ENTRY 21188 20120815 22322118800000001 SUBENT 21188001 20120815 22322118800100001 BIB 15 49 2118800100002 INSTITUTE (2UK ALD) 2118800100003 REFERENCE (J,JNE/AB,18,491,196409) 2118800100004 AUTHOR (J.F.Barry) 2118800100005 TITLE The radiative capture cross section of Au-197 for 2118800100006 neutrons in the energy range 0.12-1.8 MeV 2118800100007 FACILITY (VDG,2UK ALD) Van de Graaff. 2118800100008 INC-SOURCE (P-LI7) 0.12-0.6 MeV neutrons. 2118800100009 (P-T) 0.6-1.8 MeV neutrons. 2118800100010 SAMPLE .Gold discs, 0.005 cm thick by 2.3 cm diameter, of 2118800100011 chemical purity greater than 99.9%. 2118800100012 .Samples subtended +-15 degrees at the neutron source. 2118800100013 METHOD (ACTIV) Activation. 2118800100014 DETECTOR (NAICR) 7.6 cm x 7.6 cm sodium iodide crystal with 2118800100015 3.2 cm deep by 2.5 cm diameter well to count 2118800100016 gamma activity of sample. 2118800100017 (COIN,NAICR,SCIN) Beta-gamma coincidence counter using 2118800100018 NaI crystal for gamma detection and plastic 2118800100019 scintillator for beta detection to calibrate 2118800100020 the efficiency of the gamma counter. 2118800100021 (PROPC) 4-Pi beta counter also used to calibrate the 2118800100022 gamma counter. 2118800100023 (FISCH) Pair of fission chambers on either side of the 2118800100024 sample to measure the relative neutron flux. 2118800100025 Fission chambers calibrated against hydrogen 2118800100026 proportional counter. 2118800100027 DECAY-DATA (79-AU-198,2.7D,DG,411.,,B-,960.,0.986) 2118800100028 MONITOR (1-H-1(N,EL)1-H-1,,SIG) Cross-section related to 2118800100029 scattering cross-section of hydrogen contained 2118800100030 in proportional counter. 2118800100031 STATUS (NDD) From NEUDADA. 2118800100032 CORRECTION .Background due to scattered neutrons calculated as- 2118800100033 1. scattering in the materials of the fission 2118800100034 counter negligible up to 850 keV, 1.6+-1% 2118800100035 at 1 MeV, 2.7+-1.5% at 1.8 MeV. 2118800100036 2. Scattering in materials of the neutron target 2118800100037 significant above 0.75 MeV and 1+-0.5% at 1.8 MeV. 2118800100038 3. Other background neutrons gave correction of 2118800100039 0.4+-0.4% at 127 keV, 0.9+-0.9% at 1.8 MeV. 2118800100040 ERR-ANALYS (ERR-T) .Main contributions to errors are from- 2118800100041 (ERR-1) fission counter calibration............... 2%. 2118800100042 (ERR-2) Gamma counter calibration................. 2%. 2118800100043 (ERR-3,0.,2.) Neutron backgrounds............... 0-2%. 2118800100044 (ERR-S,1.,2.) Counting statistics............... 1-2%. 2118800100045 HISTORY (19791121T) 2118800100046 (19800110E) 2118800100047 (20120815A) SD: Updated to new date formats,lower case.2118800100048 Corrected according last EXFOR rules and Dict. 2118800100049 Journal's title of the ref. JNE,18,491 was 2118800100050 corrected (JNE -> JNE/AB) 2118800100051 ENDBIB 49 0 2118800100052 COMMON 2 3 2118800100053 ERR-1 ERR-2 2118800100054 PER-CENT PER-CENT 2118800100055 2. 2. 2118800100056 ENDCOMMON 3 0 2118800100057 ENDSUBENT 56 0 2118800199999 SUBENT 21188002 20120815 22322118800200001 BIB 2 2 2118800200002 REACTION (79-AU-197(N,G)79-AU-198-G,,SIG) 2118800200003 STATUS (TABLE) .Table 1 of the JNE,18,491,1964. 2118800200004 ENDBIB 2 0 2118800200005 NOCOMMON 0 0 2118800200006 DATA 5 13 2118800200007 EN EN-RSL MONIT DATA ERR-T 2118800200008 MEV MEV B MB MB 2118800200009 1.2700E-01 1.8000E-02 1.1730E+01 3.2100E+02 1.6000E+01 2118800200010 1.6200E-01 2.2000E-02 1.0620E+01 3.2100E+02 1.6000E+01 2118800200011 2.0900E-01 2.1000E-02 9.5100E+00 2.9000E+02 1.4000E+01 2118800200012 3.1400E-01 2.0000E-02 7.8600E+00 2.3200E+02 1.2000E+01 2118800200013 4.0600E-01 2.0000E-02 6.8300E+00 1.8800E+02 1.0000E+01 2118800200014 5.0700E-01 2.0000E-02 6.1200E+00 1.6100E+02 7.0000E+00 2118800200015 6.0000E-01 2.0000E-02 1.2700E+02 6.0000E+00 2118800200016 7.4600E-01 5.9000E-02 1.1200E+02 6.0000E+00 2118800200017 1.0000E+00 5.0000E-02 4.2600E+00 2118800200018 1.0140E+00 5.4000E-02 9.9000E+01 5.0000E+00 2118800200019 1.3080E+00 5.2000E-02 9.3000E+01 5.0000E+00 2118800200020 1.7890E+00 1.0000E-01 7.7000E+01 4.0000E+00 2118800200021 2.2500E+00 5.0000E-02 2.7100E+00 2118800200022 ENDDATA 15 0 2118800200023 ENDSUBENT 22 0 2118800299999 ENDENTRY 2 0 2118899999999