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Formation of dislocation channels in neutron irradiated molybdenum

Acta materialia, 2017-01, Vol.122, p.259-265

2017

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Multi-scale characterization of stress corrosion cracking of cold-worked stainless steels and the influence of Cr content

Acta materialia, 2009-10, Vol.57 (18), p.5361-5381

2009

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Materials for the power industry

Fuel and energy abstracts, 2002-07, Vol.43 (4), p.292-292

2002

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Editorial

Journal of nuclear materials, 1991-12, Vol.186 (1), p.v

Eyre, B.L.

1991

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Experimental evidence for gas driven blister growth on helium bombarded molybdenum

Journal of nuclear materials, 1977-08, Vol.67 (3), p.307-310

1977

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Materials technology challenges for power generation in the 21st century

Progress in materials science, 1997, Vol.42 (1), p.23-37

Eyre, B.L.

1997

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Mechanisms of creep fracture

Journal of nuclear materials, 1986-05, Vol.139 (1), p.75

Eyre, B.L.

1986

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Uranium nuclear energy: 1984

Journal of nuclear materials, 1986-04, Vol.138 (2-3), p.293

Eyre, B.L.

1986

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Austenitic stainless steels - microstructure & mechanical properties

Journal of nuclear materials, 1986-02, Vol.137 (3), p.294

Eyre, B.L.

1986

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Crystals: Point Defects

Encyclopedia of Materials: Science and Technology, 2011, p.1919-1924

2011

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A systematic approach to the radiation damage problem

Journal of nuclear materials, 1977-10, Vol.68 (2), p.168-178

1977

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The structure of fast-reactor irradiated solution-treated AISI type 316 steel

Journal of nuclear materials, 1977-01, Vol.67 (1), p.181-197

1977

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The pebble bed modular reactor: a new reactor for the twenty-first century

Interdisciplinary science reviews, 2001-12, Vol.26 (4), p.287-295

2001

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Technological impact of microstructural evolution during irradiation

Journal of nuclear materials, 1993-10, Vol.205, p.1-15

1993

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Industrial Applications of Radiation

Radiation protection dosimetry, 1996-11, Vol.68 (1-2), p.63-72

EYRE, B. L

1996

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An electron microscope study of Mo2C precipitates in molybdenum—I. Crystallographic relationships

Acta metallurgica, 1978-04, Vol.26 (4), p.569-577

1978

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The nucleation and growth of voids at carbides in 9 Cr-1 Mo steel

Acta metallurgica, 1986-07, Vol.34 (7), p.1321-1327

1986

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Temper embrittlement of low alloy NI-CR steels—I. The susceptibility to temper embrittlement and the influence of intermediate tempering treatments

Acta metallurgica, 1980-03, Vol.28 (3), p.335-356

1980

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Effects of Nitrogen on Grain Boundary Fracture in Molybdenum

Materials science forum, 1993-01, Vol.126-128, p.153-156

1993

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The heat of solution and diffusivity of nitrogen in molybdenum

Acta metallurgica, 1969-01, Vol.17 (8), p.1109-1115

1969

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An electron microscope study of the low temperature ageing behaviour of quenched molybdenum-nitrogen alloys

Acta metallurgica, 1972-01, Vol.20 (2), p.267-273

1972

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The low temperature recovery behaviour of nitrogen quenched into molybdenum

Acta metallurgica, 1970-01, Vol.18 (7), p.835-841

1970

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Low-Energy Self-Ion Irradiations of Copper and Molybdenum at 4.2K

Materials science forum, 1987-01, Vol.15-18, p.1069-1074

1987

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Mechanisms of creep fracture: H.E. Evans (Elsevier Applied Science Publishers, New York, London, 1984)

Journal of Nuclear Materials, 1986, Vol.139 (1), p.75-75

Eyre, B.L.

1986

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Uranium nuclear energy: 1984: Proceedings of the ninth international Symposium, Uranium Institute, London, September 1984 (The Uranium Institute, London, 1985), 416 pp.; price: £45.00

Journal of Nuclear Materials, 1986, Vol.138 (2), p.293-293

Eyre, B.L.

1986

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Formation of dislocation channels in neutron irradiated molybdenum

Multi-scale characterization of stress corrosion cracking of cold-worked stainless steels and the influence of Cr content

Materials for the power industry

Editorial

Experimental evidence for gas driven blister growth on helium bombarded molybdenum

Materials technology challenges for power generation in the 21st century

Mechanisms of creep fracture

Uranium nuclear energy: 1984

Austenitic stainless steels - microstructure & mechanical properties

Crystals: Point Defects

A systematic approach to the radiation damage problem

The structure of fast-reactor irradiated solution-treated AISI type 316 steel

The pebble bed modular reactor: a new reactor for the twenty-first century

Technological impact of microstructural evolution during irradiation

Industrial Applications of Radiation

An electron microscope study of Mo2C precipitates in molybdenum—I. Crystallographic relationships

The nucleation and growth of voids at carbides in 9 Cr-1 Mo steel

Temper embrittlement of low alloy NI-CR steels—I. The susceptibility to temper embrittlement and the influence of intermediate tempering treatments

Effects of Nitrogen on Grain Boundary Fracture in Molybdenum

The heat of solution and diffusivity of nitrogen in molybdenum

An electron microscope study of the low temperature ageing behaviour of quenched molybdenum-nitrogen alloys

The low temperature recovery behaviour of nitrogen quenched into molybdenum

Low-Energy Self-Ion Irradiations of Copper and Molybdenum at 4.2K

Mechanisms of creep fracture: H.E. Evans (Elsevier Applied Science Publishers, New York, London, 1984)

Uranium nuclear energy: 1984: Proceedings of the ninth international Symposium, Uranium Institute, London, September 1984 (The Uranium Institute, London, 1985), 416 pp.; price: £45.00

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