The Mechanical Design of TRISO-Coated Particle Fuels for the Large HTGR

Gulden, T. D.; Smith, C. L.; Harmon, D.P.; Hudritsch, W. W.

doi:10.13182/nt72-a31179

Cited by 36 publications

(4 citation statements)

References 9 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…[9][10][11][12][13][14][15][16][17][18][19]. Samples that either failed to meet the TRISO coating design basis (Ref, [9][10][11][12][13][14][15][16][17][18][19][20][21][22][23][24][25][26][27][28] or had one or more coatings purposely designed to evaluate LHTGR fuel particle specification limits are not included. The data were obtained from fuel capsules P13L, P13M, P13N, P13P, P13R, and P13S, Results from all unbonded particle samples in each test that satisfy the LHTGR TRISO UC" pressure vessel design basis are included in Table 9-22, as are results from all reference LHTGR TRISO UCfuel that has been irradiated in unbonded particle tests.…”

Section: -1 and 9-21mentioning

confidence: 99%

HTGR fuels and core development program. Quarterly progress report for the period ending November 30, 1974

1975

View full text Add to dashboard Cite

Section: -1 and 9-21mentioning

confidence: 99%

HTGR fuels and core development program. Quarterly progress report for the period ending November 30, 1974

1975

View full text Add to dashboard Cite

“…This study is motivated by the increase in energy consumption and the efforts underway to search for alternative energy sources, including active studies in the field of nuclear and thermonuclear energy. In Kazakhstan, in recent years, new materials for future nuclear and nuclear fuel cycle facilities have been widely studied [ 1 , 2 , 3 , 4 ]; reactor [ 5 , 6 , 7 , 8 , 9 , 10 , 11 , 12 , 13 , 14 , 15 , 16 ] and out-of-pile [ 17 , 18 , 19 ] experiments simulating their operating conditions have been conducted. One area of such work is corrosion testing of materials for the high-temperature gas reactor (HTGR), a Generation IV in the early design stage [ 20 , 21 , 22 , 23 ].…”

Section: Introductionmentioning

confidence: 99%

Study of Morphological, Structural, and Strength Properties of Model Prototypes of New Generation TRISO Fuels

et al. 2022

View full text Add to dashboard Cite

The purpose of this work is to characterize the morphological, structural, and strength properties of model prototypes of new-generation TRi-structural ISOtropic particle fuel (TRISO) designed for Generation IV high-temperature gas reactors (HTGR-type). The choice of model structures consisting of inner pyrolytic carbon (I-PyC), silicon carbide (SiC), and outer pyrolytic carbon (O-PyC) as objects of research is motivated by their potential use in creating a new generation of fuel for high-temperature nuclear reactors. To fully assess their full functional value, it is necessary to understand the mechanisms of resistance to external influences, including mechanical, as in the process of operation there may be external factors associated with deformation and leading to the destruction of the surface of fuel structures, which will critically affect the service life. The objective of these studies is to obtain new data on the fuel properties, as well as their resistance to external influences arising from mechanical friction. Such studies are necessary for further tests of this fuel on corrosion and irradiation resistance, as closely as possible to real conditions in the reactor. The research revealed that the study samples have a high degree of resistance to external mechanical influences, due to the high strength of the upper layer consisting of pyrolytic carbon. The presented results of the radiation resistance of TRISO fuel testify to the high resistance of the near-surface layer to high-dose irradiation.

show abstract

“…The outermost layer is another high-density, isotropic outer PyC layer that protects the SiC during the remainder of the fabrication process and imparts structural stability to the particles during irradiation. 7,8) The significance of SiC coatings is that they maintain the strength of the TRISO particles from the internal pressure exerted by gas evolution from the inner sides of the particles. [9][10][11][12][13] From the point of view on safety of the fusion structures, it is necessary to study their facture strength and the behavior of materials precisely with the same dimensions and fabrication processes of TRISO nuclear fuel particles.…”

Section: Introductionmentioning

confidence: 99%

High-Temperature Fracture Strength of a CVD-SiC Coating Layer for TRISO Nuclear Fuel Particles by a Micro-Tensile Test

Lee¹,

Park²,

Park

et al. 2015

Journal of the Korean Ceramic Society

View full text Add to dashboard Cite

Silicon carbide (SiC) coatings for tri-isotropic (TRISO) nuclear fuel particles were fabricated using a chemical vapor deposition (CVD) process onto graphite. A micro-tensile-testing system was developed for the mechanical characterization of SiC coatings at high temperatures. The fracture strength of the SiC coatings was characterized by the developed micro-tensile test in the range of 25°C to 1000°C. Two types of CVD-SiC films were prepared for the micro-tensile test. SiC-A exhibited a large grain size (0.4~0.6 m) and the [111] preferred orientation, while SiC-B had a small grain size (0.2~0.3 mm) and the [220] preferred orientation. Free silicon (Si) was co-deposited onto SiC-B, and stacking faults also existed in the SiC-B structure. The fracture strengths of the CVD-SiC coatings, as measured by the high-temperature micro-tensile test, decreased with the testing temperature. The high-temperature fracture strengths of CVD-SiC coatings were related to the microstructure and defects of the CVD-SiC coatings.

show abstract

The Mechanical Design of TRISO-Coated Particle Fuels for the Large HTGR

Cited by 36 publications

References 9 publications

HTGR fuels and core development program. Quarterly progress report for the period ending November 30, 1974

HTGR fuels and core development program. Quarterly progress report for the period ending November 30, 1974

Study of Morphological, Structural, and Strength Properties of Model Prototypes of New Generation TRISO Fuels

High-Temperature Fracture Strength of a CVD-SiC Coating Layer for TRISO Nuclear Fuel Particles by a Micro-Tensile Test

Contact Info

Product

Resources

About