ENTRY 30790 20010404 00003079000000001 SUBENT 30790001 20010404 00003079000100001 BIB 12 27 3079000100002 TITLE Independent yield of 88Y from thermal neutron induced 3079000100003 fission of 235U 3079000100004 AUTHOR (Sun Jianguo,Guo Jingru,Wang Fangding) 3079000100005 INSTITUTE (3CPRAEP) 3079000100006 REFERENCE (J,JRN/L,108,347,198703) 3079000100007 SAMPLE Weight:0.3 g; composition: 15% metallic Mg, 85% U02 3079000100008 enriched to 10% U-235 3079000100009 FACILITY (REAC,3CPRAEP) swimming-pool type 3079000100010 INC-SPECT thermal neutron flux = 10**12 n/cm2/sec; 3079000100011 irradiation time: 10 days. 3079000100012 METHOD (RCHEM)after about 1 month cooling time 3079000100013 (GSPEC)sample placed in 1 g/cm2 polyethylene container 3079000100014 to reduce bremsstrahlung. 3079000100015 3 hour live-time counting repeated 34 time (total: 102 3079000100016 hours counting time) 3079000100017 DETECTOR (GELI)of 130 cm3, resolution: 2 keV at 1332 keV, with 3079000100018 Canberra 2001 preamplifier, Canberra 2010 amplifier, 3079000100019 Canberra SCORPIO-3000 multichannel analyzer system. 3079000100020 (SCIN) FH-1914 beta plastic scintillator for measuring 3079000100021 the activity of the Y-91 monitor. 3079000100022 ANALYSIS Program library SPAL used for automatic peak search, 3079000100023 energy calibration and photopeak area determination. 3079000100024 Counting efficiency determined with Y-88 standard, 3079000100025 which was also used for continuous check of stability. 3079000100026 CORRECTION made for counting efficiency, decay during irradiation 3079000100027 and cooling time and degree of saturation. 3079000100028 HISTORY (20010404C) ML 3079000100029 ENDBIB 27 0 3079000100030 NOCOMMON 0 0 3079000100031 ENDSUBENT 30 0 3079000199999 SUBENT 30790002 20010404 00003079000200001 BIB 5 11 3079000200002 REACTION (92-U-235(N,F)39-Y-88,IND,FY,,MXW) 3079000200003 MONITOR (92-U-235(N,F)39-Y-91-G,CUM,FY,,MXW) 3079000200004 MONIT-REF (,B.F.RIDER,R,NEDO-12154-3/C,1980) 3079000200005 DECAY-DATA (39-Y-88,106.61D) 3079000200006 (39-Y-91-G,58.5D) 3079000200007 from: General Electric cahrt of the nuclides, 13th ed. 3079000200008 (1984). 3079000200009 ANALYSIS No peak was seen in the fission product spectrum. The 3079000200010 upper limit was derived from the background count rate 3079000200011 in the energy range where the Y-88 gamma-ray peak 3079000200012 should be. 3079000200013 ENDBIB 11 0 3079000200014 COMMON 2 3 3079000200015 EN-DUMMY MONIT 3079000200016 EV PC/FIS 3079000200017 0.0253 5.93 3079000200018 ENDCOMMON 3 0 3079000200019 DATA 1 1 3079000200020 DATA-MAX 3079000200021 PC/FIS 3079000200022 1.53E-8 3079000200023 ENDDATA 3 0 3079000200024 ENDSUBENT 23 0 3079000299999 ENDENTRY 2 0 3079099999999