ENTRY 12717 19830330 00001271700000001 SUBENT 12717001 19830330 00001271700100001 BIB 15 37 1271700100002 INSTITUTE (1USANBS,2AUSIRK,1USAANL) 1271700100003 REFERENCE (J,NSE,78,415,8108) 1271700100004 AUTHOR (G.WINKLER,V.SPIEGEL,C.M.EISENHAUER,D.L.SMITH) 1271700100005 TITLE MEASUREMENT OF THE AVERAGE ACTIVATION CROSS SECTION FOR1271700100006 THE REACTION 63-CU(N,ALPHA)60-CO IN THE SPONTANEOUS 1271700100007 FISSION NEUTRON FIELD OF CALIFORNIUM-252 1271700100008 FACILITY IRRADIATION- NATIONAL BUREAU OF STANDARDS INDOOR 1271700100009 IRRADIATION FACILITY 1271700100010 COUNTING- ARGONNE LOW LEVEL COUNTING ROOM 1271700100011 N-SOURCE (CF252) 1271700100012 SAMPLE DISKS OF NATURAL COPPER, 25.40-MM DIAMETER, 3.19-MM 1271700100013 THICK 1271700100014 DETECTOR (NAICR) PAIR OF 7.62 BY 7.62-CM NAI(TL) DETECTORS 1271700100015 PLACED ON EITHER SIDE OF SAMPLE. 1271700100016 ACTIVATED SAMPLES RECOUNTED 6 MONTHS LATER USING 1271700100017 12.7 BY 12.7-CM WELL-TYPE NAI(TL) DETECTOR. 1271700100018 DECAY-DATA (27-CO-60-G,5.271YR,DG) 1271700100019 INC-SPECT FISSION SPECTRUM OF CF-252 1271700100020 METHOD (ACTIV). COMPENSATED FLUX GEOMETRY USED. STANDARD 1271700100021 RADON-BERYLLIUM SOURCES IN MANGANEOUS SULPHATE BATH 1271700100022 USED TO CALIBRATE NEUTRON SOURCE. 1271700100023 CORRECTION CORRECTIONS MADE FOR SCATTERING, NEUTRON ABSORPTION, 1271700100024 FLUX GRADIENT, AND GEOMETRY 1271700100025 ERR-ANALYS (ERR-T) TOTAL ERROR 1271700100026 (ERR-S) COUNTING STATISTICS AND REPRODUCIBILITY OF 1271700100027 ACTIVATION MEASUREMENT 1271700100028 (ERR-1) GAMMA-RAY DETECTION EFFICIENCY 1271700100029 (ERR-2) SOURCE STRENGTH 1271700100030 (ERR-3) DISTANCE MEASUREMENTS 1271700100031 (ERR-4) CORRECTION FOR NEUTRON SCATTERING DUE TO THE 1271700100032 SOURCE CAPSULE,SOURCE, AND SAMPLE SUPPORT STRUCTURES 1271700100033 (ERR-5) ACTIVATION DECAY RATE FACTOR 1271700100034 (ERR-6) CORRECTION FOR NEUTRON SCATTERING, ABSORPTION, 1271700100035 AND GEOMETRY DUE TO SAMPLE 1271700100036 STATUS NO REPLY TO AUTHOR PROOF. 1271700100037 HISTORY (820105C) 1271700100038 (830330A) CORRECTED DECAY-DATA. 1271700100039 ENDBIB 37 0 1271700100040 NOCOMMON 0 0 1271700100041 ENDSUBENT 40 0 1271700199999 SUBENT 12717002 19830330 00001271700200001 BIB 2 2 1271700200002 REACTION (29-CU-63(N,A)27-CO-60,,SIG,,FIS) 1271700200003 HISTORY (830330A) CORRECTED REACTION. 1271700200004 ENDBIB 2 0 1271700200005 NOCOMMON 0 0 1271700200006 DATA 10 1 1271700200007 EN-DUMMY DATA ERR-T ERR-S ERR-1 ERR-2 1271700200008 ERR-3 ERR-4 ERR-5 ERR-6 1271700200009 MEV MB MB PER-CENT PER-CENT PER-CENT 1271700200010 PER-CENT PER-CENT PER-CENT PER-CENT 1271700200011 1.5 0.709 0.017 0.2 1.5 1.1 1271700200012 0.3 1.0 0.1 1.0 1271700200013 ENDDATA 6 0 1271700200014 ENDSUBENT 13 0 1271700299999 ENDENTRY 2 0 1271799999999