within +- 3 % . 2052100100029 ERR-ANALYS (DATA-ERR) Errors are 2 standard deviations in article.2052100100030 HISTORY (19740729C) 2052100100031 (19800722A) Minor corrections. 2052100100032 (20170723A) SD:Updated to new date formats,lower case. 2052100100033 MONITOR -> ANALYSIS. Subents 004-006 were added. 2052100100034 (20170805A) M.M. 2052100100035 EN-DUMMY, ELEMENT, ERR-1 were moved in Subents 002,003.2052100100036 BIB information was updated 2052100100037 DATA-ERR was re-calculated from two sigma to one sigma.2052100100038 (20230228U) SD: REL-REF added. 2052100100039 ENDBIB 37 0 2052100100040 NOCOMMON 0 0 2052100100041 ENDSUBENT 40 0 2052100199999 SUBENT 20521002 20170805 22682052100200001 BIB 7 22 2052100200002 REACTION (92-U-235(N,F)ELEM/MASS,DL/CUM,NU,,MXW) 2052100200003 Delayed NU for specific precursors. 2052100200004 DECAY-DATA ((1.)33-AS-84,5.5SEC,DG) ~5.5 sec 2052100200005 ((2.)33-AS-85,2.05SEC,DG) 2.05+-0.05 sec 2052100200006 ((3.)33-AS-86,0.9SEC,DG) 0.9+-0.2 sec 2052100200007 ANALYSIS (DECAY) Neutron decay curve was analyzed 2052100200008 Delayed neutron yields (As-84, 985) were obtained by 2052100200009 comparing the neutron activities in the As fraction 2052100200010 with those of the corresponding delayed-neutron groups 2052100200011 in unseparated samples of U-235, irradiated and 2052100200012 counted under the same conditions. 2052100200013 Delayed neutron yields for As-86 was obtained from 2052100200014 0.8 sec activity amounting ~ 7 % of 2.0 sec component. 2052100200015 MONITOR (92-U-235(N,F),DL/GRP,NU) 2052100200016 From G.R.Keepin,Physics of Nuclear Kinetics,p.90, 2052100200017 Addison-Wesley, Reading,Mass., 1965 2052100200018 ERR-ANALYS (ERR-1) Error in neutron flux 2052100200019 STATUS (TABLE) Table 2 of J.Inorg.Nucl.Chem.,35,1407,1973 2052100200020 Text, page 1414 of JIN,35,1407,1973 2052100200021 HISTORY (19800722A) REACTION corrected. 2052100200022 (20170723A) SD: NO-DIM -> PC/FIS 2052100200023 (20170805A) M.M. ANALYSIS, MONITOR 2052100200024 ENDBIB 22 0 2052100200025 COMMON 3 3 2052100200026 EN-DUMMY ERR-1 ELEMENT 2052100200027 EV PER-CENT NO-DIM 2052100200028 2.5300E-02 3. 33. 2052100200029 ENDCOMMON 3 0 2052100200030 DATA 8 3 2052100200031 MASS DATA +DATA-ERR -DATA-ERR DECAY-FLAG HL-NRM 2052100200032 MONIT MONIT-ERR 2052100200033 NO-DIM PC/FIS PC/FIS PC/FIS NO-DIM SEC 2052100200034 PC/FIS PC/FIS 2052100200035 84. 2. E-04 0.5E-04 0.5E-04 1. 6. 2052100200036 31.0E-02 3.6E-02 2052100200037 85. 7.8E-02 0.6E-02 0.6E-02 2. 2. 2052100200038 62.4E-02 2.6E-02 2052100200039 86. 5.7E-03 1.25E-03 0.75E-03 3. 