TRISO-Coated Particle Fuel Fabrication and Performance

Demkowicz, Paul A.; Petti, David A.; Sawa, Kôichiro; Maki, John T.; Hobbins, R.R.

doi:10.1016/b978-0-12-803581-8.11785-0

Cited by 7 publications

(10 citation statements)

References 48 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The initial fractional porosities were assumed to be 0.010 for the UO 2 kernel; 0.560 for the buffer; 0.160 for iPyC; 0.006 for SiC and 0.166 for oPyC [52] .…”

Section: Porositymentioning

confidence: 99%

Peridynamic Modelling of Cracking in TRISO Particles for High Temperature Reactors

Haynes¹,

Battistini²,

Leide³

et al. 2023

Preprint

View full text Add to dashboard Cite

A linear-elastic computer simulation (model) for a single particle of TRISO fuel has been built using a bond-based peridynamic technique implemented in the finite element code 'Abaqus'. The model is able to consider the elastic and thermal strains in each layer of the particle and to simulate potential fracture both within and between layers. The 2D cylindrical model makes use of a plane stress approximation perpendicular to the plane modelled. The choice of plane stress was made by comparison of 2D and 3D finite element models. During an idealised ramp to normal operating power for a kernel of 0.267 W and a bulk fuel temperature of 1305 K, cracks initiate in the buffer near to the kernel-buffer interface and propagate towards the buffer-iPyC coating interface, but do not penetrate the iPyC and containment of the fission products is maintained. In extreme accident conditions, at around 600% (1.60 W) power during a power ramp at 100% power (0.267 W) per second, cracks were predicted to form on the kernel side of the kernel-buffer interface, opposite existing cracks in the buffer. These were predicted to then only grow further with further increases in power. The SiC coating was predicted to subsequently fail at a power of 940% (2.51 W), with cracks formed rapidly at the iPyC-SiC interface and propagating in both directions. These would overcome the containment to fission gas release offered by the SiC 'pressure vessel'. The extremely high power at which failure was predicted indicates the potential safety benefits of the proposed high temperature reactor design based on TRISO fuel.

show abstract

“…The initial fractional porosities were assumed to be 0.010 for the UO 2 kernel; 0.560 for the buffer; 0.160 for iPyC; 0.006 for SiC and 0.166 for oPyC [52] .…”

Section: Porositymentioning

confidence: 99%

Peridynamic Modelling of Cracking in TRISO Particles for High Temperature Reactors

Haynes¹,

Battistini²,

Leide³

et al. 2023

Preprint

View full text Add to dashboard Cite

show abstract

“…It lowers the risk of proliferation by reducing the possibility of plutonium being produced from uranium fuel. Furthermore, its neutronic properties would be ideal for the TRISO fuel, which is a well‐known technology and is marketed as the most durable nuclear fuel design 15,16 …”

Section: Introductionmentioning

confidence: 99%

“…Furthermore, its neutronic properties would be ideal for the TRISO fuel, which is a well-known technology and is marketed as the most durable nuclear fuel design. 15,16 Neutron leakage in a big reactor core is roughly 3%, but SMR or MMR core neutron leakage ranges from 5% to 9% due to smaller axial and radial dimensions, resulting in lower fuel utilization and lower discharge burnup, particularly in single-batch fuel loadings. 17 Thorium fuel usage employing the TRISO duplex fuel design has proven in prior study that it can provide higher burnup, better fuel utilization, and longer cycle length.…”

mentioning

confidence: 99%

The neutronics effect of TRISO duplex fuel packing fractions and their comparison with homogeneous thorium‐uranium fuel

Rabir

Ismail

Yahya

2022

Intl J of Energy Research

View full text Add to dashboard Cite

“…Figure 1. Overview of how TRISO particle kernels are made into both prismatic block-type and pebble bed-type HTGR fuel (Demkowicz et al 2020).…”

Section: Introductionmentioning

confidence: 99%

“…REFERENCES .......................................................................................................................................... Figure 1. Overview of how TRISO particle kernels are made into both prismatic block-type and pebble bed-type HTGR fuel (Demkowicz et al 2020)…”

mentioning

confidence: 99%

A White Paper: Disposition Options for a High-Temperature Gas-Cooled Reactor

Kitcher

2020

View full text Add to dashboard Cite

The high-temperature gas-cooled reactor (HTGR) is a uranium-fueled, graphite-moderated, gas-cooled nuclear reactor design concept capable of producing very high core outlet temperatures. Both types of HTGR have the tristructural isotropic (TRISO) fuel kernel at the heart of the fuel design. For the prismatic block-type HTGR, the TRISO particles are overcoated with a resinated graphitic matrix and pressed into fuel compacts, which are then heat treated and placed in the fuel channels of the prismatic-block-shaped fuel assemblies. For the pebble-bed-type HTGR, the TRISO particles are dispersed in a graphitic-matrix sphere, which is the basic unit for the reactor core. Despite having very different fuel designs, both types of HTGR are graphite-moderated, gas-cooled, thermal reactors using many of the same materials. As a result, both prismatic-block-type and pebble-bed-type HTGRs have similar radioactive waste streams, all of which require safe and secure storage and eventual disposition. Modern HTGR designs are based on a long and rich operating history of several different graphite-moderated, gas-cooled, thermal reactors. Several of these reactors have been shut down, the fuel has been placed in safe storage, and they have undergone some degree of decommissioning. As such, there is significant experience in the management of the spent nuclear fuel (SNF) and radioactive wastes associated with operating these reactors. This white paper will, (1) identify the definitions and regulations that apply to the safe and secure management, storage, and disposal of radioactive waste; and (2) identify the key radioactive waste streams from HTGRs and their characteristics. Idaho National Laboratory (INL) has significant experience in the management of SNF from HTGR predecessors. This experience should form the basis for the management and disposition efforts of the radioactive waste from any new HTGR-type small modular reactor, or microreactor intended for deployment at the INL site.

show abstract

TRISO-Coated Particle Fuel Fabrication and Performance

Cited by 7 publications

References 48 publications

Peridynamic Modelling of Cracking in TRISO Particles for High Temperature Reactors

Peridynamic Modelling of Cracking in TRISO Particles for High Temperature Reactors

The neutronics effect of TRISO duplex fuel packing fractions and their comparison with homogeneous thorium‐uranium fuel

A White Paper: Disposition Options for a High-Temperature Gas-Cooled Reactor

Contact Info

Product

Resources

About