THE DEVELOPMENT OF A DILUTE ALUMINUM-GOLD ALLOY FOR THERMAL AND RESONANCE NEUTRON FLUX MEASUREMENTS

作者: L. M. Howe , R. E. Jervis , T. A. Eastwood

DOI: 10.13182/NSE12-2-185

关键词: AluminiumNeutron fluxMaterials scienceNeutron detectionThermalHomogeneity (physics)Neutron temperatureAnnealing (metallurgy)Electromagnetic shieldingAnalytical chemistryNuclear magnetic resonance

摘要: Aluminum -gold alloy wire of very uniform cross section and composition was made for the preparation neutron flux monitors. Because ls uniform, a device to cut lt into pleces equal length can be used rapld monltors need weigh lndividual monitors thus avoided. Homogeneity achieved mainly by rolling annealing, effectiveness each step assessed neutronactlvatlon analysis. The gold content flnal product (wire 0.018 in. dlameter) also determined activation analysis found 0.0985 plus or minus 0.0020 at.%. Thermal-neutron self-shleldlng ln thls is negligible cadmlum ratio experiments show that resonanceneutron self-shielding amounts about 2.5%. (auth)

参考文章(7)
G.M. Roe, THE ABSORPTION OF NEUTRONS IN DOPPLER BROADENED RESONANCES Other Information: Orig. Receipt Date: 31-DEC-55. ,(1954) , 10.2172/4397079
B. W. Sargent, L. Yaffe, A. P. Gray, MEASUREMENT OF THE HALF-LIVES OF AcC″, Cu66, Mg27, Ti51, Tl206, and V52 Canadian Journal of Physics. ,vol. 31, pp. 235- 249 ,(1953) , 10.1139/P53-025
K. Jirlow, E. Johansson, The resonance integral of gold Journal of Nuclear Energy. Part A. Reactor Science. ,vol. 11, pp. 101- 107 ,(1960) , 10.1016/0368-3265(60)90021-9
W. H. Walker, C. H. Westcott, T. K. Alexander, MEASUREMENT OF RADIATIVE CAPTURE RESONANCE INTEGRALS IN A THERMAL REACTOR SPECTRUM, AND THE THERMAL CROSS SECTION OF Pu-240 Canadian Journal of Physics. ,vol. 38, pp. 57- 77 ,(1960) , 10.1139/P60-008
Donald J. Hughes, Lyle B. Borst, Neutron Cross Sections ,(1957)
K. Shure, C. H. Westcott, Effective Cross Section Values for Well-Moderated Thermal Reactor Spectra Mathematics of Computation. ,vol. 14, pp. 87- ,(1960) , 10.2307/2003009