ENTRY 10900 19841205 00001090000000001 SUBENT 10900001 19841205 00001090000100001 BIB 15 50 1090000100002 INSTITUTE (1USAANL) 1090000100003 REFERENCE (J,NSE,76,43,8010) 1090000100004 AUTHOR (D.L.SMITH,J.W.MEADOWS) 1090000100005 TITLE CROSS SECTION MEASUREMENT FOR THE CR-52(N,PROTON)V-52 1090000100006 REACTION NEAR THRESHOLD 1090000100007 FACILITY ARGONNE FAST NEUTRON GENERATOR 1090000100008 INC-SOURCE (D-D) DEUTERONS ON DEUTERIUM GAS 1090000100009 SAMPLE SOLID CHROMIUM CYLINDER, MASS OF 86.76-GRAMS APPROX 1090000100010 10-CM FROM NEUTRON SOURCE. 1090000100011 DETECTOR (GELI) TRUE COAXIAL GERMANIUM-LITHIUM DETECTOR IN 1090000100012 MASSIVE SHIELD. VOLUME IS APPROX 100-CC. LOCATED 1090000100013 APPROX 100-CM FROM SAMPLE, 90-DEG FROM BEAM. 1090000100014 (FISCH) U-238(93.90-PERCENT),U-233(6.09-PERCENT), 1090000100015 U-235(0.01-PERCENT) FISSION CHAMBER FOR NEUTRON FLUX 1090000100016 MEASUREMENT. 1090000100017 DECAY-DATA (23-V-52,3.75MIN,DG,1434.) 1090000100018 MONITOR (92-U-235(N,F),,SIG) FROM ENDF/B-V 1090000100019 CORRESPONDING ENERGY AND RESOLUTION GIVEN UNDER 1090000100020 MISCELLANEOUS DATA (SEE MISC-COL). 1090000100021 METHOD (ACTIV). ENERGY SCALE OF ACCELERATOR CALIBRATED USING 1090000100022 PROTON BEAM AND OBSERVING REACTION THRESHOLDS FOR 1090000100023 PROTONS ON LI-7, B-11, AND AL-27. CRYSTAL CONTROLLED 1090000100024 DELAY CIRCUIT USED TO INTRODUCE A DELAY TO ALLOW 1090000100025 SCATTERED NEUTRON BACKGROUND TO DIE AWAY. 1090000100026 CORRECTION CORRECTED FOR GEOMETRY, NEUTRON SOURCE CHARACTERISTICS,1090000100027 ABORPTION AND MULTIPLE SCATTERING OF NEUTRONS, 1090000100028 ABSORPTION OF GAMMAS, TARGET THICKNESS, AND DECAY 1090000100029 HALF-LIFE. 1090000100030 ERR-ANALYS SOURCE OF ERRORS IN MEASURED RATIO INCLUDE- 1090000100031 -DETERMINATION DETECTOR COUNTS, 2-16 PERCENT 1090000100032 -GEOMETRIC EFFECTS, 3-PERCENT 1090000100033 -NEUTRON SOURCE CHARACTERISTICS, 3-PERCENT 1090000100034 -GAMMA-RAY DETECTOR EFFICIENCY, 4-PERCENT 1090000100035 -MASS OF URANIUM DEPOSIT, 1-PERCENT 1090000100036 -GAMMA RAY ABSORPTION IN CHROMIUM, 2-PERCENT 1090000100037 -NEUTRON ABSORPTION IN CHROMIUM, 2-PERCENT 1090000100038 -NEUTRON MULTIPLE SCATTERING IN CHROMIUM, 2-PERCENT 1090000100039 -HALF LIFE AND DUTY CYCLE, 2-PERCENT 1090000100040 -BACKGROUND EFFECTS, 1-4 PERCENT 1090000100041 -GAMMA DECAY BRANCHING FACTOR, 1-PERCENT 1090000100042 TOTAL RMS ERROR, 8-18 PERCENT 1090000100043 SYSTEMATIC ERROR, APPROX 8-PERCENT 1090000100044 ERROR IN U-238 FISSION CROSS SECTIONS ASSUMED TO BE 1090000100045 APPROX 5-PERCENT. 1090000100046 STATUS (APRVD) APPROVED BY D.L.SMITH,80/5/15. 1090000100047 HISTORY (790412C) 1090000100048 (800419A) REFERENCE UPDATE. 1090000100049 (800820U) BIB CORRECTION. 1090000100050 (801030U) REFERENCE UPDATED. 1090000100051 (841205A) COMMON DELETED, DATA HEADINGS CORRECTED. 