The thermal conductivity of neutron-irradiated reactor-grade graphites made from needle coke (H-327), Gilsocoke (H-328), and isotropic petroleum coke (H-451) was measured between 22 and 800ยฐC. Irradiation temperatures were between 600 and 16OO"C, and fast neutron fluences ranged up to lO22 n/cm\* (E
Immobilization of Radionuclides in Irradiated Reactor-Graphite Blocks
โ Scribed by P. A. Platonov; Ya. I. Shtrombakh; O. K. Chugunov; N. S. Lobanov; V. P. Aleksandrov; V. M. Alekseev; V. M. Semochkin; V. A. Denisov; V. N. Kochkin
- Book ID
- 110393536
- Publisher
- Springer US
- Year
- 2002
- Tongue
- English
- Weight
- 40 KB
- Volume
- 92
- Category
- Article
- ISSN
- 1573-8205
No coin nor oath required. For personal study only.
๐ SIMILAR VOLUMES
Ahstraet-For the design of the core of a High Temperature Reactor, reliable data on the radiation induced plasticity of reactor graphite are necessary. This paper describes a series of restrained skrinkage experiments on a number of graphites in the temperature range 400-1400ยฐC. A description is giv
The phenomenon of irradiation creep in graphite is essential to the design and construction of graphite-moderated reactors. Recent experimental results have shown large apparent reductions in creep rate for creep strains greater than ?I'%. It is shown that this is not a true reduction in creep rate,
Properties of polycrystalline graphites irradiated at various temperatures (338ยฐK and 873ยฐK) were tested from 100 to 750ยฐK. The dynamic mechanical properties for these specimens indicate multirelaxation behavior. The modulus values increase for all irradiated specimens as compared to unirradiated va