Design da ta for irradiated graphite are usually presented as families of isothermal curves showing the change in physical property as a function of fast neutron fluence. In this report, procedures for combining isothermal curves to predict behavior und er changing irradiation temperatures are compared with experimental data on irradiation-induced changes in dimensions, Young's modulus, thermal conductivity, and thermal expansivity. The suggested procedure fits the data quite weIl and is physically realistic
Graphite has historically been used as a moderator material in nuclear reactor designs dating back t...
Detailed knowledge regarding the nature of and mechanisms causing neutron irradiation damage in grap...
The behavior of 0.125-in. spectroscopic graphite rods is shown to be variable beyond the variation o...
Preliminary results of a broad irradiation program on graphite are reported. Within this program gra...
COMPARISON Of IRRADIATION DAMAGE IN ARTIFICIAL AND NATURAL GRAPHITE AT DIFFERENTIRRADIATION TEMPERAT...
Property changes in polycrystalline graphite resulting from reactor irradiations at temperatures up ...
Irradiation effects at 500 deg C in experiemtal graphites with varied density, crystallinity, surfac...
Experimental data on the thermal conductivity of needle-coke and isotropic graphites irradiated betw...
This study presents experimental results about the significance of noncrystalline carbon for the beh...
International audienceDue to its excellent moderator and reflector qualities, graphite was used in C...
The graphite grade ATR-2E was developed as a reference material for future High-Temperature Reactors...
Experiments are described in which the change in thermal conductivity of U-impregnated graphite unde...
In the present report a method is introduced by which it has become possible to analyze data for irr...
tThe properties of graphite samples from the thermal column of a material testing reactor and from t...
Graphite expands linearly with irradiation at temperatures below 250 deg C and develops stored energ...
Graphite has historically been used as a moderator material in nuclear reactor designs dating back t...
Detailed knowledge regarding the nature of and mechanisms causing neutron irradiation damage in grap...
The behavior of 0.125-in. spectroscopic graphite rods is shown to be variable beyond the variation o...
Preliminary results of a broad irradiation program on graphite are reported. Within this program gra...
COMPARISON Of IRRADIATION DAMAGE IN ARTIFICIAL AND NATURAL GRAPHITE AT DIFFERENTIRRADIATION TEMPERAT...
Property changes in polycrystalline graphite resulting from reactor irradiations at temperatures up ...
Irradiation effects at 500 deg C in experiemtal graphites with varied density, crystallinity, surfac...
Experimental data on the thermal conductivity of needle-coke and isotropic graphites irradiated betw...
This study presents experimental results about the significance of noncrystalline carbon for the beh...
International audienceDue to its excellent moderator and reflector qualities, graphite was used in C...
The graphite grade ATR-2E was developed as a reference material for future High-Temperature Reactors...
Experiments are described in which the change in thermal conductivity of U-impregnated graphite unde...
In the present report a method is introduced by which it has become possible to analyze data for irr...
tThe properties of graphite samples from the thermal column of a material testing reactor and from t...
Graphite expands linearly with irradiation at temperatures below 250 deg C and develops stored energ...
Graphite has historically been used as a moderator material in nuclear reactor designs dating back t...
Detailed knowledge regarding the nature of and mechanisms causing neutron irradiation damage in grap...
The behavior of 0.125-in. spectroscopic graphite rods is shown to be variable beyond the variation o...