ENTRY 21600 19810408 00002160000000001 SUBENT 21600001 19810408 00002160000100001 BIB 14 36 2160000100002 INSTITUTE (2AUSIRK) 2160000100003 REFERENCE (C,78HARWELL,,204,7809) MAIN REFERENCE. 2160000100004 (W,GRABMAYR,800625) DATA. 2160000100005 (T,GRABMAYR,78) THESIS. 2160000100006 AUTHOR (P.GRABMAYR,P.HILLE) 2160000100007 TITLE -GAMMA RAY MULTIPLICITY OF CO-59 AFTER EXCITATION 2160000100008 BY INELASTIC SCATTERING OF 14.5 MEV NEUTRONS-. 2160000100009 FACILITY (CCW ) PULSED COCKROFT-WALTON ACCELERATOR. 2160000100010 INC-SOURCE (D-T ) THE T(D,N) REACTION, USING A TITANIUM- 2160000100011 TRITIUM TARGET. 2160000100012 SAMPLE .285.1 GRAM CO-59 POWDER, 99.99 PERCENT PURITY, 2160000100013 CONTAINED IN A SEMISPHERICAL CAN OF ALUMINUM, 2160000100014 INNER RADIUS 2.4 CM AND OUTER RADIUS 3.5 CM. 2160000100015 METHOD (TOF ) TIME-OF-FLIGHT TECHNIQUES, FLIGHT PATH 2160000100016 1.5 METERS. 2160000100017 DETECTOR (SCIN ) 5 INCH TIMES 1 INCH NE 213 LIQUID 2160000100018 SCINTILLATOR WITH N-GAMMA DISCRIMINATION, PLACED 2160000100019 AT 0 DEGREES. 2160000100020 COMMENT .DUE TO SHAPE OF THE SAMPLE THE CROSS-SECTIONS ARE 2160000100021 NORMALISED TO 90 DEGREES USING DOUBLE DIFFERENTIAL 2160000100022 CROSS-SECTION OF HERMASDORF ET AL (INDC(GRD)-2/L). 2160000100023 .THE NEUTRON FLUX WAS MEASURED, 2160000100024 -BETWEEN RUNS WITH A FAST SCINTILLATOR AND 2160000100025 -ABSOLUTE USING THE DIRECT FLUX. 2160000100026 STATUS .DATA FROM PRIVATE COMMUNICATION AND FROM MAIN 2160000100027 REFERENCE. 2160000100028 HISTORY (800707C) CN. 2160000100029 (800718E) 2160000100030 CORRECTION .FOR- 2160000100031 -DEADTIME OF CFT,TAC AND ADC, 2160000100032 -PILE-UP, 2160000100033 -BACKGROUND, 2160000100034 -MULTIPLE SCATTERING AND 2160000100035 -ABSORBTION IN SAMPLE. 2160000100036 ERR-ANALYS .STATISTICAL ERRORS, ERROR OF CORRECTIONS, ERROR 2160000100037 OF DETECTOR EFFICIENCY AND NORMALISATION ERROR. 2160000100038 ENDBIB 36 0 2160000100039 COMMON 2 3 2160000100040 EN EN-RSL 2160000100041 MEV MEV 2160000100042 1.4500E+01 3.0000E-01 2160000100043 ENDCOMMON 3 0 2160000100044 ENDSUBENT 43 0 2160000199999 SUBENT 21600002 19810408 00002160000200001 BIB 4 6 2160000200002 REACTION (27-CO-59(N,X)0-NN-1,EM,DE) 2160000200003 EN-SEC OUTGOING NEUTRON ENERGIES QUOTED ARE AT THE 2160000200004 CENTROID OF THE 0.5 MEV WIDE BINS. 2160000200005 STATUS .DATA FROM PRIVATE COMMUNICATION. 2160000200006 HISTORY (800707C) 2160000200007 (800718E) 2160000200008 ENDBIB 6 0 2160000200009 NOCOMMON 0 0 2160000200010 DATA 3 15 2160000200011 E DATA DATA-ERR 2160000200012 MEV MB/MEV MB/MEV 2160000200013 9.7000E-01 4.9100E+02 4.7600E+01 2160000200014 1.4600E+00 4.2600E+02 4.1400E+01 2160000200015 1.9600E+00 3.4000E+02 3.3900E+01 2160000200016 2.4500E+00 2.9200E+02 2.9400E+01 2160000200017 2.9500E+00 2.1800E+02 2.2300E+01 2160000200018 3.4500E+00 1.6100E+02 1.6600E+01 2160000200019 3.9500E+00 1.4600E+02 1.5200E+01 2160000200020 4.4500E+00 1.1300E+02 1.2000E+01 2160000200021 4.9500E+00 1.0000E+02 1.0700E+01 2160000200022 5.4500E+00 7.7100E+01 9.5000E+00 2160000200023 5.9600E+00 7.4800E+01 9.3700E+00 2160000200024 6.4600E+00 5.7900E+01 8.0300E+00 2160000200025 6.9600E+00 4.5700E+01 7.6500E+00 2160000200026 7.4600E+00 3.6300E+01 7.4200E+00 2160000200027 7.9700E+00 3.1200E+01 6.8100E+00 2160000200028 ENDDATA 17 0 2160000200029 ENDSUBENT 28 0 2160000299999 SUBENT 21600003 19810408 00002160000300001 BIB 4 8 2160000300002 REACTION (27-CO-59(N,X)0-NN-1,EM,SIG) TOTAL NEUTRON EMISSION 2160000300003 CROSS-SECTION. 2160000300004 ANALYSIS .USING THE HAUSER-FESHBACH CODE STARPE BY M. UHL TO 2160000300005 CALCULATE THE TOTAL NEUTRON EMISSION CROSS-SECTION. 2160000300006 STATUS .DATA FROM MAIN REFERENCE. 2160000300007 (DEP,21600002) 2160000300008 HISTORY (800707C) 2160000300009 (800718E) 2160000300010 ENDBIB 8 0 2160000300011 NOCOMMON 0 0 2160000300012 DATA 2 1 2160000300013 DATA DATA-ERR 2160000300014 MB MB 2160000300015 2.0690E+03 6.9000E+01 2160000300016 ENDDATA 3 0 2160000300017 ENDSUBENT 16 0 2160000399999 SUBENT 21600004 19810408 00002160000400001 BIB 4 6 2160000400002 REACTION (27-CO-59(N,INL)27-CO-59,,SIG) 2160000400003 ADD-RES .USING THE HAUSER-FESHBACH CODE STARPE BY M. UHL TO 2160000400004 CALCULATE THE TOTAL INELASTIC NEUTRON CROSS-SECTION. 2160000400005 STATUS .DATA FROM MAIN REFERENCE. 2160000400006 HISTORY (800707C) 2160000400007 (800718E) 2160000400008 ENDBIB 6 0 2160000400009 NOCOMMON 0 0 2160000400010 DATA 2 1 2160000400011 DATA DATA-ERR 2160000400012 MB MB 2160000400013 4.0200E+02 1.4000E+02 2160000400014 ENDDATA 3 0 2160000400015 ENDSUBENT 14 0 2160000499999 ENDENTRY 4 0 2160099999999