NSR Query Results
Output year order : Descending NSR database version of May 1, 2024. Search: Author = O.Aizawa Found 7 matches. 1986AI02 Radiat.Eff. 93, 225 (1986) O.Aizawa, H.Kadotani, T.Matsumoto, S.Oheda Temperature Dependence of Total Neutron Cross Sections in Thermal and keV Regions NUCLEAR REACTIONS Si(n, n'), E=thermal, 0.002-2 eV; measured σ(E). Nb(n, n), E=23.3, 25.3 keV; measured σ vs temperature.
doi: 10.1080/00337578608207458
1985SU12 J.Nucl.Sci.Technol.(Tokyo) 22, 765 (1985) E.Suetomi, O.Aizawa, T.Matsumoto, H.Kadotani Total Neutron Cross Sections of Single- and Poly-Crystalline Germanium NUCLEAR REACTIONS Ge(n, n), E=0.0001-10 eV; measured σ(E). Single-, poly-crystalline Ge.
doi: 10.1080/18811248.1985.9735724
1983AI01 J.Nucl.Sci.Technol.(Tokyo) 20, 354 (1983) O.Aizawa, T.Matsumoto, H.Kadotani Measurements of Total Neutron Cross Sections at 24-keV by Means of Iron-Filter Method NUCLEAR REACTIONS Be, C(n, γ), E=24 keV; measured σ. Iron filter method.
doi: 10.1080/18811248.1983.9733402
1983AI02 J.Nucl.Sci.Technol.(Tokyo) 20, 713 (1983) O.Aizawa, T.Matsumoto, H.Kadotani Total Neutron Cross Sections of Magnesium, Aluminum, Silicon, Zirconium, Niobium and Molybdenum in Energy Range from 0.001 to 0.3 eV NUCLEAR REACTIONS Mg, Al, Si, Zr, Nb, Mo(n, n), E=0.001-0.3 eV; measured σ(E). Solid, powdered samples.
doi: 10.1080/18811248.1983.9733458
1976KA16 Nucl.Sci.Eng. 60, 230 (1976) Total Neutron Cross Section of Lead NUCLEAR REACTIONS Pb(n, X), E < 1 eV; measured σ(E).
doi: 10.13182/NSE76-A26879
1973TA29 Bull.Tokyo Inst.Technol.(Engl.Ed.) No.116, 1 (1973) Fast Neutron Decay Measurements on Lead and Iron by the Use of Californium-252 as a Randomly Pulsed Source NUCLEAR REACTIONS Fe, Pb(n, X), E < 15 MeV; measured delayed neutrons.
1972YA11 Bull.Tokyo Inst.Technol.(Engl.Ed.) No.109, 19 (1972) N.Yamamuro, H.Yokobori, O.Aizawa, I.Kimura, T.Akiyoshi, T.Ebisawa Neutron Transmission Measurement of Pd NUCLEAR REACTIONS 105,108Pd(n, n), E=10-150 eV; measured σ(E). 106,109Pd resonances deduced n-width. Data from this article have been entered in the EXFOR database. For more information, access X4 dataset20510. Back to query form |