ENTRY 22056 19880804 00002205600000001 SUBENT 22056001 19880804 00002205600100001 BIB 9 20 2205600100002 REFERENCE (J,JIN,33,(11),3649,7111) MAIN REFERENCE. 2205600100003 (C,71CANT,51,7109) 2205600100004 TITLE -INDEPENDENT YIELDS OF I-133, I-134 AND I-135 IN 2205600100005 THE FISSION OF TH-232 INDUCED BY REACTOR NEUTRONS 2205600100006 AND 14.8 MEV NEUTRONS - CHARGE DISTRIBUTION IN 2205600100007 LOW AND MEDIUM ENERGY FISSION. 2205600100008 AUTHOR (H.O.DENSCHLAG,S.M.QAIM) 2205600100009 INSTITUTE (2GERMNZ) EXPERIMENTAL SITE, H.O.D. 2205600100010 (2GERJUL) S.M.Q. 2205600100011 DETECTOR (NAICR) USED FOR GAMMA ACTIVITY MEASUREMENTS OF 2205600100012 THE IODINE ISOTOPES. 2205600100013 (GELI ) USED FOR GAMMA ACTIVITY MEASUREMENTS OF 2205600100014 XE-135. 2205600100015 PART-DET (DG ) 2205600100016 CORRECTION .CORRECTIONS WERE APPLIED FOR CHEMICAL YIELD. 2205600100017 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2205600100018 HISTORY (871105C) N.O. 2205600100019 (871211E) 2205600100020 (880804U) 2205600100021 (880810E) 2205600100022 ENDBIB 20 0 2205600100023 NOCOMMON 0 0 2205600100024 ENDSUBENT 23 0 2205600199999 SUBENT 22056002 19890207 00002205600200001 BIB 11 25 2205600200002 REACTION ((90-TH-232(N,F)ELEM/MASS,IND,FY,,SPA)/ 2205600200003 (90-TH-232(N,F)MASS,CHN,FY,,SPA)) 2205600200004 FLAG (1.) UPPER LIMIT. 2205600200005 MONITOR ((90-TH-232(N,F)ELEM/MASS,CUM,FY,,SPA)/ 2205600200006 (90-TH-232(N,F)MASS,CHN,FY,,SPA)) 2205600200007 FACILITY (REAC ) MAINZ TRIGA REACTOR. IRRADIATION POSITION 2205600200008 COVERED WITH A CADMIUM SHIELD. 2205600200009 INC-SOURCE (REAC ) THERMAL REACTOR. 2205600200010 METHOD (CHSEP) 2205600200011 .FOR THE REACTOR IRRADIATIONS AN AUTOMATIC, FAST 2205600200012 SEPARATION AND RADIOCHEMICAL PURIFICATION METHOD 2205600200013 WAS USED, PRIOR TO GAMMA ACTIVITY MEASUREMENTS. 2205600200014 INC-SPECT .EPI-CADMIUM REACTOR NEUTRONS. THE INTEGRATED 2205600200015 NEUTRON FLUX FOR THE 0.05 SEC IRRADIATION WAS 2205600200016 1.5E+12 NEUTRONS/CM2. 2205600200017 SAMPLE .ABOUT 1 G OF TH-232 IN THE FORM OF NITRATE WAS 2205600200018 USED IN THE AUTOMATIC SEPARATION MEASUREMENTS. 2205600200019 ERR-ANALYS (DATA-ERR) THE QUOTED ERRORS INCLUDE SYSTEMATIC 2205600200020 ERRORS AND CORRESPOND TO A CONFIDENCE LEVEL OF 2205600200021 90 PER-CENT. 2205600200022 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2205600200023 HISTORY (871105C) N.O. 2205600200024 (871211E) 2205600200025 (880804U) 2205600200026 (880810E) 2205600200027 ENDBIB 25 0 2205600200028 COMMON 2 3 2205600200029 EN-MIN EN-MAX 2205600200030 MEV MEV 2205600200031 1.0000E+00 8.0000E+00 2205600200032 ENDCOMMON 3 0 2205600200033 DATA 6 3 2205600200034 ELEMENT MASS DATA DATA-ERR MONIT FLAG 2205600200035 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 2205600200036 5.3000E+01 1.3300E+02 5.0000E-02 