Internal Gelation as Applied to the Production of Uranium Nitride Space Nuclear Fuel

Author(s):  
W. J. Carmack
2018 ◽  
Vol 117 (sup1) ◽  
pp. s76-s81 ◽  
Author(s):  
Tashiema L. Wilson ◽  
Emily E. Moore ◽  
Denise Adorno Lopes ◽  
Vancho Kocevski ◽  
Elizabeth Sooby Wood ◽  
...  
Keyword(s):  

2018 ◽  
Vol 44 (6) ◽  
pp. 6739-6746 ◽  
Author(s):  
Wei Tian ◽  
M.A. Pouchon ◽  
Hangxu Guo ◽  
Denglei Chen ◽  
Xiaojie Yin ◽  
...  

2020 ◽  
Vol 528 ◽  
pp. 151842 ◽  
Author(s):  
Scott Middlemas ◽  
Zilong Hua ◽  
Vinay Chauhan ◽  
W. Tanner Yorgason ◽  
Robert Schley ◽  
...  

2012 ◽  
Vol 57 ◽  
pp. 111-116 ◽  
Author(s):  
M. Cabanes-Sempere ◽  
C. Cozzo ◽  
S. Vaucher ◽  
J.M. Catalá-Civera ◽  
M.A. Pouchon

2004 ◽  
Vol 92 (12) ◽  
Author(s):  
Rodney D. Hunt ◽  
Jack L. Collins

SummaryIn the 1970s and 1980s, U.S. Department of Energy (DOE) conducted numerous studies on the fabrication of nuclear fuel particles using the internal gelation process. These amorphous kernels were prone to flaking or breaking when gases tried to escape from the kernels during calcination and sintering. These earlier kernels would not meet today´s proposed specifications for reactor fuel. In the interim, the internal gelation process has been used to create hydrous metal oxide microspheres for the treatment of nuclear waste. With the renewed interest in advanced nuclear fuel by the DOE, the lessons learned from the nuclear waste studies were recently applied to the fabrication of uranium kernels, which will become tri-isotropic (TRISO) fuel particles. These process improvements included equipment modifications, small changes to the feed formulations, and a new temperature profile for the calcination and sintering. The modifications to the laboratory-scale equipment and its operation as well as small changes to the feed composition increased the product yield from 60% to 80%–99%. The new kernels were substantially less glassy, and no evidence of flaking was found. Finally, key process parameters were identified, and their effects on the uranium microspheres and kernels are discussed.


JOM ◽  
2021 ◽  
Author(s):  
S. S. Parker ◽  
S. Newman ◽  
A. J. Fallgren

AbstractRecent interest in compact nuclear reactors for applications in space or in remote locations drives innovation in nuclear fuel design, especially non-oxide ceramic nuclear fuels. This work details neutronic modeling designed to support the development of a new nuclear fuel concept based on a mixture of thorium and uranium nitride. A Monte Carlo N-Particle Version 6.2 (MCNP-6) model of a compact 10 MWe reactor design which incorporates (ThxU1−x)N fuel is presented. In this context, a “compact” reactor is a completely assembled reactor which may be emptied of coolant and transported by specialized commercial vehicle, deployed by a C130J aircraft, or launched into space. Core geometry, reflector barrels, and the heat exchange zones are designed to support reduction of overall reactor volume of core components while maintaining criticality with a fixed total fuel mass of 4500 kg. Dense mixed nitrides of thorium nitride (ThN) additions in uranium nitride (UN) in 5 wt.% increments between $$0.05 \le x \le 0.5$$ 0.05 ≤ x ≤ 0.5 have been considered for calculation of $$k_{\infty }$$ k ∞ and $$k_{{{\text{effective}}}}$$ k effective . ThN additions in UN results in a slight increase in the magnitude of the temperature coefficient of reactivity, which is negative by design. The isotopic distribution of the principal actinide inventory as a function of burnup, time, and initial fuel composition is presented and discussed within the context of the proliferation risk of this core design.


2014 ◽  
Vol 69 ◽  
pp. 139-143 ◽  
Author(s):  
R.D. Hunt ◽  
R.R. Hickman ◽  
J.L. Ladd-Lively ◽  
K.K. Anderson ◽  
R.T. Collins ◽  
...  

2010 ◽  
Vol 401 (1-3) ◽  
pp. 55-59 ◽  
Author(s):  
R.D. Hunt ◽  
J.D. Hunn ◽  
J.F. Birdwell ◽  
T.B. Lindemer ◽  
J.L. Collins

Author(s):  
Lisa Grande ◽  
Wargha Peiman ◽  
Sally Mikhael ◽  
Bryan Villamere ◽  
Adrianexy Rodriguez-Prado ◽  
...  

SuperCritical Water-cooled nuclear Reactors (SCWRs) utilize a light-water coolant pressurized to 25 MPa with a channel inlet temperature of 350°C and outlet temperature of 625°C. Previous studies have indicated that uranium dioxide (UO2) nuclear fuel may not be suitable for SCWR use, because the maximum fuel centerline temperature might exceed the industry accepted limit of 1850°C. This research paper explores the use of uranium nitride (UN) as an alternative fuel option to UO2 at SuperCritical Water (SCW) conditions. A generic 1200-MWel Pressure-Tube (PT) -type reactor cooled with SCW was used for this thermalhydraulics analysis. The selected fuel option must have a fuel centerline temperature not higher than the industry accepted limit of 1850°C. Furthermore, the sheath (clad) temperature must not exceed the design limit of 850°C. The sheath and bundle geometry were adopted from previous studies. A single fuel channel was modeled using the UN fuel and an Inconel-600 sheath for several Axial Heat Flux Profiles (AHFPs). Uniform, upstream-skewed cosine, cosine and downstream-skewed cosine AHFPs were used. For each AHFP bulk-fluid, sheath and fuel centerline temperatures, and Heat Transfer Coefficient (HTC) profiles were calculated along the heated length of the channel. The calculations show that the UN fuel maintains a centerline temperature well below the industry accepted limit due to its high thermal conductivity at high temperatures. Therefore, the UN nuclear fuel is a viable fuel option for PT-type SCWRs.


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