2052100200040 2052100200041 ENDDATA 10 0 2052100200042 ENDSUBENT 41 0 2052100299999 SUBENT 20521003 20170805 22682052100300001 BIB 8 17 2052100300002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 2052100300003 DECAY-DATA (33-AS-87,0.3SEC,DG) ~0.3 sec 2052100300004 ANALYSIS (DECAY) 2052100300005 - Cumulative fission yield of As-87 was defined from a 2052100300006 fractional yield of 1.8+-0.8 % of this work and a 2052100300007 chain yield of 2.37+-0.05 % (from rel.ref.of A.C.Whal+)2052100300008 ASSUMED (ASSUM,92-U-235(N,F)MASS,CHN,FY,,MXW) 2052100300009 REL-REF (R,,A.C.Whal+,C,69VIENNA,,813,1969) 2052100300010 ERR-ANALYS (ERR-1) Error in neutron flux 2052100300011 STATUS (TABLE) Table 2 of J.Inorg.Nucl.Chem.,35,1407,1973 2052100300012 (DEP,20521007) fractional cumulative yield 2052100300013 Preliminary data on HL and fis. yield of ~0.6sec As-872052100300014 are in Entry 22047 2052100300015 HISTORY (19800722A) REACTION corrected. 2052100300016 (20170723A) SD: NO=DIM -> PC/FIS in DATA section 2052100300017 (20170805A) M.M. ANALYSIS, REL-REF,ASSUMED were added. 2052100300018 Part of data were moved in ASSUMED in Subents 004-006.2052100300019 ENDBIB 17 0 2052100300020 COMMON 5 3 2052100300021 EN-DUMMY ERR-1 MASS ASSUM ASSUM-ERR 2052100300022 EV PER-CENT NO-DIM PC/FIS PC/FIS 2052100300023 2.5300E-02 3. 87. 2.37 0.05 2052100300024 ENDCOMMON 3 0 2052100300025 DATA 3 1 2052100300026 ELEMENT DATA DATA-ERR 2052100300027 NO-DIM PC/FIS PC/FIS 2052100300028 33. 0.04 0.01 2052100300029 ENDDATA 3 0 2052100300030 ENDSUBENT 29 0 2052100399999 SUBENT 20521004 20170805 22682052100400001 BIB 7 17 2052100400002 REACTION (33-AS-84(0,B-)34-SE-84,,PN,,,DERIV) 2052100400003 DECAY-DATA (33-AS-84,5.5SEC,DG) ~5.5 sec 2052100400004 ASSUMED (ASSUM,92-U-235(N,F)33-AS-84,CUM,FY,,MXW) 2052100400005 ANALYSIS Neutron emission probability was defined as 2052100400006 measured delayed neutron yield (Subent 002) divided by 2052100400007 fission cumulative yield of As-84 , 2052100400008 which was determined from fractional cumulative yield 2052100400009 17+-2 % of P.del Marmol, 15.3+-1.2 % of J.-V.Kratz+ and2052100400010 chain yield o.96+-0.02 % from A.C.Wahl+. 2052100400011 REL-REF (R,,P.del Marmol,J,JIN,30,2873,1968) 2052100400012 (R,,A.C.Whal+,C,69VIENNA,,813,1969) 2052100400013 Also J.-V.Kratz+, to be published. 2052100400014 STATUS (TABLE) Table 2 of J.Inorg.Nucl.Chem.,35,1407,1973 2052100400015 (DEP,20521002) Delayed neutron yield. 2052100400016 HISTORY (20170723C) SD 2052100400017 (20170805A) M.M. ANALYSIS, REL-REF, ASSUMED were added,2052100400018 DEP code was added in STATUS 2052100400019 ENDBIB 17 0 2052100400020 NOCOMMON 0 0 2052100400021 DATA 4 1 2052100400022 DATA DATA-ERR ASSUM ASSUM-ERR 2052100400023 NO-DIM NO-DIM PC/FIS PC/FIS 2052100400024 0.0013 0.0003 0.15 0.01 2052100400025 ENDDATA 3 0 2052100400026 ENDSUBENT 25 0 2052100499999 SUBENT 20521005 20170805 22682052100500001 BIB 7 15 2052100500002 REACTION (33-AS-85(0,B-)34-SE-85,,PN,,,DERIV) 2052100500003 DECAY-DATA (33-AS-85,2.05SEC,DG) 2.05+-0.05 sec 2052100500004 ASSUMED (ASSUM,92-U-235(N,F)33-AS-85,CUM,FY,,MXW) 2052100500005 ANALYSIS Neutron emission probability was defined as 2052100500006 measured delayed neutron yield (Subent 002) divided by 2052100500007 fission cumulative yield of As-85 , 2052100500008 which was estimated from the yield systematics int his 2052100500009 mass region (J.