Dry Pressing Ceramic Fuel Elements to Close Tolerances

2009 ◽  
pp. 301-301-10
Author(s):  
FJ Hartwig
Keyword(s):  
Dry Pressing ◽  
Ceramic Fuel ◽  
Fuel Elements

Venting Device for Sodium-Cooled Fast Reactor Ceramic Fuel Elements

1973 ◽  
Vol 19 (2) ◽  
pp. 96-110 ◽  
Author(s):  
M. Martini ◽  
A. Gerosa
Keyword(s):  
Fast Reactor ◽  
Ceramic Fuel ◽  
Fuel Elements

Study of various characteristics of ceramic fuel elements with a semiconductor gamma-spectrometer

1969 ◽  
Vol 27 (3) ◽  
pp. 964-965
Author(s):  
E. F. Davydov ◽  
A. V. Sukhikh ◽  
V. N. Syuzev ◽  
V. I. Ivanov
Keyword(s):  
Gamma Spectrometer ◽  
Ceramic Fuel ◽  
Fuel Elements ◽  
Semiconductor Gamma

Thermal stress evaluation of ceramic fuel elements

1964 ◽  
Vol 11 (3) ◽  
pp. 273-301
Author(s):  
B.A. Chandler ◽  
J.E. McConnelee
Keyword(s):  
Thermal Stress ◽  
Stress Evaluation ◽  
Ceramic Fuel ◽  
Fuel Elements

Ceramic fuel elements

1967 ◽  
Vol 24 (3) ◽  
pp. 350
Author(s):  
J.A.L. Robertson
Keyword(s):  
Ceramic Fuel ◽  
Fuel Elements

scholarly journals Candidate Core Designs for the Transformational Challenge Reactor

2021 ◽  
Vol 2 (1) ◽  
pp. 74-85
Author(s):  
Brian J. Ade ◽  
Benjamin R. Betzler ◽  
Aaron J. Wysocki ◽  
Michael S. Greenwood ◽  
Phillip C. Chesser ◽  
...  
Keyword(s):  
Reactor Core ◽  
Fissile Material ◽  
Design Concepts ◽  
Thermal Spectrum ◽  
Triso Fuel ◽  
Ceramic Fuel ◽  
Near Term ◽  
Fuel Particles ◽  
Fuel Elements ◽  
Spectrum Design

Early cycle activities under the Transformational Challenge Reactor (TCR) program focused on analyzing and maturing four reactor core design concepts: two fast-spectrum systems and two thermal-spectrum systems. A rapid, iterative approach has been implemented through which designs can be modified and analyzed and subcomponents can be manufactured in parallel over time frames of weeks rather than months or years. To meet key program initiatives (e.g., timeline, material use), several constraints—including fissile material availability (less than 250 kg of HALEU), component availabilities, materials compatibility, and additive manufacturing capabilities—were factored into the design effort, yielding small (less than one cubic meter in volume) cores with near-term viability. The fast-spectrum designs did not meet the fissile material constraint, so the thermal-spectrum systems became the primary design focus. Since significant progress has been made on advanced moderator materials (YHx) under the TCR program, gas-cooled thermal-spectrum systems using less than 250 kg of HALEU that occupy less than 1 m3 are now feasible. The designs for two of these systems have been evolved and matured. In both thermal-spectrum design concepts, bidirectional coolant flow is used. Coolant flows down through YHx moderator elements and is reversed in a bottom manifold and core support structure, and then flows up though or around the fuel elements. The main difference between the two thermal-spectrum design concepts is the fuel elements—one uses traditional UO2 ceramic fuel, and the other uses UN-bearing TRISO fuel particles embedded inside a SiC matrix. Core neutronics and thermal performance for these systems are assessed and summarized herein.

Pore migration in ceramic fuel elements

1968 ◽  
Vol 27 (2) ◽  
pp. 137-146 ◽  
Author(s):  
F.A. Nichols
Keyword(s):  
Ceramic Fuel ◽  
Fuel Elements
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