The behaviour of helium in neutron-irradiated copper-boron alloys was investigated in the temperature range between 300° C and 800° C. It was found that bubbles nucleate preferentially upon dislocations which are created by the annealing of displacement damage. After gas precipitation is complete, the bubbles grow by migration and coalescence, at such a rate that the average bubble radius is proportional to t 1 14, where t is time. Helium causes solution-hardening and the strength of an alloy containing bubbles is inversely proportional to the bubble spacing. One atomic per cent of helium causes a 3 μohm · cm increase in electrical resistivity. The changes which occur in the resistance during annealing are complicated and contributions aris...
Ferritic/martensitic (FM) steels, F82H and Optimax-A, were irradiated up to 11.3 dpa/1175 appm He in...
Tensile properties at 250℃ and swelling of beryllium, irradiated to 5×10^n/cm^2 at about 450℃ and su...
Helium (He) bubbles are typical radiation defects in structural materials in nuclear reactors after ...
The lattice parameter of copper is proportional to the concentration of dissolved interstitial heliu...
Neutron irradiated copper-boron alloys are employed to study the mutual interaction betwe...
Neutron irradiated copper-boron alloys are employed to study the mutual interaction betwe...
The paper analyses afresh the data of Russell and Hastings on the changes in lattice parameter durin...
Neutron irradiated copper-boron alloys are employed to study the mutual interaction betwe...
The paper analyses afresh the data of Russell and Hastings on the changes in lattice parameter durin...
This work reports on the evolution law of helium bubbles in Hastelloy N alloy on post-irradiation an...
In the present contribution, the basic ideas pertinent to modelling helium accumulation in metals ar...
Helium was implanted in a homogeneous distribution into 10 $\mu$m thick foils of nickel and copper a...
When boron carbide is used as a neutron absorber in nuclear power plants, large quantities of helium...
When boron carbide is used as a neutron absorber in nuclear power plants, large quantities of helium...
When boron carbide is used as a neutron absorber in nuclear power plants, large quantities of helium...
Ferritic/martensitic (FM) steels, F82H and Optimax-A, were irradiated up to 11.3 dpa/1175 appm He in...
Tensile properties at 250℃ and swelling of beryllium, irradiated to 5×10^n/cm^2 at about 450℃ and su...
Helium (He) bubbles are typical radiation defects in structural materials in nuclear reactors after ...
The lattice parameter of copper is proportional to the concentration of dissolved interstitial heliu...
Neutron irradiated copper-boron alloys are employed to study the mutual interaction betwe...
Neutron irradiated copper-boron alloys are employed to study the mutual interaction betwe...
The paper analyses afresh the data of Russell and Hastings on the changes in lattice parameter durin...
Neutron irradiated copper-boron alloys are employed to study the mutual interaction betwe...
The paper analyses afresh the data of Russell and Hastings on the changes in lattice parameter durin...
This work reports on the evolution law of helium bubbles in Hastelloy N alloy on post-irradiation an...
In the present contribution, the basic ideas pertinent to modelling helium accumulation in metals ar...
Helium was implanted in a homogeneous distribution into 10 $\mu$m thick foils of nickel and copper a...
When boron carbide is used as a neutron absorber in nuclear power plants, large quantities of helium...
When boron carbide is used as a neutron absorber in nuclear power plants, large quantities of helium...
When boron carbide is used as a neutron absorber in nuclear power plants, large quantities of helium...
Ferritic/martensitic (FM) steels, F82H and Optimax-A, were irradiated up to 11.3 dpa/1175 appm He in...
Tensile properties at 250℃ and swelling of beryllium, irradiated to 5×10^n/cm^2 at about 450℃ and su...
Helium (He) bubbles are typical radiation defects in structural materials in nuclear reactors after ...