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Experimental Neutron Spectra in a Cylinder of Hot Moderator. (CRRP-985-D) AECL-1471

Experimental Neutron Spectra in a Cylinder of Hot Moderator. (CRRP-985-D) AECL-1471
Paper規格・テクニカルリポート類
Bigham, C. B, Turner, R. B, Chidley, B. G1962<M-AECL-1471>
National Diet Library

Effect of Bi-Directional Fuelling on Reactivity. (CRRP-1014) AECL-1235

Effect of Bi-Directional Fuelling on Reactivity. (CRRP-1014) AECL-1235
Paper規格・テクニカルリポート類
Duret, M. F1961<M-AECL-1235>
National Diet Library

Analog Simulation of Xenon Instability. (CRRP-998) AECL-1185

Analog Simulation of Xenon Instability. (CRRP-998) AECL-1185
Paper規格・テクニカルリポート類
Pearce, R. M1961<M-AECL-1185>
National Diet Library

Slowing-Down Spectrum in Heterogeneous Reactors. (CRRP-1006) AECL-1228

Slowing-Down Spectrum in Heterogeneous Reactors. (CRRP-1006) AECL-1228
Paper規格・テクニカルリポート類
Bigham, C. B, Pearce, R. M1961<M-AECL-1228>
National Diet Library

Cadmium Cross Section after Burnout of Cadmium113. (CRRP-1037) AECL-1304

Cadmium Cross Section after Burnout of Cadmium113. (CRRP-1037) AECL-1304
Paper規格・テクニカルリポート類
Fowler, A. G, Hart, R. G1961<M-AECL-1304>
National Diet Library

Digital Simulation of Xenon Instability in Reactors. (CRRP-1002) AECL-1226

Digital Simulation of Xenon Instability in Reactors. (CRRP-1002) AECL-1226
Paper規格・テクニカルリポート類
Barss, W. M1961<M-AECL-1226>
National Diet Library

Chalk River Thermal Neutron Analyser. (CRRP-1078) AECL-1494

Chalk River Thermal Neutron Analyser. (CRRP-1078) AECL-1494
Paper規格・テクニカルリポート類
Egelstaff, P. A, Cocking, S. J, Alexander, T. K1960<M-AECL-1494>
National Diet Library

Multigroup Diffusion Calculations of Thermal Neutron Spectra in CANDU Using a Free Gas Model. (CRRP-1045) AECL-1414

Multigroup Diffusion Calculations of Thermal Neutron Spectra in CANDU Using a Free Gas Model. (CRRP-1045) AECL-1414
Paper規格・テクニカルリポート類
Kennedy, J. M, Pearce, R. M1961<M-AECL-1414>
National Diet Library

Temperature Coefficient for a Lattice of 19-Element UO2 Clusters. (CRRP-978) AECL-1121

Temperature Coefficient for a Lattice of 19-Element UO2 Clusters. (CRRP-978) AECL-1121
Paper規格・テクニカルリポート類
Green, R. E, Allen, D. F, Hone, D. W, Okazaki, A1960<M-AECL-1121>
National Diet Library

Void Coefficient Measurements in Zeep. (CRRP-942) AECL-1053

Void Coefficient Measurements in Zeep. (CRRP-942) AECL-1053
Paper規格・テクニカルリポート類
Green, R. E, Beer, G. A, Hone, D. W1960<M-AECL-1053>
National Diet Library

Estimate of the Reactivity of Assemblies of NRX Fuel Elements in Light Water. (CRRP-914) AECL-1010

Estimate of the Reactivity of Assemblies of NRX Fuel Elements in Light Water. (CRRP-914) AECL-1010
Paper規格・テクニカルリポート類
Jarvis, R. G1960<M-AECL-1010>
National Diet Library

Some Close-Packed Lattices in Light Water and Heavy Water: part 1. buckling measurements. (CRRP-894) AECL-1254