1090000100052 ENDBIB 50 0 1090000100053 NOCOMMON 0 0 1090000100054 ENDSUBENT 53 0 1090000199999 SUBENT 10900002 19841205 00001090000200001 BIB 3 7 1090000200002 REACTION 1((24-CR-52(N,P)23-V-52,,SIG)/(92-U-238(N,F),,SIG)) 1090000200003 2(24-CR-52(N,P)23-V-52,,SIG) 1090000200004 MISC-COL (MISC) RESOLUTION FOR NEUTRONS INCIDENT ON FISSION 1090000200005 CHAMBER. 1090000200006 HISTORY (800419A) DATA REPLACED WITH AUTHORS UPDATED 1090000200007 RENORMALIZATION 1090000200008 (801030A) BIB, DATA-HEADING CORRECTIONS. 1090000200009 ENDBIB 7 0 1090000200010 COMMON 1 3 1090000200011 MONIT-ERR 1090000200012 PER-CENT 1090000200013 5. 1090000200014 ENDCOMMON 3 0 1090000200015 DATA 9 22 1090000200016 EN EN-RSL-FW DATA 1DATA-ERR 1DATA 2DATA-ERR 21090000200017 EN-NRM 2MISC 2MONIT 2 1090000200018 MEV MEV NO-DIM PER-CENT B PER-CENT 1090000200019 MEV MEV B 1090000200020 5.337 0.198 5.877 -03 18.0 0.3184 -02 18.7 1090000200021 5.301 0.232 0.5418 1090000200022 5.563 0.185 1.373 -02 11.0 0.7564 -02 12.1 1090000200023 5.527 0.218 0.5509 1090000200024 5.786 0.171 1.758 -02 9.9 0.1019 -01 11.1 1090000200025 5.746 0.206 0.5795 1090000200026 5.896 0.167 1.789 -02 10.3 0.1062 -01 11.4 1090000200027 5.856 0.202 0.5938 1090000200028 6.003 0.162 2.162 -02 9.6 0.1314 -01 10.8 1090000200029 5.962 0.196 0.6076 1090000200030 6.112 0.158 2.227 -02 9.2 0.1422 -01 10.5 1090000200031 6.070 0.193 0.6384 1090000200032 6.161 0.156 2.294 -02 9.2 0.1502 -01 10.5 1090000200033 6.114 0.192 0.6547 1090000200034 6.324 0.149 3.168 -02 8.7 0.2285 -01 10.0 1090000200035 6.280 0.186 0.7213 1090000200036 6.534 0.141 3.162 -02 8.6 0.2545 -01 9.9 1090000200037 6.488 0.180 0.8048 1090000200038 6.742 0.136 3.021 -02 8.5 0.2614 -01 9.8 1090000200039 6.695 0.175 0.8653 1090000200040 6.934 0.131 3.451 -02 8.4 0.3125 -01 9.7 1090000200041 6.885 0.173 0.9055 1090000200042 7.137 0.127 3.343 -02 8.5 0.3119 -01 9.8 1090000200043 7.086 0.172 0.9330 1090000200044 7.359 0.124 3.760 -02 8.4 0.3616 -01 9.8 1090000200045 7.306 0.173 0.9618 1090000200046 7.558 0.121 3.657 -02 8.5 0.3610 -01 9.8 1090000200047 7.504 0.176 0.9871 1090000200048 7.759 0.120 3.934 -02 8.4 0.3890 -01 9.8 1090000200049 7.700 0.180 0.9887 1090000200050 7.958 0.118 4.110 -02 8.4 0.4070 -01 9.7 1090000200051 7.897 0.185 0.9902 1090000200052 8.157 0.117 4.106 -02 8.4 0.4072 -01 9.8 1090000200053 8.099 0.191 0.9917 1090000200054 8.354 0.116 4.273 -02 8.3 0.4244 -01 9.7 1090000200055 8.292 0.198 0.9932 1090000200056 8.552 0.116 4.391 -02 8.3 0.4367 -01 9.7 1090000200057 8.487 0.206 0.9946 1090000200058 8.747 0.117 4.645 -02 8.3 0.4626 -01 9.7 1090000200059 8.681 0.215 0.9960 1090000200060 8.748 0.117 4.913 -02 8.3 0.4893 -01 9.7 1090000200061 8.680 0.213 0.9960 1090000200062 8.943 0.117 5.211 -02 8.4 0.5198 -01 9.8 1090000200063 8.875 0.225 0.9975 1090000200064 ENDDATA 48 0 1090000200065 ENDSUBENT 64 0 1090000299999 ENDENTRY 2 0 1090099999999