Irradiation-induced densification and PuO2 particle behavior in mixed-oxide pellet fuel-Reference-Cited by-同舟云学术

Irradiation-induced densification and PuO2 particle behavior in mixed-oxide pellet fuel

Published:1979-04 Issue:1-2 Volume:81 Page:63-92
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Freshley M.D.,Brite D.W.,Daniel J.L.,Hart P.E.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference24 articles.

1. Irradiation-Induced Densification of UO2 Pellet Fuel;Freshley;J. Nucl. Mater.,1976

2. Plutonia Fuel Study (EPRI Research Project 336), Final Report;Freshley;Electric Power Research Institute Report RP 396,1977

3. “Standard Method of Test for Water Absorption, Bulk Density, Apparent Porosity, and Apparent Specific Gravity of Fired Whiteware Products,” ASTM Standard C-373-72.

4. Average Grain Size in Polycrystalline Ceramics;Mendelson;J. Am. Ceram. Soc.,1966

Cited by 5 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. Characterization of ThO2–UO2 pellets made by co-precipitation process;Journal of Nuclear Materials;2009-06

2. Fuel characteristics required for LWR fuel rod calculations;Journal of Nuclear Materials;1982-04

3. Interdiffusion and chemical diffusion in the UO2 — (U,Pu)O2 system;Journal of Nuclear Materials;1982-04

4. Optical methods for application in nuclear fuel characterization;Journal of Nuclear Materials;1982-04

5. Specification of limiting sizes of PuO2-microheterogeneities in pellets of mixed oxide fuels;Nuclear Engineering and Design;1981-07