Kernel Migration for HTGR Fuels from the System Th-U-Pu-C-O-N-Reference-Cited by-同舟云学术

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Kernel Migration for HTGR Fuels from the System Th-U-Pu-C-O-N

Published:1977-01 Issue:1-2 Volume:60 Page:5-14
ISSN:0002-7820
Container-title:Journal of the American Ceramic Society
language:en
Short-container-title:

Author:

LINDEMER T. B.,PEARSON R. L.

Publisher

Wiley

Subject

Materials Chemistry,Ceramics and Composites

Link

http://onlinelibrary.wiley.com/wol1/doi/10.1111/j.1151-2916.1977.tb16082.x/fullpdf

Reference49 articles.

1. Fuel Element Fabrication for the Dragon Reactor Experiment;Price;J. Br. Nucl. Energy Soc.,1966

2. AVR Pebble Bed Reactor;Mueller;Ibid.

3. Fort Saint Vrain Core Design Characteristics;Dahlberg;Nucl. Eng. Int.,1969

4. Development of Coated Particle Fuels for High Temperature Reactors;Shepherd;J. Br. Nucl. Energy Soc.,1970

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2. Derivation of ideal power distribution to minimize the maximum Kernel migration rate for nuclear design of pin-in-block type HTGR;Journal of Nuclear Science and Technology;2020-07-09

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

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

5. Modeling morphology evolution and densification during solid-state sintering via kinetic Monte Carlo simulation;Modelling and Simulation in Materials Science and Engineering;2016-10-13

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