ENTRY 22069 20220215 23092206900000001 SUBENT 22069001 20220215 23092206900100001 BIB 13 34 2206900100002 TITLE Independent isomeric yield ratio of Pm-148 in the 2206900100003 thermal-neutron induced fission of U-233 2206900100004 AUTHOR (H.Umezawa) 2206900100005 REFERENCE (J,JIN,35,353,1973) 2206900100006 (R,JAERI-1103,1966) - method, U-235, 2206900100007 U233(prelim.) results. 2206900100008 INSTITUTE (2JPNJAE) 2206900100009 FACILITY (REAC,2JPNJAE) JRR-3 reactor. 2206900100010 INC-SOURCE (REAC) Graphite reflector region used. 2206900100011 INC-SPECT Well thermalized neutrons. Cadmium ratio for gold 2206900100012 activation was 200. Thermal neutron flux was 2206900100013 2.0 x 10**11 neutrons/cm2/sec. 2206900100014 METHOD (CHSEP) Radiochemical techniques. 2206900100015 (ACTIV) Activity measurement of the fission products. 2206900100016 DETECTOR (GELI) 50 cm3 GeLi detector. Resolution 2.4 keV at 2206900100017 1332 keV. Shielded with lead of thickness 100 mm. 2206900100018 The photopeak efficiency was determined with cali- 2206900100019 brated sources of Co-57, Co-60, Cs-134, Eu-155 and 2206900100020 Au-198. 2206900100021 SAMPLE 20 milli-g of U-233 as uranium-oxide, wrapped in a 2206900100022 piece of copper foil. 2206900100023 100 milli-g of neodymium-oxide (96.16% Nd-146), 2206900100024 used for correction for neutron capture in Pm-147. 2206900100025 The samples, together with a cobalt flux monitor, 2206900100026 were irradiated for 50 hours. 2206900100027 CORRECTION Corrections were applied for the sizable neutron 2206900100028 capture cross section of Pm-147. 2206900100029 COMMENT The thermal neutron flux was measured with a cobalt 2206900100030 monitor. 2206900100031 HISTORY (19871109C) N.O. 2206900100032 (20160725A) SD:Updated to new date formats,lower case. 2206900100033 Corrections in all Subents. 2206900100034 (20220215A) SD: Ref. JAERI-1103 added. Corrections in 2206900100035 all Subents. Subent 004 added. 2206900100036 ENDBIB 34 0 2206900100037 COMMON 1 3 2206900100038 EN-DUMMY 2206900100039 EV 2206900100040 2.5300E-02 2206900100041 ENDCOMMON 3 0 2206900100042 ENDSUBENT 41 0 2206900199999 SUBENT 22069002 20220215 23092206900200001 BIB 5 12 2206900200002 REACTION (92-U-233(N,F)ELEM/MASS,IND,FY,,FRC/SPA) 2206900200003 DECAY-DATA (61-PM-148-G,5.37D,DG,1465.) 2206900200004 (61-PM-148-M,41.3D,DG,551.,,DG,630.) 2206900200005 ERR-ANALYS (DATA-ERR) The quoted errors include statistical 2206900200006 counting errors, scattering among the repeated 2206900200007 counting data, discrepancy between duplicate runs 2206900200008 and an uncertainty of 20% in the amount of 2206900200009 formation via neutron capture. 2206900200010 STATUS (TABLE) Tbl. 1 from J.Inorg.Nucl.Chem.,35(1973)353 2206900200011 HISTORY (20160725U) SD: RESULT was added. 2206900200012 (20220215A) SD: REACTION code updated. RESULT deleted. 2206900200013 STATUS added. 2206900200014 ENDBIB 12 0 2206900200015 NOCOMMON 0 0 2206900200016 DATA 5 2 2206900200017 ELEMENT MASS ISOMER DATA DATA-ERR 2206900200018 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 2206900200019 61. 148. 0. 1.8E-07 5.E-08 2206900200020 61. 148. 1. 7.5E-07 3.E-08 2206900200021 ENDDATA 4 0 2206900200022 ENDSUBENT 21 0 2206900299999 SUBENT 22069003 20220215 23092206900300001 BIB 5 12 2206900300002 REACTION (92-U-233(N,F)61-PM-148-M/T,IND,FY/RAT,,SPA) 2206900300003 DECAY-DATA (61-PM-148-G,5.37D,DG,1465.) 2206900300004 (61-PM-148-M,41.3D,DG,551.,,DG,630.) 2206900300005 ERR-ANALYS (DATA-ERR) The quoted errors include statistical 2206900300006 counting errors, scattering among the repeated 2206900300007 counting data, discrepancy between duplicate runs 2206900300008 and an uncertainty of 20% in the amount of 2206900300009 formation via neutron capture. 2206900300010 STATUS (TABLE) Tbl. 1 from J.Inorg.Nucl.Chem.,35(1973)353 2206900300011 HISTORY (20160725A) SD: SF4=Pm-148m/m+g -> Pm-148m/t in 2206900300012 REACTION code. 2206900300013 (20220215U) SD: STATUS added. 2206900300014 ENDBIB 12 0 2206900300015 NOCOMMON 0 0 2206900300016 DATA 2 1 2206900300017 DATA DATA-ERR 2206900300018 NO-DIM NO-DIM 2206900300019 0.80 0.06 2206900300020 ENDDATA 3 0 2206900300021 ENDSUBENT 20 0 2206900399999 SUBENT 22069004 20220215 23092206900400001 BIB 4 5 2206900400002 REACTION (92-U-235(N,F)61-PM-148,IND,FY,,FRC/SPA) 2206900400003 DECAY-DATA (61-PM-148-G,5.37D,DG,1465.) 2206900400004 (61-PM-148-M,41.3D,DG,551.,,DG,630.) 2206900400005 STATUS (TABLE) Tbl. 3 from JAERI-1103. 2206900400006 HISTORY (20220215C) SD 2206900400007 ENDBIB 5 0 2206900400008 NOCOMMON 0 0 2206900400009 DATA 1 1 2206900400010 DATA-MAX 2206900400011 NO-DIM 2206900400012 3.5E-06 2206900400013 ENDDATA 3 0 2206900400014 ENDSUBENT 13 0 2206900499999 ENDENTRY 4 0 2206999999999