ENTRY 12798 19831202 00001279800000001 SUBENT 12798001 19831202 00001279800100001 BIB 10 16 1279800100002 INSTITUTE (1USAANL) 1279800100003 REFERENCE (C,82ANTWER,,740,8209) 1279800100004 (R,ANL-NDM-64,8201) 1279800100005 AUTHOR (J.W.MEADOWS,C.BUDTZ-JORGENSEN) 1279800100006 TITLE THE FISSION FRAGMENT ANGULAR DISTRIBUTIONS AND TOTAL 1279800100007 KINETIC ENERGIES FOR 235-U(N,F) FROM .18 TO 8.83 MEV 1279800100008 FACILITY (DYNAM) 1279800100009 METHOD (TOF) 1279800100010 DETECTOR (FISCH) DOUBLE-GRIDDED ION CHAMBER 1279800100011 SAMPLE ENRICHED 235-U (99.86 PERCENT) DEPOSITED ON CATHODES 1279800100012 IN SPOT 2.5 CM IN DIAMETER. THICKNESS 76 MICROGRAM/ 1279800100013 (CM)2 IN 0 DEGREE DETECTOR AND 54 IN 180 DEGREE 1279800100014 DETECTOR. 1279800100015 STATUS (APRVD) APPROVED BY J.W.MEADOWS, 83/2/7. 1279800100016 HISTORY (830104C) 1279800100017 (831202U) BIB UPDATE. 1279800100018 ENDBIB 16 0 1279800100019 NOCOMMON 0 0 1279800100020 ENDSUBENT 19 0 1279800199999 SUBENT 12798002 19830127 00001279800200001 BIB 5 9 1279800200002 REACTION (92-U-235(N,F),,DA,FF,RSD) 1279800200003 N-SOURCE (P-LI7) 1279800200004 CORRECTION DATA WERE CORRECTED SECONDARY SOURCE REACTIONS AND 1279800200005 ANGULAR DISTRIBUTION DISTORTION DUE TO SAMPLE 1279800200006 THICKNESS 1279800200007 ANALYSIS AVERAGE OF RELATIVE YIELDS FROM FORWARD AND BACKWARD 1279800200008 DETECTORS FITTED BY EQUATION OF THE FORM - 1279800200009 W(THETA)=1+B COS**2(THETA) 1279800200010 ERR-ANALYS (ERR-S) STATISTICAL UNCERTAINTY ONLY 1279800200011 ENDBIB 9 0 1279800200012 COMMON 1 3 1279800200013 ANG 1279800200014 ADEG 1279800200015 0. 1279800200016 ENDCOMMON 3 0 1279800200017 DATA 4 18 1279800200018 EN EN-RSL-FW DATA ERR-S 1279800200019 MEV MEV NO-DIM NO-DIM 1279800200020 0.179 0.024 0.97 0.015 1279800200021 0.298 0.024 1.017 0.016 1279800200022 0.467 0.022 1.067 0.016 1279800200023 0.598 0.021 1.093 0.016 1279800200024 0.748 0.020 1.079 0.016 1279800200025 0.896 0.020 1.119 0.016 1279800200026 1.046 0.020 1.097 0.016 1279800200027 1.108 0.020 1.147 0.016 1279800200028 1.459 0.034 1.163 0.012 1279800200029 1.992 0.030 1.214 0.012 1279800200030 2.491 0.028 1.201 0.013 1279800200031 2.990 0.026 1.159 0.016 1279800200032 3.254 0.047 1.168 0.020 1279800200033 3.490 0.024 1.160 0.016 1279800200034 3.760 0.044 1.153 0.020 1279800200035 3.964 0.024 1.178 0.016 1279800200036 4.274 0.041 1.155 0.020 1279800200037 4.514 0.040 1.174 0.020 1279800200038 ENDDATA 20 0 1279800200039 ENDSUBENT 38 0 1279800299999 SUBENT 12798003 19831202 00001279800300001 BIB 6 10 1279800300002 REACTION (92-U-235(N,F),,DA,FF,RSD) 1279800300003 N-SOURCE (D-D) 1279800300004 CORRECTION DATA WERE CORRECTED SECONDARY SOURCE REACTIONS AND 1279800300005 ANGULAR DISTRIBUTION DISTORTION DUE TO SAMPLE 1279800300006 THICKNESS. 1279800300007 ANALYSIS AVERAGE OF RELATIVE YIELDS FROM FORWARD AND BACKWARD 1279800300008 DETECTORS FITTED BY EQUATION OF THE FORM - 1279800300009 W(THETA)=1+B COS**2(THETA) 1279800300010 ERR-ANALYS (ERR-S) STATISTICAL UNCERTAINTY ONLY 1279800300011 HISTORY (831202A) BIB CORRECTION. 1279800300012 ENDBIB 10 0 1279800300013 COMMON 1 3 1279800300014 ANG 1279800300015 ADEG 1279800300016 0. 