ENTRY 14196 20120816 13851419600000001 SUBENT 14196001 20120816 13851419600100001 BIB 7 19 1419600100002 TITLE Tritium and alpha-particle yields in fast and 1419600100003 thermal neutron fission of 235U 1419600100004 AUTHOR (M.J.Fluss,N.D.Dudey,R.L.Malewicki) 1419600100005 INSTITUTE (1USAANL) 1419600100006 REFERENCE (J,PR/C,6,2252,1972) 1419600100007 SAMPLE (92-U-235,ENR=0.998) 1419600100008 For radiochemical measurements enriched 235U metal 1419600100009 (99.8 at.%) was cast into ingots in a graphite mold, 1419600100010 hot rolled into plates 2 or 62.5 mil thick, and 1419600100011 1-cm-diam disks were punched from the annealed plates. 1419600100012 For on-line measurements the 235U target (200 to 1419600100013 1000 mu-g) was deposited on a thick platinum backing 1419600100014 DETECTOR (PROPC) For off-line measurement the tritium gas was 1419600100015 separated from uranium sample by tritium separation 1419600100016 apparatus. Separated hydrogen gas was counted in a 1419600100017 low level internal gas proportional counter and 1419600100018 tritium yield was determined 1419600100019 HISTORY (20110202C) Compiled by S.H. 1419600100020 (20120816A) SD: Data in Subent 4 were multiplied by 10.1419600100021 ENDBIB 19 0 1419600100022 NOCOMMON 0 0 1419600100023 ENDSUBENT 22 0 1419600199999 SUBENT 14196002 20110202 13761419600200001 BIB 6 11 1419600200002 REACTION (92-U-235(N,F)1-H-3,TER,FY) 1419600200003 STATUS (CURVE) data taken from fig. 2 of the reference 1419600200004 ERR-ANALYS (ERR-S) Statistical uncertainty 1419600200005 METHOD (EDE) For in-beam measurement E-dE technique was used 1419600200006 (RCHEM) Tritium yield was determined off-line using 1419600200007 radiochemical separation technique. 1419600200008 FLAG (1.0) Particle identification technique 1419600200009 (2.0) Radiochemical technique 1419600200010 FACILITY (CCW,1USAANL) The fast-neutron irradiations were 1419600200011 carried out on the Argonne National Laboratory 1419600200012 Dynamitron and fast-neutron generator facilities. 1419600200013 ENDBIB 11 0 1419600200014 NOCOMMON 0 0 1419600200015 DATA 4 19 1419600200016 EN DATA ERR-S FLAG 1419600200017 KEV PC/FIS PC/FIS NO-DIM 1419600200018 166.9 1.94E-02 3.70E-03 1.0 1419600200019 205.1 2.70E-02 4.00E-03 1.0 1419600200020 281.9 2.43E-02 3.10E-03 1.0 1419600200021 299.0 2.16E-02 2.00E-03 1.0 1419600200022 342.8 2.55E-02 2.90E-03 1.0 1419600200023 342.8 2.49E-02 2.30E-03 1.0 1419600200024 368.8 1.53E-02 5.00E-03 1.0 1419600200025 380.4 1.89E-02 1.90E-03 2.0 1419600200026 425.3 2.01E-02 1.70E-03 1.0 1419600200027 448.1 1.66E-02 2.50E-03 1.0 1419600200028 456.2 1.78E-02 1.50E-03 1.0 1419600200029 482.6 1.86E-02 6.70E-03 2.0 1419600200030 499.8 1.92E-02 4.30E-03 1.0 1419600200031 546.9 2.00E-02 6.10E-03 2.0 1419600200032 557.2 1.78E-02 1.70E-03 1.0 1419600200033 618.4 2.71E-02 8.00E-03 2.0 1419600200034 626.1 1.81E-02 4.20E-03 1.0 1419600200035 701.2 3.25E-02 4.10E-03 2.0 1419600200036 769.6 1.70E-02 1.60E-03 2.0 1419600200037 ENDDATA 21 0 1419600200038 ENDSUBENT 37 0 1419600299999 SUBENT 14196003 20110202 13761419600300001 BIB 5 7 1419600300002 REACTION (92-U-235(N,F)1-H-3,TER,FY,,MXW) 1419600300003 STATUS (TABLE) data taken from tab. 1 of the reference 1419600300004 ERR-ANALYS (ERR-S) Statistical uncertainty 1419600300005 METHOD (RCHEM) Tritium yield was determined off-line using 1419600300006 radiochemical separation technique. 1419600300007 FACILITY (REAC,1USAANL) The thermal-neutron irradiations were 1419600300008 made in the Argonne thermal source reactor. 1419600300009 ENDBIB 7 0 1419600300010 COMMON 1 3 1419600300011 EN-DUMMY 1419600300012 EV 1419600300013 0.025 1419600300014 ENDCOMMON 3 0 1419600300015 DATA 2 1 1419600300016 DATA ERR-S 1419600300017 PC/FIS PC/FIS 1419600300018 0.85E-2 0.09E-2 1419600300019 ENDDATA 3 0 1419600300020 ENDSUBENT 19 0 1419600399999 SUBENT 14196004 20120816 13851419600400001 BIB 6 14 1419600400002 REACTION (92-U-235(N,F)2-HE-4,TER,FY) 1419600400003 STATUS (CURVE) data taken from fig. 3 of PR/C,6,2252,1972 1419600400004 FACILITY (CCW,1USAANL) The fast-neutron irradiations were 1419600400005 carried out on the Argonne National Laboratory 1419600400006 Dynamitron and fast-neutron generator facilities. 1419600400007 INC-SOURCE (P-LI7) Monoenergetic neutrons are produced by 1419600400008 irradiating lithium metal targets with accelerated 1419600400009 protons. The neutron intensities on target varied 1419600400010 between 1 x 10**7 and 5 x 10**8 n/cm2 sec depending 1419600400011 upon accelerator operating conditions and the 1419600400012 Li(p,n) excitation function. 1419600400013 ERR-ANALYS (ERR-S) Statistical uncertainty 1419600400014 HISTORY (20120816A) SD: Data were multiplied by 10. 1419600400015 INC-SOURCE and EN-RSL were added. 1419600400016 ENDBIB 14 0 1419600400017 COMMON 2 3 1419600400018 ERR-S EN-RSL 1419600400019 PER-CENT KEV 1419600400020 5.0 50. 1419600400021 ENDCOMMON 3 0 1419600400022 DATA 2 12 1419600400023 EN DATA 1419600400024 KEV PC/FIS 1419600400025 169.9 2.45E-01 1419600400026 214.5 2.45E-01 1419600400027 288.6 2.52E-01 1419600400028 305.7 2.48E-01 1419600400029 347.9 2.55E-01 1419600400030 350.5 2.33E-01 1419600400031 373.7 2.07E-01 1419600400032 431.7 2.24E-01 1419600400033 456.8 2.24E-01 1419600400034 458.5 2.60E-01 1419600400035 504.4 1.67E-01 1419600400036 574.5 2.14E-01 1419600400037 ENDDATA 14 0 1419600400038 ENDSUBENT 37 0 1419600499999 ENDENTRY 4 0 1419699999999