ENTRY 21887 19850826 00002188700000001 SUBENT 21887001 19850826 00002188700100001 BIB 15 42 2188700100002 INSTITUTE (2SWDTLU)EXPERIMENTAL SITE IN SWEDEN 2188700100003 (2FR BRC)EXPERIMENTAL SITE IN FRANCE S.J.,G.G.,D.M.D. 2188700100004 (2FR GRA) F.R. 2188700100005 REFERENCE (J,NP/A,382,71,8206)RESULTS,CROSS SECTIONS AND ANGULAR 2188700100006 DISTRIBUTIONS,COMPARED TO DSD AND CN CALCULATIONS. 2188700100007 (P,KDK-37,31,8004)REACTION MECHANISM STUDY. 2188700100008 (P,KDK-42,37,8104)ANGULAR DISTRIBUTIONS. 2188700100009 (P,KDK-53,27,8206)RESULTS COMP TO DSD AND CN CALC. 2188700100010 (P,KDK-64,26,8305)ANGULAR DISTRIBUTIONS. 2188700100011 (W,LINDHOLM,8310) NUMERICAL DATA. 2188700100012 AUTHOR (S.JOLY,G.GRENIER,D.M.DRAKE,I.BERGQVIST,D.K.MCDANIELS, 2188700100013 A.LINDHOLM,L.NILSSON,N.OLSSON,A.WAHEED,R.ZORRO, 2188700100014 F.RIGAUD) 2188700100015 TITLE -STUDY OF THE PB-208(N,G0)PB-209 REACTION BETWEEN 2188700100016 0.8 AND 7.7 MEV- 2188700100017 FACILITY (VDGT ,2SWDTLU)6 MV TANDEM ACCELERATOR 2188700100018 (VDG ,2FR BRC)4 MV VAN DE GRAAFF ACCELERATOR 2188700100019 INC-SOURCE (P-T )0.8-3.0 MEV NEUTRON ENERGY, SOLID TARGET 2188700100020 (D-D )3.2-7.7 MEV NEUTRON ENERGY, GAS TARGET 2188700100021 SAMPLE .436 GRAM OF ENRICHED (98.7 PERCENT) 208-PB FORMED AS A2188700100022 SOLID CYLINDER AT BRC AND AS A HOLLOW CYLINDER AT TLU2188700100023 METHOD .GAMMA-RAY SPECTRA RECORDED. 2188700100024 BACKGROUND REDUCTION USING TOF TECHNIQUES. 2188700100025 DETECTOR (NAICR) 2188700100026 ANALYSIS (4PI1A)UNFOLDING OF GAMMA-RAY SPECTRA USING THE RESPONS2188700100027 FUNCTIONS OF THE DETECTORS. RESULTS WERE DISPLAYED IN 2188700100028 UNITS OF THE DIFFERENTIAL CROSS SECTION AT 90 DEGREES 2188700100029 MULTIPLIED BY 4PI. 2188700100030 REL-REF (R,10226000,I.BERGQVIST+,J,NP/A,191,641,7209) 2188700100031 STATUS .DATA TAKEN FROM PRIVATE COMMUNICATION. 2188700100032 HISTORY (831025C) 2188700100033 (840202E) 2188700100034 (850325U)HH 2188700100035 (850419E) 2188700100036 CORRECTION .FOR - 2188700100037 NEUTRON AND GAMMA ATTENUATION IN THE SAMPLE 2188700100038 MULTIPLE SCATTERING OF NEUTRONS IN THE SAMPLE 2188700100039 NEUTRON SOURCE ANISOTROPY OVER THE SAMPLE. 2188700100040 ERR-ANALYS .LARGE ERRORS,ESPECIALLY AROUND 3 MEV NEUTRON ENERGY 2188700100041 BECAUSE OF BACKGROUND FROM THERMAL CAPTURE OF 2188700100042 NEUTRONS IN THE NAI-CRYSTAL. 2188700100043 NEUTRON ENERGY SPREAD OVER SAMPLE LESS THAN 150 KEV 2188700100044 ENDBIB 42 0 2188700100045 NOCOMMON 0 0 2188700100046 ENDSUBENT 45 0 2188700199999 SUBENT 21887002 19850826 00002188700200001 BIB 3 6 2188700200002 REACTION (82-PB-208(N,G)82-PB-209,PAR,DA,,4PI)DIFF.CROSS 2188700200003 SECTIONS TO THE GROUND STATE IN PB-209*4PI 2188700200004 FLAG (1.) RESULT FROM EXPERIMENT AT 2SWDTLU 2188700200005 (2.) RESULT FROM EXPERIMENT AT 2FR BRC 2188700200006 HISTORY (831025C) 2188700200007 (840202E) 2188700200008 ENDBIB 6 0 2188700200009 COMMON 2 3 2188700200010 E-LVL-FIN ANG 2188700200011 MEV ADEG 2188700200012 0.0000E+00 9.0000E+01 2188700200013 ENDCOMMON 3 0 2188700200014 DATA 4 12 2188700200015 EN DATA DATA-ERR FLAG 2188700200016 MEV MICRO-B MICRO-B NO-DIM 2188700200017 8.0000E-01 1.0600E+03 2.0000E+02 2.0000E+00 2188700200018 1.7000E+00 1.0600E+03 1.7000E+02 2.0000E+00 2188700200019 2.5000E+00 8.3000E+02 1.4000E+02 2.0000E+00 2188700200020 3.2000E+00 8.9000E+02 3.1500E+02 2.0000E+00 2188700200021 3.8000E+00 4.7500E+02 8.5000E+01 2.0000E+00 2188700200022 5.0000E+00 1.9500E+02 3.0000E+01 2.0000E+00 2188700200023 5.7000E+00 2.3600E+02 5.9000E+01 1.0000E+00 2188700200024 5.9000E+00 2.1000E+02 2.5000E+01 2.0000E+00 2188700200025 6.2000E+00 2.8300E+02 6.2000E+01 1.0000E+00 2188700200026 6.7000E+00 3.5600E+02 7.8000E+01 1.0000E+00 2188700200027 7.2000E+00 3.7900E+02 8.3000E+01 1.0000E+00 2188700200028 7.7000E+00 4.3400E+02 9.5000E+01 1.0000E+00 2188700200029 ENDDATA 14 0 2188700200030 ENDSUBENT 29 0 2188700299999 ENDENTRY 2 0 2188799999999