ENTRY 21531 20120917 22342153100000001 SUBENT 21531001 20120917 22342153100100001 BIB 10 32 2153100100002 INSTITUTE (2BLGGHT) Gent. 2153100100003 REFERENCE (J,NIM,134,299,197604) 2153100100004 (P,INDC(SEC)-51,17,197512) To be analysed. 2153100100005 (P,INIS-MF-1933,1975) Abst. 2153100100006 AUTHOR (H.Thierens,D.De Frenne,E.Jacobs,A.De Clercq,P.D'Hondt,2153100100007 A.J.Deruytter) 2153100100008 TITLE Study of the catcherfoil technique with the aid of 2153100100009 Cf-252 spontaneous fission and U-235 thermal neutron 2153100100010 fission 2153100100011 FACILITY (REAC,2BLGGHT) U-235 irradiation at BR2 reactor 2153100100012 METHOD (ACTIV) Catcherfoil technique, activity of decay 2153100100013 gammas of fission products. 2153100100014 DETECTOR (GELI ) 19 cm*3 Ge(Li) detector for gammas from 2153100100015 fission products of Cf-252., also 30 cm*3 Ge(Li) 2153100100016 detector used in U-235 measurements. 2153100100017 COMMENT .Table 1 gives a large number of fission product 2153100100018 decay parameters used in the analysis of both the 2153100100019 mass chain and independent yields. 2153100100020 ERR-ANALYS (DATA-ERR) One standard deviation. 2153100100021 Error principally from: 2153100100022 (ERR-1) the uncertainty in detector efficiency (5%), 2153100100023 * statistical error generally negligible, 2153100100024 * error on time measurements neglected, 2153100100025 * errors on branching ratios and half lives 2153100100026 not included. 2153100100027 HISTORY (19800520C) 2153100100028 (19800603E) 2153100100029 (19800729A) decay-data in subents 004,005 corrected. 2153100100030 (19800808E) 2153100100031 (20120917A) SD: Updated to new date formats,lower case.2153100100032 Corrected according last EXFOR rules and Dict. 2153100100033 BIB update. 2153100100034 ENDBIB 32 0 2153100100035 COMMON 1 3 2153100100036 ERR-1 2153100100037 PER-CENT 2153100100038 5. 2153100100039 ENDCOMMON 3 0 2153100100040 ENDSUBENT 39 0 2153100199999 SUBENT 21531002 20120917 22342153100200001 BIB 6 18 2153100200002 REACTION (92-U-235(N,F)MASS,CHN,FY,,MXW) Thermal neutron 2153100200003 mass chain yields. 2153100200004 INC-SPECT .Maxwellian thermal neutron spectrum ( beam of BR2) 2153100200005 SAMPLE (92-U-235,ENR=0.97) U-235 foil consisted of 15 mg/cm*22153100200006 uranium as U3O8, enriched to 97% U-235, on a 1 mm 2153100200007 thick aluminium disk, diameter 40 mm. 2153100200008 ANALYSIS (CHGDS) .Mass yields are normalised to a total yield 2153100200009 of 200, for those mass chains not measured directly a 2153100200010 best fitted curve was drawn through all 2153100200011 experimentally determined points. 2153100200012 CORRECTION .Except in a very few cases the contribution of 2153100200013 the stable isotope of each mass chain is neglected, 2153100200014 only for mass 134 and 135 a small correction of 2153100200015 less than 1.3% is made. 2153100200016 .For the U-235 target thickness of 15 mg/cm*2, a 2153100200017 correction factor corresponding to the mean range 2153100200018 is included for each mass. 2153100200019 STATUS (TABLE) .Table 3, Nucl.Instr.&Meth.134,299. 2153100200020 ENDBIB 18 0 2153100200021 COMMON 1 3 2153100200022 EN-DUMMY 2153100200023 EV 2153100200024 2.5300E-02 2153100200025 ENDCOMMON 3 0 2153100200026 DATA 3 37 2153100200027 MASS DATA DATA-ERR 2153100200028 NO-DIM PC/FIS PC/FIS 2153100200029 8.5000E+01 1.3300E+00 7.0000E-02 2153100200030 8.7000E+01 2.4200E+00 1.4000E-01 2153100200031 8.8000E+01 3.4600E+00 2.1000E-01 2153100200032 8.9000E+01 4.4500E+00 1.7000E-01 2153100200033 9.1000E+01 6.4700E+00 2.3000E-01 2153100200034 9.2000E+01 6.2400E+00 2.5000E-01 2153100200035 9.3000E+01 6.4400E+00 2.9000E-01 2153100200036 9.4000E+01 6.3500E+00 