SiC-Fission Product Reactions in HTGR TRISO UC2 and UCxOy Fissile Fuel: I, Kinetics of Reactions in a Thermal Gradient-Reference-Cited by-同舟云学术

SiC-Fission Product Reactions in HTGR TRISO UC2 and UCxOy Fissile Fuel: I, Kinetics of Reactions in a Thermal Gradient

Published:1979-11 Issue:11-12 Volume:62 Page:600-606
ISSN:0002-7820
Container-title:Journal of the American Ceramic Society
language:en
Short-container-title:J American Ceramic Society

Author:

SMITH C. L.

Publisher

Wiley

Subject

Materials Chemistry,Ceramics and Composites

Link

http://onlinelibrary.wiley.com/wol1/doi/10.1111/j.1151-2916.1979.tb12741.x/fullpdf

Reference13 articles.

1. 1C. B. Scott, D. P. Harmon, and J. F. Holzgraf , "Postirradiation Examination of Capsules P13R and P13S ," ERDA Tech. Rept. No. GA-A13827, Oct. 8, 1976 .

2. 2HTGR, Fuels and Core Development Program, Quart. Progr. Rept. Period Ending Feb. 29, 1976 ," ERDA Tech. Rept. No. GA-A13804, 1976 .

3. 3R. L. Pearson, and T. B. Lindemer; pp.357 -71 inProceedings of ANS Topical Meeting on Thermal Reactor Safety , July 31-Aug. 4, 1977, Sun Valley, Idaho, Vol. 3 (Conf. No. 770708). American Nuclear Society, Hinsdale, III., 1977 .

4. Silicon Carbide Corrosion in High-Temperature Gas-Cooled Reactor Fuel Particles

5. 5F. J. Homan, and E. L. Long , "Irradiation Performance of HTGR Recycle Fuel ," ERDA Tech. Rept. No. ORNL/TM-5502, 1976 .

Cited by 18 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Advanced Concepts in TRISO Fuel;Comprehensive Nuclear Materials;2020

2. Other power reactor fuels;Advances in Nuclear Fuel Chemistry;2020

3. Coated particle fuel: Historical perspectives and current progress;Journal of Nuclear Materials;2019-03

4. Advanced Concepts in TRISO Fuel;Comprehensive Nuclear Materials;2012

5. Exact Solution of Fractional Diffusion Model with Source Term used in Study of Concentration of Fission Product in Uranium Dioxide Particle;Communications in Theoretical Physics;2011-05