advanced nuclear fuel fabrication: particle fuel …...ornl/spr-2019/1216 advanced nuclear fuel...
TRANSCRIPT
ORNL/SPR-2019/1216
Advanced Nuclear Fuel Fabrication: Particle Fuel Concept for TCR
Michael P. Trammell Brian C. Jolly M. Dylan Richardson Austin T. Schumacher Kurt A. Terrani
July 2019
DOCUMENT AVAILABILITY
Reports produced after January 1, 1996, are generally available free via US Department of Energy (DOE) SciTech Connect. Website www.osti.gov Reports produced before January 1, 1996, may be purchased by members of the public from the following source: National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone 703-605-6000 (1-800-553-6847) TDD 703-487-4639 Fax 703-605-6900 E-mail [email protected] Website http://classic.ntis.gov/ Reports are available to DOE employees, DOE contractors, Energy Technology Data Exchange representatives, and International Nuclear Information System representatives from the following source: Office of Scientific and Technical Information PO Box 62 Oak Ridge, TN 37831 Telephone 865-576-8401 Fax 865-576-5728 E-mail [email protected] Website http://www.osti.gov/contact.html
This report was prepared as an account of work sponsored by an
agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
ORNL/SPR-2019/1216
Transformational Challenge Reactor Program
Advanced Nuclear Fuel Fabrication: Particle Fuel Concept for TCR
Michael P. Trammell
Brian C. Jolly
M. Dylan Richardson
Austin T. Schumacher
Kurt A. Terrani
Date Published:
July 2019
Milestone M3CT-19OR06090130
Prepared by
OAK RIDGE NATIONAL LABORATORY
Oak Ridge, TN 37831-6283
managed by
UT-BATTELLE, LLC
for the
US DEPARTMENT OF ENERGY
under contract DE-AC05-00OR22725
This page is intentionally left blank.
iii
CONTENTS
CONTENTS .................................................................................................................................................iii LIST OF FIGURES ....................................................................................................................................... v ABSTRACT .................................................................................................................................................. 1 1. INTRODUCTION ................................................................................................................................. 2 2. FABRICATION METHODOLOGY .................................................................................................... 2
2.1 BINDERJET PRINTING OF SiC ............................................................................................... 3 2.2 CHEMICAL VAPOR INFILTRATION (CVI) PROCESS ........................................................ 4
3. CONCLUSION ..................................................................................................................................... 6 4. REFERENCES ...................................................................................................................................... 7
This page is intentionally left blank.
v
LIST OF FIGURES
Figure 1. Stages of fabrication to produce particle fuel demonstration element. .......................................... 3 Figure 2. X-ray tomography of post-CVI particle fuel element. ................................................................... 3 Figure 3. Illustration of the binderjet printing process. ................................................................................. 4 Figure 4. (a) CVI system. (b) Pre-CVI parts supported by a combination of graphite fixtures and
tungsten mesh. (c) A view inside the furnace during operation. ...................................................... 5 Figure 5. Microstructure of binderjet-printed and CVI-densified test disks.................................................. 5
This page is intentionally left blank.
1
ABSTRACT
This report presents an assessment of a novel fabrication method to produce a ceramic microencapsulated
fuel element for the Transformational Challenge Reactor (TCR) program. The proposed fuel concept uses
proven materials and fuel technology in combination with readily available advanced manufacturing
systems to further advance nuclear fabrication technology. The concept consists of TRISO-coated fuel
particles embedded in a silicon carbide matrix. The fabrication method begins with a low-density silicon
carbide capsule produced using binderjet additive manufacturing technology that is filled with TRISO
coated fuel particles and then densified with highly crystalline SiC in a chemical vapor infiltration (CVI)
process. The concept, fabrication methodology, and preliminary proof-of-principle demonstration are
described.
2
1. INTRODUCTION
The Transformational Challenge Reactor (TCR) program’s goal is to explore advanced manufacturing
technologies to enhance reactor performance while reducing cost and schedule of deployment for nuclear
power systems. These technologies can include, but are not limited to, any combination of advanced
materials and additive manufacturing methods that enable rapid fabrication of components with complex
geometry, composition, and properties not achievable by traditional manufacturing methods. One specific
area of interest that could significantly benefit from these technologies is the design and fabrication of the
fuel component. This paper describes a ceramic microencapsulated fuel design that builds on recent
developments in this area [1] and evolves the technology by combining the favorable properties of silicon
carbide and the flexibility of additive manufacturing, while continuing to leverage significant
advancements in coated particle fuel technology.
