NSR Query Results
Output year order : Descending NSR database version of April 27, 2024. Search: Author = T.R.England Found 8 matches. 2002WI17 Prog.Nucl.Energy 41, 71 (2002) Delayed Neutron Study Using ENDF/B-VI Basic Nuclear Data NUCLEAR REACTIONS 227,229,232Th, 231Pa, 232,233,234,235,236,237,238U, 237,238Np, 238,239,240,241,242Pu, 241,242m,243Am, 242,243,244,245,246,248Cm, 249,251Cf, 254Es, 255Fm(n, F), E ≈ thermal-14 MeV; calculated delayed neutron production rates following fission. RADIOACTIVITY 238U, 244,246,248Cm, 250,252Cf, 253Es, 254,256Fm(SF); calculated delayed neutron production rates.
doi: 10.1016/S0149-1970(02)00006-9
2002WI20 Prog.Nucl.Energy 41, 71 (2002) Delayed neutron study using ENDF/B-VI basic nuclear data
doi: 10.1016/S0149-1970(02)00006-9
1998TI09 Phys.Rev. C58, 905 (1998) S.V.Tipnis, J.M.Campbell, G.P.Couchell, S.Li, H.V.Nguyen, D.J.Pullen, W.A.Schier, E.H.Seabury, T.R.England Yields of Short-Lived Fission Products Produced following 235U(nth, f) NUCLEAR REACTIONS 235U(n, F), E=thermal; measured Eγ, Iγ, βγ-coin; deduced independent, cumulative short-lived fission fragment yields. Helium jet, tape transport.
doi: 10.1103/PhysRevC.58.905
1989BR25 Nucl.Sci.Eng. 103, 129 (1989) Delayed Neutron Data and Group Parameters for 43 Fissioning Systems COMPILATION 227,229,232Th, 231Pa, 232,233,234,235,236,237,238U, 237,238Np, 238,239,240,241,242Pu, 241,242m,243Am, 242,245Cm, 249,251,252Cf, 254Es, 255Fm; compiled, evaluated delayed neutron six-group parameters.
doi: 10.13182/NSE103-129
1989YO11 Trans.Amer.Nucl.Soc. 60, 271 (1989) P.G.Young, E.D.Arthur, M.Bozoian, T.R.England, G.M.Hale, R.J.LaBauve, R.C.Little, R.E.MacFarlane, D.G.Madland, R.T.Perry, W.B.Wilson 7. Transport data libraries for incident proton and neutron energies to 100 MeV NUCLEAR REACTIONS 1H, 9Be, C, O, 27Al, Si, Fe, W, 238U(p, X), 1H, 9Be, C, O, 27Al, Si, Ca, Fe, W, 238U(n, X), E<100 MeV; analyzed available data; deduced σ for transport libraries.
1984MA39 Nucl.Sci.Eng. 87, 418 (1984) F.M.Mann, M.Schreiber, R.E.Schenter, T.R.England Evaluation of Delayed-Neutron Emission Probabilities RADIOACTIVITY A=79-148; analyzed delayed neutron precursor data; deduced role in fission yields, delayed neutron emission probability systematics.
doi: 10.13182/NSE84-A18508
1983EN03 Nucl.Sci.Eng. 85, 139 (1983) T.R.England, W.B.Wilson, R.E.Schenter, F.M.Mann Aggregate Delayed Neutron Intensities and Spectra using Augumented ENDF/B-V Precursor Data RADIOACTIVITY A=79-150; calculated β-delayed neutron intensities, emission probabilities (P(n)), precursor fission yields. 88,89,90,91,92,93,94,95,96,97,98,99Rb(β-n); calculated T1/2, neutron spectra. Aggregate summation method, ENDF/B-V precursor data.
doi: 10.13182/NSE83-A27422
1977MA38 Nucl.Sci.Eng. 64, 859 (1977) The Influence of Isomeric States on Independent Fission Product Yields NUCLEAR REACTIONS 233,235U(n, F), E=th; calculated isomer/ground state yield ratios.
doi: 10.13182/NSE77-A14501
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