ENTRY 22517 20121225 22342251700000001 SUBENT 22517001 20121225 22342251700100001 BIB 12 30 2251700100002 INSTITUTE (2UK ALD) 2251700100003 REFERENCE (J,JNE/AB,17,349(2),1963) 2251700100004 AUTHOR (J.L.Perkin) 2251700100005 TITLE The radiative capture cross section of Sc-45 for fast 2251700100006 neutrons 2251700100007 FACILITY (VDG,2UK ALD) AWRE 3 MeV Van de Graaff 2251700100008 INC-SOURCE (P-LI7) Neutrons of the lowest three energies were 2251700100009 produced using the 7Li(p,n) reaction; 2251700100010 (P-T) Next two energies were produced from the p-T 2251700100011 reaction 2251700100012 (D-D) At 4.5 MeV were produced using the d-D reaction 2251700100013 (D-T) At 14.65 MeV were produced using the d-T reaction2251700100014 SAMPLE Samples for neutron irradiation consisted of 0.8 gr of 2251700100015 spectroscopically pure scandium oxide in flat 2251700100016 thin-walled Perspex pill boxes about 0.1 cm deep 2251700100017 and 3 cm diam. 2251700100018 The neutron flux through the samples was determined 2251700100019 by sandwiching them between two parallel plate ion 2251700100020 chambers each containing about 3 mg of 235-U extending2251700100021 over an area similar to that of the scandium samples. 2251700100022 METHOD (ACTIV) Activation 2251700100023 DETECTOR (NAICR) 6-cm diam. 6-cm long NaI scintillation 2251700100024 gamma-ray spectrometer 2251700100025 ERR-ANALYS (DATA-ERR) Standard deviation errors 2251700100026 STATUS (SCSRS) Data are given on fig.1 of JNE/AB,17,349 2251700100027 HISTORY (19820331C) ! ! Compiled by NNDC 2251700100028 (19991210C) + + converted by S.M. + + 2251700100029 (20121225A) SD: Updated to lower case. BIB update 2251700100030 (SAMPLE, INC-SOURCE etc. were added). Ref. was 2251700100031 corrected (JNE -> JNE/AB) 2251700100032 ENDBIB 30 0 2251700100033 NOCOMMON 0 0 2251700100034 ENDSUBENT 33 0 2251700199999 SUBENT 22517002 20121225 22342251700200001 BIB 5 18 2251700200002 REACTION (21-SC-45(N,G)21-SC-46,,SIG) 2251700200003 DECAY-DATA (21-SC-46-G,83.9D) 2251700200004 MONITOR (92-U-235(N,F),,SIG) 2251700200005 The fission counting rate in the counters was 2251700200006 calibrated in terms of neutron flux by calculations 2251700200007 based on: the amount of 235-U present as determined 2251700200008 by low geometry alpha-particle assay, published 2251700200009 values for the fission cross section, and 2251700200010 experimentally determined corrections for fission 2251700200011 fragment counting losses due to the thickness and 2251700200012 non-uniformity of the 235-U foil. This calibration 2251700200013 was verified at 14.65 MeV by making an absolute 2251700200014 measurement using the usual method of counting 2251700200015 the associated alpha-particles from the d-T reaction. 2251700200016 MONIT-REF (12544002,H.L.Smith+,J,PR,125,1329,1962) see MONIT data2251700200017 in Subent 12544.002. 2251700200018 HISTORY (19991210T) Converted from subent 60436002 2251700200019 (20121225A) SD: BIB update. 2251700200020 ENDBIB 18 0 2251700200021 NOCOMMON 0 0 2251700200022 DATA 3 7 2251700200023 EN DATA DATA-ERR 2251700200024 MEV B B 2251700200025 1.5000E-01 2.6000E-02 2251700200026 3.0000E-01 1.4000E-02 4.0000E-03 2251700200027 5.2000E-01 8.9000E-03 2251700200028 9.5000E-01 7.7000E-03 1.2000E-03 2251700200029 2.0500E+00 2.0500E-03 6.0000E-04 2251700200030 4.5000E+00 1.0000E-03 1.8000E-03 2251700200031 1.4650E+01 1.2500E-03 1.0000E-04 2251700200032 ENDDATA 9 0 2251700200033 ENDSUBENT 32 0 2251700299999 ENDENTRY 2 0 2251799999999