I. J. Hastings

发表

High burnup performance of annular UO2 fuel with inter-pellet graphite discs

I. J. Hastings, R. D. Macdonald, 1984 .

A Pragmatic Approach to Modelling Thermal Conductivity of Irradiated UO2 Fuel. Review and Recommendations

H. Matzke, Hj. Matzke, I. J. Hastings, 1996 .

A model for in-reactor densification of UO2

S. Macewen, I. J. Hastings, 1975 .

Postirradiation behavior of UO2 fuel I: elements at 220 to 250°C in air

Ian J. Hastings, R. J. Chenier, I. J. Hastings, 1983 .

Air Oxidation of UO2 Fuel Fragments at 175° to 400°C

I. J. Hastings, D. Irvine, D. H. Rose, 1986 .

Postirradiation Behavior of UO2 Fuel II: Fragments at 175 to 275°C in Air

R. J. Chenier, I. J. Hastings, D. H. Rose, 1985 .

Postirradiation Dimensional Stability and Fission Product Behavior of Deliberately Defected UO2 Fuel at 200 and 400°C

I. J. Hastings, R. D. Barrand, J. Novak, 1985 .

Postirradiation Behavior of Naturally and Artificially Defected UO2 Fuel Elements at 250°C in Air

I. J. Hastings, R. E. Moeller, J. Novak, 1985 .

Irradiation-induced volume changes in commercial UO2 fuel: Comparison with model prediction

M. Notley, I. J. Hastings, D. H. Rose, 1978 .

Thermal Neutron Irradiation of Y‐Ba‐Cu‐O Superconductor

I. J. Hastings, J. A. Scoberg, Brad J. F. Palmer, 1988 .

A preliminary investigation of helium gas precipitation in irradiated copper-boron alloys

I. J. Hastings, B. Russell, 1965 .

Heat capacity and thermodynamic properties of triuranium silicide from 1 to 1203 K

D. W. Osborne, F. Grandjean, H. Flotow, 1977 .

Fission-product behavior in ceramic oxide fuel

Ian J. Hastings, I. J. Hastings, 1986 .

Voids in irradiated U3Si: Effect of electropolishing

I. J. Hastings, D. H. Rose, B. Shipley, 1972 .

Burnup and temperature dependence of swelling in U3Si

I. J. Hastings, 1971 .

Temperature-dependent swelling in irradiated U3Si fuel elements

I. J. Hastings, R. Stoute, 1970 .

Simulation of in-reactor swelling in U-3.5 wt % Si-1.5 wt % Al by ion bombardment

I. J. Hastings, P. Caillibot, 1976 .

Irradiation of U3Si-based compounds in the high-voltage electron microscope

I. J. Hastings, 1975 .

A microstructure-dependent model for fission product gas release and swelling in UO2 fuel☆

M. Notley, I. J. Hastings, 1980 .

The effect of concentration upon helium precipitation in irradiated copper boron alloys

I. J. Hastings, B. Russell, 1967 .

Bubble-precipitate interaction on grain boundaries in irradiated UO2

I. J. Hastings, 1974 .

Fission gas release from power-ramped UO2 fuel

I. J. Hastings, T. J. Carter, P. Fehrenbach, 1986 .

Grain growth in UO2: in-reactor and laboratory testing

I. J. Hastings, J. A. Scoberg, K. Mackenzie, 1979 .

Identification of precipitates associated with intergranular fission gas bubbles in irradiated UO2 fuel

I. J. Hastings, D. H. Rose, J. Baird, 1976 .

Effect of Initial Grain Size on Fission Gas Release from Irradiated UO2 Fuel

I. J. Hastings, 1983 .

Canadian fusion breeder blanket program: Irradiation facilities at chalk river

L. M. Howe, S. Macewen, R. Zee, 1986 .

A fast neutron, in situ tritium recovery experiment on solid breeder materials

R. E. Bauer, Hitoshi Watanabe, I. J. Hastings, 1989 .

Bubble formation in irradiated Li2O

I. J. Hastings, D. H. Rose, J. Miller, 1991 .

BEATRIX-II: A multinational solid breeder materials experiment

I. J. Hastings, G. Hollenberg, H. Watanabe, 1992 .

Fabrication and Properties of Lithium Ceramics

I. J. Hastings, G. Hollenberg, 1989 .