Some Close-Packed Lattices in Light Water and Heavy Water: part 1. buckling measurements. (CRRP-894) AECL-1254
Paper規格・テクニカルリポート類
Jarvis, R. G, Phillips, G. J, Walker, W. H1961<M-AECL-1254>
National Diet Library

Scintillation Counters for Thermal Neutrons Using Li6F and ZnS(Ag). (CRRP-931) AECL-1035

Scintillation Counters for Thermal Neutrons Using Li6F and ZnS(Ag). (CRRP-931) AECL-1035
Paper規格・テクニカルリポート類
Stedman, R1960<M-AECL-1035>
National Diet Library

Measurements Made in the Pool Test Reactor During the Period from November 1957 to June 1958. (CRRP-1064) AECL-1407

Measurements Made in the Pool Test Reactor During the Period from November 1957 to June 1958. (CRRP-1064) AECL-1407
Paper規格・テクニカルリポート類
Craig, D. S, Keech, G. L1961<M-AECL-1407>
National Diet Library

Experimental Effective Fission Cross Sections and Neutron Spectra in a Uranium Fuel Rod: part II. Candu-Type uranium oxide clusters. (CRRP-985-8) AECL-1350

Experimental Effective Fission Cross Sections and Neutron Spectra in a Uranium Fuel Rod: part II. Candu-Type uranium oxide clusters. (CRRP-985-8) AECL-1350
Paper規格・テクニカルリポート類
Bigham, C. B, Chidley, B. G, Turner, R. B1961<M-AECL-1350>
National Diet Library

Experimental Effective Fission Cross Sections and Neutron Spectra in a Uranium Fuel Rod: part 1. NRX uranium metal rods. (CRRP-985-A) AECL-1186

Experimental Effective Fission Cross Sections and Neutron Spectra in a Uranium Fuel Rod: part 1. NRX uranium metal rods. (CRRP-985-A) AECL-1186
Paper規格・テクニカルリポート類
Bigham. C. B, Tunnicliffe, P. R1961<M-AECL-1186>
National Diet Library

Yields and Effective Cross Sections of Fission Products and Pseudo-Fission-Products. (CRRP-913) AECL-1054

Yields and Effective Cross Sections of Fission Products and Pseudo-Fission-Products. (CRRP-913) AECL-1054
Paper規格・テクニカルリポート類
Walker, W. H1960<M-AECL-1054>
National Diet Library

Effective Cross Section Values for Well-Moderated Thermal Reactor Spectra: 3rd edition corrected. (CRRP-960), (EANDC(Can)-4), (TNCC(Can)-30) AECL-1101

Effective Cross Section Values for Well-Moderated Thermal Reactor Spectra: 3rd edition corrected. (CRRP-960), (EANDC(Can)-4), (TNCC(Can)-30) AECL-1101
Paper規格・テクニカルリポート類
Westcott, C. H1960<M-AECL-1101>
National Diet Library

Experimental Effective Fission Cross Sections and Neutron Spectra in a Uranium Fuel Rod: part III CANDU-Type fuel with H2O-D2O mixtures as coolants. (CRRP-985-C) AECL-1419

Experimental Effective Fission Cross Sections and Neutron Spectra in a Uranium Fuel Rod: part III CANDU-Type fuel with H2O-D2O mixtures as coolants. (CRRP-985-C) AECL-1419
Paper規格・テクニカルリポート類
Chidley, B. G, Turner, R. B, Bigham, C. B1961<M-AECL-1419>
National Diet Library

Effect of Flux Flattening on the Economics of Heavy Water Moderated Reactors.: App.1, App.2, App.3, App.4, App.5, App.6, App.7.(CRRP-872) AECL-949

Effect of Flux Flattening on the Economics of Heavy Water Moderated Reactors.: App.1, App.2, App.3, App.4, App.5, App.6, App.7.(CRRP-872) AECL-949
Paper規格・テクニカルリポート類
Henderson, W. J, Hurst, D. G1959<M-AECL-949>
National Diet Library
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