ENTRY 20992 20041221 00002099200000001 SUBENT 20992001 20041221 00002099200100001 BIB 12 23 2099200100002 INSTITUTE (2JPNJAE) 2099200100003 REFERENCE (J,JIN,40,1977,197812) MAIN REFERENCE. 2099200100004 (J,JIN,40,1457,1978) EXPERIMENTAL DETAILS 2099200100005 (P,NEANDC(J)-36L,19,197409) 2099200100006 AUTHOR (T.SEKINE,H.BABA) 2099200100007 TITLE -YIELDS OF NI-66 AND NI-57 IN THE IRRADIATION OF 2099200100008 NICKEL WITH REACTOR NEUTRONS-. 2099200100009 FACILITY (REAC ) THREE DIFFERENT REACTORS, JRR-2, JRR-3 AND 2099200100010 JRR-4 AT THE JAPAN ATOMIC ENERGY RESEARCH INSTITUTE. 2099200100011 INC-SOURCE (REAC ) THE THREE DIFFERENT REACTORS. 2099200100012 SAMPLE .SPECTROSCOPICALLY PURE NICKEL WIRE (0.25 MM IN DIA.) 2099200100013 OR FOIL (0.2 MM THICK). 2099200100014 .CO-AL ALLOY WIRE AS NEUTRON MONITOR. 2099200100015 METHOD (ACTIV) ACTIVATION FOLLOWED BY CHEMICAL SEPARATION. 2099200100016 DETECTOR (GELI ) COAXIAL GE(LI) DETECTOR. 2099200100017 (NAICR) 3 INCH BY 3 INCH NAI(TL) DETECTOR. 2099200100018 PART-DET (DG) DECAY GAMMAS. 2099200100019 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2099200100020 HISTORY (19790731C) CN. 2099200100021 (19790827E) 2099200100022 (19840106U) A.P.T. JAPAN CODE CHANGED TO JPN 2099200100023 (19840106E) 2099200100024 (20041221U) Dates corrected and energy added 2099200100025 ENDBIB 23 0 2099200100026 NOCOMMON 0 0 2099200100027 ENDSUBENT 26 0 2099200199999 SUBENT 20992002 20041221 00002099200200001 BIB 6 18 2099200200002 REACTION (28-NI-65(N,G)28-NI-66,,SIG,,MXW) 2099200200003 INC-SPECT .EPITHERMAL NEUTRON ENERGY AND NEUTRON FLUX WERE 2099200200004 CONVERTED IN nv0 AND r*SQRT(T/T0) IN ACCORDANCE WITH 2099200200005 WESTCOTT CONVENTION, SEE REF. 2 2099200200006 .THE THERMAL NEUTRON FLUX WAS OBTAINED FROM THE RADIO- 2099200200007 ACTIVITY OF CO-60 PRODUCED IN THE FLUX MONITOR. 2099200200008 DECAY-DATA (28-NI-66,54.8HR,DG,1039.,0.09) 2099200200009 (28-NI-65,2.564HR,DG) 2099200200010 (28-NI-57,36.0HR,DG,1921.,0.14) 2099200200011 MONITOR (27-CO-59(N,G)27-CO-60,,SIG) 2099200200012 STATUS .DATA TAKEN FROM TEXT. 2099200200013 ERR-ANALYS (ERR-T) .THE ERRORS QUOTED WERE ESTIMATED BY TAKING 2099200200014 INTO ACCOUNT THE UNCERTAINTIES INVOLVED IN 2099200200015 (ERR-1) THE COUNTING EFFICIENCY ERROR (1.5 PERCENT), 2099200200016 (ERR-2) THE CHEMICAL YIELD ERROR (1.5 %) 2099200200017 (ERR-3) THE NEUTRON FLUX ERROR (2.5 %). 2099200200018 THE STANDARD DEVIATION OF THE PEAK AREA IN THE GAMMA 2099200200019 RAY SPECTRUM WAS NOT INCLUDED 2099200200020 ENDBIB 18 0 2099200200021 COMMON 1 3 2099200200022 EN-DUMMY 2099200200023 EV 2099200200024 2.5300E-02 2099200200025 ENDCOMMON 3 0 2099200200026 DATA 5 1 2099200200027 DATA ERR-T ERR-1 ERR-2 ERR-3 2099200200028 B B PER-CENT PER-CENT PER-CENT 2099200200029 2.0400E+01 2.4000E+00 1.5 1.5 2.5 2099200200030 ENDDATA 3 0 2099200200031 ENDSUBENT 30 0 2099200299999 SUBENT 20992003 20041221 00002099200300001 BIB 6 12 2099200300002 REACTION (28-NI-65(N,G)28-NI-66,,RI) 2099200300003 INC-SPECT .EPITHERMAL NEUTRON ENERGY AND NEUTRON FLUX WERE 2099200300004 CONVERTED IN nv0 AND r*SQRT(T/T0) IN ACCORDANCE WITH 2099200300005 WESTCOTT CONVENTION, SEE REF. 2 2099200300006 .THE THERMAL NEUTRON FLUX WAS OBTAINED FROM THE RADIO- 2099200300007 ACTIVITY OF CO-60 PRODUCED IN THE FLUX MONITOR. 2099200300008 DECAY-DATA (28-NI-66,54.8HR,DG,1039.,0.09) 2099200300009 (28-NI-65,2.564HR,DG) 2099200300010 (28-NI-57,36.0HR,DG,1921.,0.14) 2099200300011 MONITOR (27-CO-59(N,G)27-CO-60,,SIG) 2099200300012 STATUS .DATA TAKEN FROM TEXT. 2099200300013 ERR-ANALYS .ERRORS NOT GIVEN 2099200300014 ENDBIB 12 0 2099200300015 NOCOMMON 0 0 2099200300016 DATA 2 1 2099200300017 EN-MIN DATA-MAX 2099200300018 EV B 2099200300019 2.5300E-02 6.0000E+01 2099200300020 ENDDATA 3 0 2099200300021 ENDSUBENT 20 0 2099200399999 SUBENT 20992004 20041221 00002099200400001 BIB 7 9 2099200400002 REACTION (28-NI-58(N,2N)28-NI-57,,SIG,,FIS) 2099200400003 INC-SPECT .FAST NEUTRON FLUX FROM REACTOR. 2099200400004 DECAY-DATA (28-NI-57,36.0HR,DG,1921.,0.14) 2099200400005 MONITOR (28-NI-58(N,P)27-CO-58-G,,SIG,,FIS) USING THE CROSS 2099200400006 SECTION VALUE OF 113 +- 7 MB. 2099200400007 COMMENT .MEASURED CROSS SECTION IS A MEAN VALUE OF 4 DIF- 2099200400008 FERENT RUNS. 2099200400009 STATUS .DATA TAKEN FROM TEXT. 2099200400010 ERR-ANALYS .NO INFORMATION GIVEN. 2099200400011 ENDBIB 9 0 2099200400012 COMMON 3 3 2099200400013 EN-DUMMY MONIT MONIT-ERR 2099200400014 MEV MB MB 2099200400015 1.5000E+00 1.1300E+02 7.0000E+00 2099200400016 ENDCOMMON 3 0 2099200400017 DATA 2 1 2099200400018 DATA DATA-ERR 2099200400019 MB MB 2099200400020 3.8000E-03 5.0000E-04 2099200400021 ENDDATA 3 0 2099200400022 ENDSUBENT 21 0 2099200499999 ENDENTRY 4 0 2099299999999