3.1000E-01 2153100200037 9.5000E+01 6.5900E+00 2.1000E-01 2153100200038 9.7000E+01 5.7400E+00 1.9000E-01 2153100200039 9.9000E+01 6.3200E+00 2.2000E-01 2153100200040 1.0100E+02 5.5000E+00 2.0000E-01 2153100200041 1.0300E+02 3.1000E+00 1.6000E-01 2153100200042 1.0400E+02 1.8000E+00 9.0000E-02 2153100200043 1.0500E+02 9.3600E-01 3.8000E-02 2153100200044 1.0600E+02 3.5600E-01 6.0000E-02 2153100200045 1.1500E+02 1.3000E-02 5.0000E-03 2153100200046 1.2700E+02 1.2900E-01 1.0000E-02 2153100200047 1.2800E+02 2.8400E-01 3.5000E-02 2153100200048 1.2900E+02 8.1700E-01 4.7000E-02 2153100200049 1.3100E+02 2.9000E+00 1.5000E-01 2153100200050 1.3200E+02 4.1300E+00 2.1000E-01 2153100200051 1.3300E+02 6.2900E+00 2.9000E-01 2153100200052 1.3400E+02 7.2900E+00 2.0000E-01 2153100200053 1.3500E+02 6.1800E+00 1.9000E-01 2153100200054 1.3700E+02 6.2400E+00 4.0000E-01 2153100200055 1.3800E+02 6.2000E+00 3.0000E-01 2153100200056 1.4000E+02 6.8000E+00 2.1000E-01 2153100200057 1.4100E+02 6.2500E+00 3.9000E-01 2153100200058 1.4200E+02 6.0000E+00 3.1000E-01 2153100200059 1.4300E+02 5.7900E+00 3.0000E-01 2153100200060 1.4400E+02 5.5800E+00 2.9000E-01 2153100200061 1.4600E+02 2.9400E+00 1.2000E-01 2153100200062 1.4700E+02 2.2100E+00 1.1000E-01 2153100200063 1.4900E+02 1.0870E+00 5.6000E-02 2153100200064 1.5100E+02 4.0600E-01 2.8000E-02 2153100200065 1.5300E+02 1.4300E-01 1.6000E-02 2153100200066 ENDDATA 39 0 2153100200067 ENDSUBENT 66 0 2153100299999 SUBENT 21531003 20120917 22342153100300001 BIB 5 15 2153100300002 REACTION (98-CF-252(0,F)MASS,CHN,FY) Spontaneous fission 2153100300003 mass chain yields. 2153100300004 SAMPLE .Cf-252 source prepared by self-transfer method 2153100300005 at C.B.N.M. Geel, intensity 1.2 10**6 fis/min, 2153100300006 active layer 10 mm, mounted on a 0.5 mm aluminium 2153100300007 disk. 2153100300008 ANALYSIS (CHGDS) .Mass yields are normalised to a total yield 2153100300009 of 200%. For mass chains not directly measured 2153100300010 a best fit curve was drawn through all experimentally 2153100300011 determined points. 2153100300012 CORRECTION .Except in very few cases the contribution of the 2153100300013 stable isotopes is neglected. Only for mass chains 2153100300014 134 and 135 is a small correction of less than 1.3% 2153100300015 necessary. 2153100300016 STATUS (TABLE) .Table 2, Nucl.Instr.&Meth.134,299. 2153100300017 ENDBIB 15 0 2153100300018 NOCOMMON 0 0 2153100300019 DATA 3 43 2153100300020 MASS DATA DATA-ERR 2153100300021 NO-DIM PC/FIS PC/FIS 2153100300022 8.5000E+01 1.1000E-01 2.0000E-02 2153100300023 8.8000E+01 3.0000E-01 3.0000E-02 2153100300024 9.1000E+01 4.8000E-01 3.0000E-02 2153100300025 9.2000E+01 7.1000E-01 7.0000E-02 2153100300026 9.4000E+01 1.0600E+00 1.2000E-01 2153100300027 9.5000E+01 1.1900E+00 4.0000E-02 2153100300028 9.7000E+01 1.6100E+00 6.0000E-02 2153100300029 9.9000E+01 2.7800E+00 1.2000E-01 2153100300030 1.0100E+02 4.0000E+00 2.1000E-01 2153100300031 1.0300E+02 5.2100E+00 2.6000E-01 2153100300032 1.0400E+02 5.5700E+00 2.9000E-01 2153100300033 1.0500E+02 6.1300E+00 1.5000E-01 2153100300034 1.0600E+02 5.9300E+00 3.6000E-01 2153100300035 1.0700E+02 6.6100E+00 3.7000E-01 2153100300036 1.0900E+02 6.0000E+00 4.9000E-01 2153100300037 1.1100E+02 5.1700E+00 3.2000E-01 2153100300038 1.1200E+02 4.6900E+00 2.4000E-01 2153100300039 1.1300E+02 4.8800E+00 3.0000E-01 2153100300040 1.1500E+02 2.9800E+00 1.8000E-01 2153100300041 1.1700E+02 1.5600E+00 1.3000E-01 2153100300042 1.2700E+02 1.3800E-01 1.3000E-02 2153100300043 1.2800E+02 2.6000E-01 2.7000E-03 2153100300044 1.2900E+02 5.7000E-01 7.0000E-02 2153100300045 1.3100E+02 1.6100E+00 9.0000E-02 2153100300046 1.3200E+02 2.1300E+00 1.6000E-01 2153100300047 