ENTRY 10902 19841205 00001090200000001 SUBENT 10902001 19841205 00001090200100001 BIB 15 50 1090200100002 INSTITUTE (1USAANL) 1090200100003 REFERENCE (J,NSE,76,61,8010) 1090200100004 (W,SMITH,8003) 1090200100005 AUTHOR (D.L.SMITH,J.W.MEADOWS) 1090200100006 TITLE ACTIVATION CROSS SECTIONS FOR 66-ZN(N,PROTON)CU-66 1090200100007 FACILITY (DYNAM) ANL FAST NEUTRON GENERATOR 1090200100008 SAMPLE NATURAL ZINC DISKS, 2.54-CM DIAMETER AND 0.32-CM THICK 1090200100009 WITH AVERAGE MASS OF 11.5-GMS. 1090200100010 INC-SOURCE (P-LI7) PROTONS ON LITHIUM FOR NEUTRONS OF 5.8-MEV 1090200100011 AND BELOW 1090200100012 (D-D) DEUTERONS ON DEUTERIUM GAS AT 2-ATM FOR NEUTRONS 1090200100013 FROM 4.7 TO 10-MEV. 1090200100014 DETECTOR (NAICR) SODIUM IODIDE SCINTILLATION DETECTOR FOR GAMMA 1090200100015 DETECTION 1090200100016 (FISCH) FISSION CHAMBER USING A 2.54-CM DIAMETER 1090200100017 DEPOSIT OF DEPLETED URANIUM-238. 1090200100018 DECAY-DATA (29-CU-66,5.10MIN,DG,1039.,0.08) 1090200100019 MONITOR GAMMAS FROM NA-22 USED TO CALIBRATE NAI DETECTOR 1090200100020 PROTONS ON LI-7, B-11, AND AL-27 USED TO CALIBRATE 1090200100021 NEUTRON ENERGY SCALE. 1090200100022 2(92-U-238(N,F),,SIG) VALUES TAKEN FROM ENDF/B-V TO 1090200100023 OBTAIN ABSOLUTE CROSS SECTION VALUES. 1090200100024 METHOD (ACTIV) ACTIVATION ANALYSIS USED. SAMPLES ATTACHED TO 1090200100025 LOW MASS FISSION DETECTOR. SAMPLE SOURCE DISTANCE IS 1090200100026 3-5 CM. 1090200100027 CORRECTION CORRECTIONS MADE FOR- 1090200100028 -GEOMETRY 1090200100029 -NEUTRON SOURCE CHARACTERISTICS 1090200100030 -ABSORPTION OF NEUTRONS 1090200100031 -MULTIPLE SCATTERING OF NEUTRONS 1090200100032 -TARGET THICKNESS 1090200100033 -DECAY HALF LIFE 1090200100034 -KINEMATICS 1090200100035 -ENERGY DEPENDENCE OF ALL PARAMETERS 1090200100036 ERR-ANALYS (ERR-T) TOTAL UNCERTAINTY BASED ON - 1090200100037 -DETERMINATION OF DETECTOR COUNTS, 4-26 PERCENT 1090200100038 -HALF-LIFE DEPENDENT EFFECTS, 1-2 PERCENT 1090200100039 -GEOMETRIC EFFECTS, 1-2 PERCENT 1090200100040 -NEUTRON SOURCE CHARACTERISTICS, 1-4 PERCENT 1090200100041 -GAMMA RAY DETECTOR EFFICIENCY, 3-PERCENT 1090200100042 -MASS OF URANIUM DEPOSIT, 1-PERCENT 1090200100043 -GAMMA RAY DECAY BRANCHING FACTOR, 12.5-PERCENT 1090200100044 -NEUTRON SCATTERING EFFECTS, APPROX 1-PERCENT 1090200100045 -BACKGROUND EFFECTS, LESS THAN 3-PERCENT 1090200100046 -U-238 FISSION STANDARD CROSS SECTION, APPROX 1090200100047 4-PERCENT 1090200100048 STATUS (APRVD) APPROVED BY D.L.SMITH, 80/5/30. 1090200100049 HISTORY (800428C) 1090200100050 (801030U) REFERENCE UPDATED. 1090200100051 (841205A) BIB, DATA HEADING CORRECTIONS. 1090200100052 ENDBIB 50 0 1090200100053 NOCOMMON 0 0 1090200100054 ENDSUBENT 53 0 1090200199999 SUBENT 10902002 19841205 00001090200200001 BIB 1 2 1090200200002 REACTION 1((30-ZN-66(N,P)29-CU-66,,SIG)/(92-U-238(N,F),,SIG)) 1090200200003 2(30-ZN-66(N,P)29-CU-66,,SIG) 1090200200004 ENDBIB 2 0 1090200200005 COMMON 1 3 1090200200006 MONIT-ERR 1090200200007 PER-CENT 1090200200008 4. 