A significant achievement within the nuclear community that is incorporated into this concept is the
development and qualification of tri-structural isotropic (TRISO) coated particle fuel for gas-cooled
reactors [2]. The particle fuel consists of a fuel kernel (historically UO2 or UCO and recently UN [3])
with a diameter of 350-800 µm that is coated with pyrolytic carbon and silicon carbide layers that serve
many functions including structural support for the fuel kernel and fission product retention. For gas
cooled reactors, the coated fuel particles are embedded in a graphite matrix with an overcoating and
pressing process [4]. For the fuel concept described here, these coated fuel particles are directly
embedded in a silicon carbide matrix that is produced by a combination of binderjet printing and then
densification in a chemical vapor infiltration (CVI) process. The work described here is agnostic to the
exact type and geometry of the TRISO fuel particles. The TCR program is targeting TRISO particles with
800 µm UN kernels as the fuel to facilitate criticality with a small core.
The materials and fabrication processes used to produce this fuel design were selected based on specific
criteria. Silicon carbide is widely accepted as a desirable material for nuclear applications based on its
fission product retention, irradiation stability, and resistance to degradation under accident conditions [5].
SiC in powder form is very suitable for the binderjet printing process. The fabrication process begins with
a low-density silicon carbide capsule that is produced using binderjet technology. Binderjet printing is a
relatively recent additive manufacturing technique that provides design flexibility for complex features
such as fuel free zones and cooling channels that are otherwise difficult, if not impossible, to produce
using traditional fabrication methods. This is especially important for ceramic materials with only a few
fabrication routes available [6, 7]. The capsule is filled with a combination of TRISO-coated fuel particles
and loose SiC powder. At this stage, densification is required. For this concept, a CVI process was chosen
for densification based on several reasons: (a) it provides near theoretical density SiC [5], (b) the resulting
SiC satisfies high purity and irradiation performance requirements for nuclear reactor applications [5],
and (c) the process produces little to no dimensional change. Although the individual materials and
methods described here are well established, the combination presents an opportunity to further advance
fuel fabrication technology1.
2. FABRICATION METHODOLOGY
To assess the viability of the ceramic microencapsulated particle fuel concept, the proposed materials and
fabrication methods were used to produce a proof-of-principle demonstration element using surrogate
TRISO-coated particles. The process begins with SiC feedstock powder and a CAD file with an overly
exaggerated complex geometry capsule design. With binderjet technology, the printer works directly from
1 Patent Pending 62/769,588
3
this CAD file to produce a low-density (~35–45%TD) part comprised of the selected SiC feedstock
material. Once the print is complete, the designated fueled region of the capsule is loaded with a
combination of surrogate TRISO-coated particles and additional SiC powder. The SiC powder is needed
to fill the interstitial spaces between particles and is rolled smooth after filling is complete. The loaded
capsule is then densified in a CVI process to achieve microencapsulation of TRISO particles in a SiC
matrix. The steps to achieve this process are illustrated in Figure 1. The binderjet and CVI processes are
discussed in subsequent sections of this report.
Figure 1. Stages of fabrication to produce particle fuel demonstration element.
Results from x-ray tomography are shown in Figure 2. This image reveals surrogate TRISO fuel particles
in the designated fueled region of the capsule design. The image also showcases the complex network of
interconnected cooling channels that can be achieved with the binderjet/CVI method.
Figure 2. X-ray tomography of post-CVI particle fuel element.
2.1 BINDERJET PRINTING OF SiC
The binderjet process is an additive manufacturing technology that could provide a cost-effective
opportunity for printing ceramic materials with complex geometry for nuclear applications. The process
begins with a built-in software that slices the model of the desired part into sequential 2D layers. The
printhead travels across a powder bed and selectively delivers binder in the shape of the first cross
sectional layer (Figure 3a). The next step, referred to as recoating, consists of several functions (Figure
3b). During the recoating process, the base plate is lowered by the predetermined layer height (typically
50–100 µm), and powder is delivered across the print area. After powder delivery, a counter-rotating
roller travels across the print area to set the layer height and smooth the powder bed in preparation for the
next print layer. The next layer in the sequence is printed, and the process continues to repeat until
4
complete. Once the printing process is complete, the job-box is removed and placed in an air oven at
190°C for ~6 hours. This process fully cures the binder and produces a finished part that is embedded in
loose powder (Figure 3c). The parts are then extracted and cleaned.
Figure 3. Illustration of the binderjet printing process.
At this stage, the printed part has a relatively low density (35–45%TD) and consists of the feedstock
powder bound together with residual binder. To be useful, binderjet-printed parts are typically densified
and/or strengthened by several techniques, including precursor infiltration and pyrolysis (PIP), reactive
melt infiltration (RMI), or direct sintering [7]. The technique used for post processing can vary depending
on the feedstock powder material and the application. For this application and as a novel solution, CVI
was chosen for densification and is described in the subsequent section of this report.
2.2 CHEMICAL VAPOR INFILTRATION (CVI) PROCESS
After the capsule is binderjet printed, it is filled with TRISO particles and loose SiC powder in
preparation for densification. A CVI process is used to densify the capsule by filling the voids in the
printed part and the loose powder while encapsulating the TRISO-coated particles. This process increases
density, provides a hermetic seal, and provides mechanical integrity, all while maintaining dimensional
stability throughout the process.
