☆ 4.7 Article

Investigation on thermo-mechanical performance of fully ceramic microencapsulated fuel

JOURNAL OF NUCLEAR MATERIALS (2021)

相关参考文献

注意：仅列出部分参考文献，下载原文获取全部文献信息。

Article Materials Science, Multidisciplinary

Modeling of irradiation-induced thermo-mechanical coupling and multi-scale behavior in a fully ceramic-microencapsulated fuel pellet

Hongyang Wei et al.

Summary: A new method to model the irradiation-induced thermo-mechanical behavior of fully ceramic microencapsulated fuels is established in this study, and a fuel performance code called TMAIMF is developed based on ABAQUS platform. Numerical simulation results indicate that the deformations of FCM pellets are dominated by the thermal expansion and irradiation swelling of SiC matrix, while the gas-induced effective expansion strains in the porous carbon layer protect the pellet from cracking.

JOURNAL OF NUCLEAR MATERIALS (2021)

添加到收藏夹

Article Nuclear Science & Technology

Neutronic performance of fully ceramic microencapsulated of uranium oxycarbide and uranium nitride composite fuel in SMR

Yahya A. Al-Zahrani et al.

Summary: This study explores the potential advantages of microencapsulated fuels for the SMART reactor, investigating detailed designs and fuel assembly configurations with different fuel types, and their effects on criticality, burn up, and power peaking factor. The nitride (UN) and carbide (UCO) fuel types are considered safer and more beneficial compared to standard uranium oxides due to their mechanical stability, enhanced thermal conductivity, and high fuel density.

ANNALS OF NUCLEAR ENERGY (2021)

添加到收藏夹

Article Nuclear Science & Technology

Preliminary numerical investigation of TRISO-matrix interface debonding characteristics in fully ceramic microencapsulated fuel

Cheng Zhang et al.

Summary: The bonding mode between NITE-SiC matrix and TRISO particles significantly affects the fracture mechanisms of Fully Ceramic Microencapsulated (FCM) fuel. A finite element method (FEM) model based on the cohesive zone model (CZM) was presented to analyze the debonding characteristics of TRISO-matrix interface. The CZM was coupled with various irradiation and thermo-mechanical behaviors, and used to investigate the interface debonding characteristics of TRISO coated FCM Fuel. The effects of burnup, particle spacing, stress distributions, interfacial bonding strength, and other key parameters in the CZM model were studied and investigated.

ANNALS OF NUCLEAR ENERGY (2021)

添加到收藏夹

Review Materials Science, Multidisciplinary

A review of in-pile fuel safety tests of TRISO fuel forms and future testing opportunities in non-HTGR applications

Nicholas R. Brown

JOURNAL OF NUCLEAR MATERIALS (2020)

添加到收藏夹

Article Nuclear Science & Technology

Multidimensional multiphysics modeling of TRISO particle fuel with SiC/ZrC coating using modified fission gas release model

Cheng Zhang et al.

ANNALS OF NUCLEAR ENERGY (2020)

添加到收藏夹

Review Materials Science, Multidisciplinary

Coated particle fuel: Historical perspectives and current progress

Paul A. Demkowicz et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

添加到收藏夹

Article Nuclear Science & Technology

Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost

Cihang Lu et al.

NUCLEAR ENGINEERING AND DESIGN (2019)

添加到收藏夹

Article Materials Science, Multidisciplinary

The study of irradiation-induced failure behavior for the TRISO-coated fuel particle in HTGR

Rong Li et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

添加到收藏夹

Review Materials Science, Multidisciplinary

Materials for future nuclear energy systems

G. S. Was et al.

JOURNAL OF NUCLEAR MATERIALS (2019)

添加到收藏夹

Review Nuclear Science & Technology

Enhanced thermal conductivity accident tolerant fuels for improved reactor safety - A comprehensive review

Wei Zhou et al.

ANNALS OF NUCLEAR ENERGY (2018)

添加到收藏夹

Article Materials Science, Multidisciplinary

Irradiation stability and thermo-mechanical properties of NITE-SiC irradiated to 10 dpa

Kurt A. Terrani et al.

JOURNAL OF NUCLEAR MATERIALS (2018)

添加到收藏夹

Article Nuclear Science & Technology

Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON

D. Schappel et al.

NUCLEAR ENGINEERING AND DESIGN (2018)

添加到收藏夹

Article Nuclear Science & Technology

The potential impact of Fully Ceramic Microencapsulated (FCM) fuel on thermal hydraulic performance of SMART reactor

Sarah Kamalpour et al.