1.0000E+00 1.0000E+002205600200037 5.3000E+01 1.3400E+02 3.0000E-02 1.0000E+00 1.0000E+002205600200038 5.3000E+01 1.3500E+02 1.5000E-01 3.0000E-02 9.8000E-01 2205600200039 ENDDATA 5 0 2205600200040 ENDSUBENT 39 0 2205600299999 SUBENT 22056003 19890207 00002205600300001 BIB 10 29 2205600300002 REACTION ((90-TH-232(N,F)ELEM/MASS,IND,FY)/ 2205600300003 (90-TH-232(N,F)MASS,CHN,FY)) 2205600300004 FLAG (1.) UPPER LIMIT. 2205600300005 MONITOR ((90-TH-232(N,F)ELEM/MASS,CUM,FY)/ 2205600300006 (90-TH-232(N,F)MASS,CHN,FY)) 2205600300007 FACILITY (CCW ) COCKCROFT-WALTON ACCELERATOR. 2205600300008 INC-SOURCE (D-T ) NEUTRON FLUX 5.0E+10 NEUTRONS/CM2 SEC. 2205600300009 .IRRADIATION TIMES UP TO 10 SEC FOR THE AUTOMATIC 2205600300010 SEPARATION AND 1 MIN FOR THE MANUAL SEPARATION. 2205600300011 FOR XE-135 MEASUREMENTS THE IRRADIATION TIME WAS 2205600300012 15 MIN. 2205600300013 METHOD (CHSEP) 2205600300014 .FOR THE 14.8 MEV IRRADIATIONS, A SLOWER, MANUAL 2205600300015 SEPARATION TECHNIQUE WAS USED IN ADDITION TO THE 2205600300016 FAST METHOD MENTIONED. 2205600300017 .THE XE-135 YIELD WAS DETERMINED BY DIRECT GAMMA- 2205600300018 RAY SPECTROMETRY. 2205600300019 SAMPLE .ABOUT 1 G OF TH-232 IN THE FORM OF NITRATE WAS 2205600300020 USED IN THE AUTOMATIC SEPARATION MEASUREMENTS. 2205600300021 .ABOUT 4 G OF TH-232 IN THE FORM OF NITRATE WAS 2205600300022 USED IN THE MANUAL SEPARATION MEASUREMENTS. 2205600300023 ERR-ANALYS (DATA-ERR) THE QUOTED ERRORS INCLUDE SYSTEMATIC 2205600300024 ERRORS AND CORRESPOND TO A CONFIDENCE LEVEL OF 2205600300025 90 PER-CENT. 2205600300026 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2205600300027 HISTORY (871105C) N.O. 2205600300028 (871211E) 2205600300029 (880804U) 2205600300030 (880810E) 2205600300031 ENDBIB 29 0 2205600300032 COMMON 2 3 2205600300033 EN EN-RSL 2205600300034 MEV MEV 2205600300035 1.4800E+01 3.0000E-01 2205600300036 ENDCOMMON 3 0 2205600300037 DATA 6 4 2205600300038 ELEMENT MASS DATA DATA-ERR MONIT FLAG 2205600300039 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 2205600300040 5.3000E+01 1.3300E+02 8.0000E-02 2.0000E-02 1.0000E+00 2205600300041 5.3000E+01 1.3400E+02 1.5200E-01 5.0000E-03 1.0000E+00 2205600300042 5.3000E+01 1.3500E+02 4.7000E-01 8.0000E-02 9.8000E-01 2205600300043 5.4000E+01 1.3500E+02 2.0000E-02 1.0000E+002205600300044 ENDDATA 6 0 2205600300045 ENDSUBENT 44 0 2205600399999 SUBENT 22056004 19880804 00002205600400001 BIB 10 19 2205600400002 REACTION (90-TH-232(N,F)MASS,,ZP,,SPA) 2205600400003 FLAG (1.) UPPER LIMIT. 2205600400004 FACILITY (REAC ) MAINZ TRIGA REACTOR. IRRADIATION POSITION 2205600400005 COVERED WITH A CADMIUM SHIELD. 2205600400006 INC-SOURCE (REAC ) THERMAL REACTOR. 2205600400007 INC-SPECT .EPI-CADMIUM REACTOR NEUTRONS. THE INTEGRATED 2205600400008 NEUTRON FLUX FOR THE 0.05 SEC IRRADIATION WAS 2205600400009 1.5E+12 NEUTRONS/CM2. 