1.3300E+02 3.0900E+00 1.6000E-01 2153100300048 1.3400E+02 3.6500E+00 1.5000E-01 2153100300049 1.3500E+02 4.5000E+00 1.4000E-01 2153100300050 1.3700E+02 5.4200E+00 3.6000E-01 2153100300051 1.3800E+02 5.2500E+00 1.9000E-01 2153100300052 1.4000E+02 5.5000E+00 2.2000E-01 2153100300053 1.4100E+02 6.1300E+00 3.6000E-01 2153100300054 1.4200E+02 6.1900E+00 5.2000E-01 2153100300055 1.4300E+02 6.1300E+00 3.1000E-01 2153100300056 1.4400E+02 6.2100E+00 3.8000E-01 2153100300057 1.4600E+02 5.1800E+00 3.2000E-01 2153100300058 1.4700E+02 4.1000E+00 2.1000E-01 2153100300059 1.4900E+02 2.7400E+00 2.0000E-01 2153100300060 1.5100E+02 1.9900E+00 1.3000E-01 2153100300061 1.5300E+02 1.3100E+00 8.0000E-02 2153100300062 1.5500E+02 8.3800E-01 3.5000E-02 2153100300063 1.5600E+02 6.1400E-01 3.9000E-02 2153100300064 1.5700E+02 5.6000E-01 6.0000E-02 2153100300065 ENDDATA 45 0 2153100300066 ENDSUBENT 65 0 2153100399999 SUBENT 21531004 20120917 22342153100400001 BIB 7 19 2153100400002 REACTION ((92-U-235(N,F)ELEM/MASS,IND,FY,,MXW)/ 2153100400003 (92-U-235(N,F)MASS,CHN,FY,,MXW)) 2153100400004 Fractional independent yields relative to the total 2153100400005 chain yield. 2153100400006 SAMPLE (92-U-235,ENR=0.97) U-235 foil consisted of 15 mg/cm*22153100400007 uranium as U3O8, enriched to 97% U-235, on a 1 mm 2153100400008 thick aluminium disk, diameter 40 mm. 2153100400009 INC-SPECT Maxwellian thermal neutron spectrum. 2153100400010 DECAY-DATA ((1.)53-I-134-G,52.6MIN,DG,621.8,0.106, 2153100400011 DG,847.0,0.956, 2153100400012 DG,884.1,0.654, 2153100400013 DG,1072.6,0.153) 2153100400014 ((2.)54-XE-135-G,9.083HR,DG,249.79,0.904) 2153100400015 RESULT (FRIND) 2153100400016 STATUS (TABLE) .Table 5, Nucl.Instr.&Meth.134,299. 2153100400017 HISTORY (19800729A) DECAY-DATA corrected 2153100400018 (19800808E) 2153100400019 (20120917A) SD: SF4=ELEM/MASS -> MASS in denominator 2153100400020 of REACTION code 2153100400021 ENDBIB 19 0 2153100400022 COMMON 1 3 2153100400023 EN-DUMMY 2153100400024 EV 2153100400025 2.5300E-02 2153100400026 ENDCOMMON 3 0 2153100400027 DATA 5 2 2153100400028 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 2153100400029 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 2153100400030 5.3000E+01 1.3400E+02 1.3000E-01 3.0000E-02 1.0000E+00 2153100400031 5.4000E+01 1.3500E+02 5.0000E-02 6.0000E-03 2.0000E+00 2153100400032 ENDDATA 4 0 2153100400033 ENDSUBENT 32 0 2153100499999 SUBENT 21531005 20120917 22342153100500001 BIB 6 16 2153100500002 REACTION ((98-CF-252(0,F)ELEM/MASS,IND,FY)/ 2153100500003 (98-CF-252(0,F)MASS,CHN,FY)) 2153100500004 fractional independent yields relative to the total 2153100500005 chain yield. 2153100500006 SAMPLE .Cf-252 source prepared by self-transfer method 2153100500007 at C.B.N.M. Geel, intensity 1.2 10*6 fis/min, active 2153100500008 layer 10 mm, mounted on a 0.5 mm aluminium disk. 2153100500009 DECAY-DATA ((1.)53-I-134-G,52.6MIN,DG,621.8,0.106, 2153100500010 DG,847.0,0.956, 2153100500011 DG,884.1,0.654, 2153100500012 DG,1072.6,0.153) 2153100500013 ((2.)54-XE-135-G,9.083HR,DG,249.79,0.904) 2153100500014 RESULT (FRIND) 2153100500015 STATUS (TABLE) .Table 4, Nucl.Instr.&Meth.134,299. 2153100500016 HISTORY (19800729A) DECAY-DATA corrected 2153100500017 (19800808E) 2153100500018 ENDBIB 16 0 2153100500019 NOCOMMON 0 0 2153100500020 DATA 5 2 2153100500021 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 2153100500022 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 2153100500023 5.3000E+01 1.3400E+02 2.7000E-01 6.0000E-02 1.0000E+00 2153100500024 5.4000E+01 1.3500E+02 8.7000E-02 1.0000E-02 2.0000E+00 2153100500025 ENDDATA 4 0 2153100500026 ENDSUBENT 25 0 2153100599999 ENDENTRY 5 0 2153199999999