1090200200009 ENDCOMMON 3 0 1090200200010 DATA 7 35 1090200200011 EN EN-RSL-FW DATA 1ERR-T 1DATA 2ERR-T 21090200200012 MONIT 2 1090200200013 MEV MEV NO-DIM PER-CENT MB PER-CENT 1090200200014 MB 1090200200015 4.172 0.271 1.482 -03 26.7 0.8113 27.0 1090200200016 547.5 1090200200017 4.251 0.113 1.849 -03 28.8 1.013 29.0 1090200200018 548.0 1090200200019 4.574 0.080 5.023 -03 15.0 2.747 15.5 1090200200020 546.9 1090200200021 4.626 0.264 4.022 -03 24.4 2.193 24.7 1090200200022 545.2 1090200200023 5.015 0.222 9.123 -03 16.3 4.871 16.8 1090200200024 533.9 1090200200025 5.174 0.082 8.105 -03 15.0 4.363 15.5 1090200200026 538.3 1090200200027 5.365 0.198 1.250 -02 14.6 6.799 15.1 1090200200028 543.7 1090200200029 5.377 0.083 1.011 -02 15.0 5.500 15.5 1090200200030 544.0 1090200200031 5.499 0.197 1.540 -02 14.9 8.428 15.4 1090200200032 547.4 1090200200033 5.561 0.155 1.529 -02 18.7 8.493 19.1 1090200200034 555.3 1090200200035 5.576 0.083 1.814 -02 15.0 10.11 15.5 1090200200036 557.3 1090200200037 5.775 0.084 1.633 -02 15.0 9.525 15.5 1090200200038 583.3 1090200200039 6.022 0.173 2.091 -02 13.8 12.98 14.4 1090200200040 620.7 1090200200041 6.078 0.156 1.874 -02 15.3 12.02 15.8 1090200200042 641.4 1090200200043 6.414 0.125 1.710 -02 15.6 13.31 16.1 1090200200044 778.5 1090200200045 6.724 0.126 1.731 -02 15.1 15.11 15.6 1090200200046 873.1 1090200200047 7.030 0.127 1.576 -02 17.0 14.59 17.4 1090200200048 925.7 1090200200049 7.256 0.204 1.841 -02 14.1 17.59 14.6 1090200200050 955.2 1090200200051 7.257 0.202 1.966 -02 14.1 18.78 14.6 1090200200052 955.4 1090200200053 7.325 0.129 1.839 -02 15.2 17.73 15.7 1090200200054 964.3 1090200200055 7.558 0.215 1.994 -02 14.6 19.69 15.2 1090200200056 987.6 1090200200057 7.558 0.213 2.141 -02 13.9 21.14 14.5 1090200200058 987.6 1090200200059 7.626 0.131 2.077 -02 15.4 20.52 15.9 1090200200060 988.1 1090200200061 7.854 0.216 2.004 -02 15.6 19.84 16.1 1090200200062 989.8 1090200200063 7.854 0.216 2.079 -02 13.3 20.58 13.9 1090200200064 989.8 1090200200065 7.922 0.134 2.151 -02 15.6 21.30 16.1 1090200200066 990.4 1090200200067 7.924 0.134 2.331 -02 14.6 23.09 15.1 1090200200068 990.4 1090200200069 8.218 0.137 2.386 -02 14.8 23.68 15.4 1090200200070 992.6 1090200200071 8.511 0.140 2.821 -02 14.7 28.06 15.2 1090200200072 994.8 1090200200073 8.803 0.143 3.377 -02 14.5 33.67 15.1 1090200200074 996.9 1090200200075 9.093 0.147 3.373 -02 15.8 33.63 16.3 1090200200076 996.9 1090200200077 9.383 0.150 3.815 -02 14.6 37.84 15.2 1090200200078 992.0 1090200200079 9.672 0.154 4.590 -02 14.0 45.32 14.5 1090200200080 987.4 1090200200081 9.864 0.157 4.523 -02 14.7 44.52 15.2 1090200200082 984.2 1090200200083 9.965 0.158 3.961 -02 14.5 38.92 15.0 1090200200084 982.6 1090200200085 ENDDATA 74 0 1090200200086 ENDSUBENT 85 0 1090200299999 ENDENTRY 2 0 1090299999999