1279800300017 ENDCOMMON 3 0 1279800300018 DATA 4 15 1279800300019 EN EN-RSL-FW DATA ERR-S 1279800300020 MEV MEV NO-DIM NO-DIM 1279800300021 5.19 0.14 1.153 0.025 1279800300022 5.48 0.13 1.174 0.023 1279800300023 5.76 0.11 1.155 0.022 1279800300024 6.04 0.10 1.168 0.021 1279800300025 6.31 0.09 1.243 0.020 1279800300026 6.58 0.08 1.374 0.035 1279800300027 6.84 0.08 1.376 0.032 1279800300028 7.10 0.08 1.364 0.031 1279800300029 7.36 0.08 1.296 0.024 1279800300030 7.61 0.08 1.395 0.028 1279800300031 7.86 0.07 1.335 0.027 1279800300032 8.12 0.07 1.379 0.027 1279800300033 8.36 0.07 1.353 0.028 1279800300034 8.58 0.07 1.401 0.028 1279800300035 8.83 0.07 1.380 0.027 1279800300036 ENDDATA 17 0 1279800300037 ENDSUBENT 36 0 1279800399999 SUBENT 12798004 19830127 00001279800400001 BIB 7 12 1279800400002 REACTION (92-U-235(N,F),,AKE,FF) 1279800400003 N-SOURCE (P-LI7) 1279800400004 ASSUMED THE AVERAGE KINETIC ENERGY OF FISSION FRAGMENTS 1279800400005 FROM THERMAL NEUTRON FISSION WAS ASSUMED TO BE 1279800400006 170. MEV. THE QUANTITY DETERMINED IN THE EXPERIMENT 1279800400007 WAS AKE(THERMAL) - AKE(EN). 1279800400008 CORRECTION DATA WERE CORRECTED SECONDARY SOURCE REACTIONS AND 1279800400009 BACKGROUND NEUTRONS. 1279800400010 ANALYSIS DATA WERE AVERAGE OF FORWARD AND BACKWARD DETECTORS 1279800400011 ERR-ANALYS (ERR-S) STATISTICAL UNCERTAINTY ONLY 1279800400012 STATUS COLUMN 5 OF TABLE II IN ANL/NDM-64 MISLABELED, SHOULD 1279800400013 BE DELTA E(BAR). 1279800400014 ENDBIB 12 0 1279800400015 NOCOMMON 0 0 1279800400016 DATA 4 18 1279800400017 EN EN-RSL-FW DATA ERR-S 1279800400018 MEV MEV MEV MEV 1279800400019 0.179 0.024 170.269 0.200 1279800400020 0.298 0.024 170.073 0.200 1279800400021 0.467 0.022 169.947 0.200 1279800400022 0.598 0.021 170.357 0.199 1279800400023 0.748 0.020 170.326 0.200 1279800400024 0.896 0.020 170.134 0.197 1279800400025 1.046 0.020 170.484 0.197 1279800400026 1.108 0.020 170.128 0.200 1279800400027 1.459 0.034 170.267 0.143 1279800400028 1.992 0.030 170.201 0.141 1279800400029 2.491 0.028 170.042 0.146 1279800400030 2.990 0.026 170.039 0.178 1279800400031 3.254 0.047 170.026 0.219 1279800400032 3.490 0.024 170.160 0.178 1279800400033 3.760 0.044 169.966 0.221 1279800400034 3.964 0.024 170.017 0.178 1279800400035 4.274 0.041 169.980 0.211 1279800400036 4.514 0.040 169.558 0.221 1279800400037 ENDDATA 20 0 1279800400038 ENDSUBENT 37 0 1279800499999 SUBENT 12798005 19830127 00001279800500001 BIB 7 12 1279800500002 REACTION (92-U-235(N,F),,AKE,FF) 1279800500003 N-SOURCE (D-D) 1279800500004 ASSUMED THE AVERAGE KINETIC ENERGY OF FISSION FRAGMENTS 1279800500005 FROM THERMAL NEUTRON FISSION WAS ASSUMED TO BE 1279800500006 170. MEV. THE QUANTITY DETERMINED IN THE EXPERIMENT 1279800500007 WAS AKE(THERMAL) - AKE(EN). 1279800500008 CORRECTION DATA WERE CORRECTED SECONDARY SOURCE REACTIONS AND 1279800500009 BACKGROUND NEUTRONS. 1279800500010 ANALYSIS DATA WERE AVERAGE OF FORWARD AND BACKWARD DETECTORS 1279800500011 ERR-ANALYS (ERR-S) STATISTICAL UNCERTAINTY ONLY 1279800500012 STATUS COLUMN 5 OF TABLE II IN ANL/NDM-64 MISLABELED, SHOULD 1279800500013 BE DELTA E(BAR). 1279800500014 ENDBIB 12 0 1279800500015 NOCOMMON 0 0 1279800500016 DATA 4 15 1279800500017 EN EN-RSL-FW DATA ERR-S 1279800500018 MEV MEV MEV MEV 1279800500019 5.19 0.14 169.150 0.292 1279800500020 5.48 0.13 169.531 0.264 1279800500021 5.76 0.11 169.356 0.256 1279800500022 6.04 0.10 168.955 0.240 1279800500023 6.31 0.09 169.425 0.241 1279800500024 6.58 0.08 169.167 0.256 1279800500025 6.84 0.08 168.988 0.245 1279800500026 7.10 0.08 169.337 0.231 1279800500027 7.36 0.08 168.637 0.228 1279800500028 7.61 0.08 169.244 0.216 1279800500029 7.86 0.07 169.075 0.218 1279800500030 8.12 0.07 169.485 0.207 1279800500031 8.36 0.07 169.070 0.204 1279800500032 8.58 0.07 169.305 0.202 1279800500033 8.83 0.07 169.293 0.192 1279800500034 ENDDATA 17 0 1279800500035 ENDSUBENT 34 0 1279800599999 ENDENTRY 5 0 1279899999999