-V.Kratz+, to be published) 2052100500010 ERR-ANALYS Errors do not include the uncertainties in 2052100500011 the fission yields. 2052100500012 STATUS (TABLE) Table 2 of J.Inorg.Nucl.Chem.,35,1407,1973 2052100500013 (DEP,20521002) Delayed neutron yield. 2052100500014 HISTORY (20170723C) SD 2052100500015 (20170805A) M.M. ANALYSIS, ASSUMED were added , 2052100500016 DEP code was added in STATUS 2052100500017 ENDBIB 15 0 2052100500018 NOCOMMON 0 0 2052100500019 DATA 3 1 2052100500020 DATA DATA-ERR ASSUM 2052100500021 NO-DIM NO-DIM PC/FIS 2052100500022 0.23 0.015 0.34 2052100500023 ENDDATA 3 0 2052100500024 ENDSUBENT 23 0 2052100599999 SUBENT 20521006 20170805 22682052100600001 BIB 7 15 2052100600002 REACTION (33-AS-86(0,B-)34-SE-86,,PN,,,DERIV) 2052100600003 DECAY-DATA (33-AS-86,0.9SEC,DG) 0.9+-0.2 sec 2052100600004 ASSUMED (ASSUM,92-U-235(N,F)33-AS-86,CUM,FY,,MXW) 2052100600005 ANALYSIS Neutron emission probability was defined as 2052100600006 measured delayed neutron yield (Subent 002) divided by 2052100600007 fission cumulative yield of As-86 , 2052100600008 which was estimated from the yield systematics in this 2052100600009 mass region (J.-V.Kratz+, to be published) 2052100600010 ERR-ANALYS Errors do not include the uncertainties in 2052100600011 the fission yields. 2052100600012 STATUS (TABLE) Table 2 of J.Inorg.Nucl.Chem.,35,1407,1973 2052100600013 (DEP,20521002) Delayed neutron yield. 2052100600014 HISTORY (20170723C) SD 2052100600015 (20170805A) M.M. ANALYSIS was added , 2052100600016 DEP code was added in STATUS 2052100600017 ENDBIB 15 0 2052100600018 NOCOMMON 0 0 2052100600019 DATA 4 1 2052100600020 DATA +DATA-ERR -DATA-ERR ASSUM 2052100600021 NO-DIM NO-DIM NO-DIM PC/FIS 2052100600022 0.038 0.0085 0.005 0.15 2052100600023 ENDDATA 3 0 2052100600024 ENDSUBENT 23 0 2052100699999 SUBENT 20521007 20170805 22682052100700001 BIB 9 14 2052100700002 REACTION ((92-U-235(N,F)33-AS-87,CUM,FY,,MXW)/ 2052100700003 (92-U-235(N,F)MASS,CHN,FY,,MXW)) 2052100700004 RESULT (FRCUM) 2052100700005 DECAY-DATA (33-AS-87,0.3SEC,DG) ~0.3 sec 2052100700006 (35-BR-87,55.SEC) 2052100700007 ANALYSIS (DECAY) 2052100700008 ASSUMED (ASSUM,(92-U-235(N,F)35-BR-87,CUM,FY,,MXW)/ 2052100700009 (92-U-235(N,F)MASS,CHN,FY,,MXW)) 2052100700010 From H.D.Schuessler+ 2052100700011 REL-REF (R,,H.D.Schuessler+,C,69VIENNA,,591,1969) 2052100700012 (A,,G.T.Garvey+,J,RMP,41,S1,1969) 4.+-2. % 2052100700013 ERR-ANALYS (ERR-1) Error in neutron flux 2052100700014 STATUS (TABLE) Text, p.1413 of J.Inorg.Nucl.Chem.,35,1407,19732052100700015 HISTORY (20170805C) M.M. 2052100700016 ENDBIB 14 0 2052100700017 COMMON 2 3 2052100700018 EN-DUMMY ERR-1 2052100700019 EV PER-CENT 2052100700020 2.5300E-02 3. 2052100700021 ENDCOMMON 3 0 2052100700022 DATA 5 1 2052100700023 MASS DATA DATA-ERR ASSUM ASSUM-ERR 2052100700024 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 2052100700025 87. 0.018 0.0045 0.95 0.04 2052100700026 ENDDATA 3 0 2052100700027 ENDSUBENT 26 0 2052100799999 ENDENTRY 7 0 2052199999999