NUCLEAR ENGINEERING AND DESIGN (2018)

添加到收藏夹

Article Nuclear Science & Technology

Determining the minimum required uranium carbide content for HTGR UCO fuel kernels

Jacob W. McMurray et al.

ANNALS OF NUCLEAR ENERGY (2017)

添加到收藏夹

Article Materials Science, Multidisciplinary

Progress on matrix SiC processing and properties for fully ceramic microencapsulated fuel form

K. A. Terrani et al.

JOURNAL OF NUCLEAR MATERIALS (2015)

添加到收藏夹

Article Materials Science, Multidisciplinary

High temperature steam oxidation of SiC coating layer of TRISO fuel particles

Kurt A. Terrani et al.

JOURNAL OF NUCLEAR MATERIALS (2015)

添加到收藏夹

Article Materials Science, Multidisciplinary

First high temperature safety tests of AGR-1 TRISO fuel with the Fuel Accident Condition Simulator (FACS) furnace

Paul A. Demkowicz et al.

JOURNAL OF NUCLEAR MATERIALS (2015)

添加到收藏夹

Article Nuclear Science & Technology

Neutronics evaluation of a super-deep-burn with TRU Fully Ceramic Microencapsulated (FCM) fuel in CANDU

Donny Hartanto et al.

PROGRESS IN NUCLEAR ENERGY (2015)

添加到收藏夹

Article Materials Science, Multidisciplinary

Accident tolerant fuels for LWRs: A perspective

S. J. Zinkle et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

添加到收藏夹

Article Materials Science, Multidisciplinary

Stability of SiC-matrix microencapsulated fuel constituents at relevant LWR conditions

L. L. Snead et al.

JOURNAL OF NUCLEAR MATERIALS (2014)

添加到收藏夹

Article Nuclear Science & Technology

Conceptual core design of an innovative small PWR utilizing fully ceramic microencapsulated fuel

Xiang Dai et al.

PROGRESS IN NUCLEAR ENERGY (2014)

添加到收藏夹

Article Nuclear Science & Technology

Neutronic evaluation of a PWR with fully ceramic microencapsulated fuel. Part II: Nodal core calculations and preliminary study of thermal hydraulic feedback

Nicholas R. Brown et al.

ANNALS OF NUCLEAR ENERGY (2013)

添加到收藏夹

Article Materials Science, Multidisciplinary

Multidimensional multiphysics simulation of TRISO particle fuel

J. D. Hales et al.

JOURNAL OF NUCLEAR MATERIALS (2013)

添加到收藏夹

Article Materials Science, Multidisciplinary

Microstructure of TRISO coated particles from the AGR-1 experiment: SiC grain size and grain boundary character

Rita Kirchhofer et al.

JOURNAL OF NUCLEAR MATERIALS (2013)

添加到收藏夹

Article Materials Science, Multidisciplinary

Microencapsulated fuel technology for commercial light water and advanced reactor application

Kurt A. Terrani et al.

JOURNAL OF NUCLEAR MATERIALS (2012)

添加到收藏夹

Article Materials Science, Multidisciplinary

Fabrication and characterization of fully ceramic microencapsulated fuels

K. A. Terrani et al.

JOURNAL OF NUCLEAR MATERIALS (2012)

添加到收藏夹

Review Materials Science, Multidisciplinary

A review of TRISO fuel performance models

Jeffrey J. Powers et al.

JOURNAL OF NUCLEAR MATERIALS (2010)

添加到收藏夹

Article Materials Science, Multidisciplinary

Handbook of SiC properties for fuel performance modeling

Lance L. Snead et al.

JOURNAL OF NUCLEAR MATERIALS (2007)

添加到收藏夹

Article Nuclear Science & Technology

Considerations pertaining to the achievement of high burn-ups in HTR fuel

DG Martin

NUCLEAR ENGINEERING AND DESIGN (2002)

添加到收藏夹

Article Nuclear Science & Technology

Modeling of fuel performance and metallic fission product release behavior during HTTR normal operating conditions

K Verfondern et al.

NUCLEAR ENGINEERING AND DESIGN (2001)

添加到收藏夹

© Peeref 2019-2024. All rights reserved.