2205600400010 SAMPLE .ABOUT 1 G OF TH-232 IN THE FORM OF NITRATE WAS 2205600400011 USED IN THE AUTOMATIC SEPARATION MEASUREMENTS. 2205600400012 ASSUMED .WIDTH PARAMETER USED WAS SIGMA = 0.56 +/- 0.06. 2205600400013 ERR-ANALYS (DATA-ERR) THE QUOTED ERRORS INCLUDE ERRORS IN THE 2205600400014 INDEPENDENT YIELDS AS WELL AS ERRORS ARISING FROM 2205600400015 THE UNCERTAINTY IN THE SIGMA VALUE. 2205600400016 STATUS (DEP,22056002) DATA TAKEN FROM MAIN REFERENCE. 2205600400017 HISTORY (871105C) N.O. 2205600400018 (871211E) 2205600400019 (880804U) 2205600400020 (880810E) 2205600400021 ENDBIB 19 0 2205600400022 COMMON 2 3 2205600400023 EN-MIN EN-MAX 2205600400024 MEV MEV 2205600400025 1.0000E+00 8.0000E+00 2205600400026 ENDCOMMON 3 0 2205600400027 DATA 5 3 2205600400028 MASS DATA +DATA-ERR -DATA-ERR FLAG 2205600400029 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 2205600400030 1.3300E+02 5.1580E+01 1.0000E+00 2205600400031 1.3400E+02 5.1450E+01 1.0000E+00 2205600400032 1.3500E+02 5.1930E+01 1.2000E-01 1.5000E-01 2205600400033 ENDDATA 5 0 2205600400034 ENDSUBENT 33 0 2205600499999 SUBENT 22056005 19880804 00002205600500001 BIB 8 20 2205600500002 REACTION (90-TH-232(N,F)MASS,,ZP) 2205600500003 FACILITY (CCW ) COCKCROFT-WALTON ACCELERATOR. 2205600500004 INC-SOURCE (D-T ) NEUTRON FLUX 5.0E+10 NEUTRONS/CM2 SEC. 2205600500005 .IRRADIATION TIMES UP TO 10 SEC FOR THE AUTOMATIC 2205600500006 SEPARATION AND 1 MIN FOR THE MANUAL SEPARATION. 2205600500007 FOR XE-135 MEASUREMENTS THE IRRADIATION TIME WAS 2205600500008 15 MIN. 2205600500009 SAMPLE .ABOUT 1 G OF TH-232 IN THE FORM OF NITRATE WAS 2205600500010 USED IN THE AUTOMATIC SEPARATION MEASUREMENTS. 2205600500011 .ABOUT 4 G OF TH-232 IN THE FORM OF NITRATE WAS 2205600500012 USED IN THE MANUAL SEPARATION MEASUREMENTS. 2205600500013 ASSUMED .WIDTH PARAMETER USED WAS SIGMA = 0.56 +/- 0.06. 2205600500014 ERR-ANALYS (DATA-ERR) THE QUOTED ERRORS INCLUDE ERRORS IN THE 2205600500015 INDEPENDENT YIELDS AS WELL AS ERRORS ARISING FROM 2205600500016 THE UNCERTAINTY IN THE SIGMA VALUE. 2205600500017 STATUS (DEP,22056003) DATA TAKEN FROM MAIN REFERENCE. 2205600500018 HISTORY (871105C) N.O. 2205600500019 (871211E) 2205600500020 (880804U) 2205600500021 (880810E) 2205600500022 ENDBIB 20 0 2205600500023 COMMON 2 3 2205600500024 EN EN-RSL 2205600500025 MEV MEV 2205600500026 1.4800E+01 3.0000E-01 2205600500027 ENDCOMMON 3 0 2205600500028 DATA 4 3 2205600500029 MASS DATA +DATA-ERR -DATA-ERR 2205600500030 NO-DIM NO-DIM NO-DIM NO-DIM 2205600500031 1.3300E+02 5.1720E+01 1.4000E-01 1.8000E-01 2205600500032 1.3400E+02 5.1930E+01 7.0000E-02 7.0000E-02 2205600500033 1.3500E+02 5.2510E+01 2.6000E-01 1.3000E-01 2205600500034 ENDDATA 5 0 2205600500035 ENDSUBENT 34 0 2205600599999 ENDENTRY 5 0 2205699999999