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Neutron thermalization in graphite

✍ Scribed by M.P. Navalkar; S.B.D. Iyengar


Publisher
Elsevier Science
Year
1968
Weight
403 KB
Volume
22
Category
Article
ISSN
0022-3107

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Thermal conductivity of neutron-irradiat
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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 800Β°C. Irradiation temperatures were between 600 and 16OO"C, and fast neutron fluences ranged up to lO22 n/cm\* (E