The CVI system consists of a quartz tube inside a clamshell-style furnace that allows the temperature and
pressure to be independently controlled. Figure 4 illustrates the equipment and demonstration capsule
both before (Figure 4b) and during (Figure 4c) the process. In the initial steps of the CVI process, the
desired temperature and pressures are achieved under inert conditions. Note, during this step, the residual
binder from the binderjet printing process is baked out. After heating, the CVI system introduces methyl
trichlorosilane as the precursor, which decomposes on the surface of solid powder particles to yield high purity and crystalline SiC [8]. In this case, the CVI process was initiated at 1000ºC under below-
atmospheric pressure with H2 flowing into the coating chamber. A carrier gas, H2, was routed through a
bubbler to achieve an adequate volume flow rate of methyl trichlorosilane.
5
Figure 4. (a) CVI system. (b) Pre-CVI parts supported by a combination of graphite fixtures and tungsten
mesh. (c) A view inside the furnace during operation.
Results from density and microstructure characterization performed on 5 mm radius by 3 mm thick disks
fabricated using this binderjet/CVI method indicate that a relatively high density (~90%TD) can be
achieved for thin sections. The microstructure of these test disks can be seen in Figure 5 and shows that
some internal porosity still exists. Initially, the CVI process uniformly densifies the green part by
depositing a fully dense coating on all internal and external surfaces. However, as the pores inside the
material close, an outer layer develops (Figure 5b) to create a robust hermetic seal. As the material
thickness increases, it becomes more difficult for precursor gasses to reach the inner porosity, and this
could potentially cause a density gradient. This effect may be reduced by optimizing processing
conditions.
Figure 5. Microstructure of binderjet-printed and CVI-densified test disks.
6
3. CONCLUSION
The TCR program is interested in accessing advanced materials and fabrication methods to further the
advancement of nuclear technology. In this report, a preliminary investigation to assess the possibilities of
producing a ceramic microencapsulated particle fuel concept fabricated using a combination of binderjet
printing and CVI is explored. To determine the viability of this concept, a commercially available
binderjet system was used to produce a fuel capsule from SiC powder. The capsule was filled with a
combination of surrogate TRISO particles and additional SiC powder and then densified in a CVI
process. In conclusion, the results indicate the following:
• Binderjet technology can successfully be used to print complex geometry capsules from SiC
feedstock powder.
• The binderjet-printed capsule will survive the CVI process (binder burnout) even when fully loaded
with particles and SiC powder.
• Densification in a CVI process is achievable and provides suitable density and microstructure.
7
4. REFERENCES
[1] K.A. Terrani, J.O. Kiggans, Y. Katoh, K. Shimoda, F.C. Montgomery, B.L. Armstrong, C.M. Parish,
T. Hinoki, J.D. Hunn, L.L. Snead, Fabrication and characterization of fully ceramic microencapsulated
fuels, J Nucl Mater 426 (2012) 268-276.
[2] D. Petti, J. Maki, J. Hunn, P. Pappano, C. Barnes, J. Saurwein, S. Nagley, J. Kendall, R. Hobbins, The
DOE Advanced Gas Reactor Fuel Development and Qualification Program, Jom-Us 62 (2010) 62-66.
[3] T.B. Lindemer, C.M. Silva, J.J. Henry, J.W. McMurray, S.L. Voit, J.L. Collins, R.D. Hunt,
Quantification of process variables for carbothermic synthesis of UC1-xNx fuel microspheres, J Nucl
Mater 483 (2017) 176-191.
[4] P.J. Pappano, T.D. Burchell, J.D. Hunn, M.P. Trammell, A novel approach to fabricating fuel
compacts for the next generation nuclear plant (NGNP), J Nucl Mater 381 (2008) 25-38.
[5] L.L. Snead, T. Nozawa, Y. Katoh, T.S. Byun, S. Kondo, D.A. Petti, Handbook of SiC properties for
fuel performance modeling, J Nucl Mater 371 (2007) 329-377.
[6] W.C. Du, X.R. Ren, C. Ma, Z.J. Pei, Binder Jetting Additive Manufacturing of Ceramics: A Literature
Review, Proceedings of the Asme International Mechanical Engineering Congress and Exposition, 2017
Vol 14 (2018).
[7] X.Y. Lv, F. Ye, L.F. Cheng, S.W. Fan, Y.S. Liu, Binder jetting of ceramics: Powders, binders,
printing parameters, equipment, and post-treatment, Ceram Int 45 (2019) 12609-12624.
[8] H.O. Pierson, Handbook of Chemical Vapor Deposition, 2nd Edition: Principles, Technology and
Applications, Elsevier Science1999.