Creep behaviour of δ-phase of U–Zr system by impression creep technique

Kutty, T.R.G.; Basak, C.B.; Kumar, Arun; Kamath, H.S.

doi:10.1016/j.jnucmat.2010.11.016

Cited by 15 publications

(7 citation statements)

References 44 publications

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“…A model for combined secondary thermal creep and irradiation creep for U-Pu-Zr fast reactor fuel is available, with the creep rate modeled as a function of time, fuel porosity, effective stress, and fission rate. The constitutive relation is taken from Kutty et al [51] and is given aṡ…”

Section: Thermal and Irradiation Creep [Creepupuzr]mentioning

confidence: 99%

BISON Theory Manual The Equations behind Nuclear Fuel Analysis

et al. 2016

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Section: Thermal and Irradiation Creep [Creepupuzr]mentioning

confidence: 99%

BISON Theory Manual The Equations behind Nuclear Fuel Analysis

et al. 2016

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Section: Fuel Creep Model: Upuzrcreepupdatementioning

confidence: 99%

Summary and Assessment of Metal Fuel Capabilities in Bison

Novascone

Casagranda

Matthews

et al. 2018

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The work described in this report was performed under funding from the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. This report is issued in satisfaction of the level 2 milestone M2MS-18IN0201012 on Release Bison with Initial Metallic Fuel Performance Capability. Metallic fuel development began in Bison a few years after light water reactor development began (∼ 2009). The initial development was funded by the Advanced Fuels Campaign. With recent interest from industry, the Nuclear Regulatory Commission, and the Versatile Test Reactor program, the Nuclear Energy Modeling Simulation Program has increased funding for metallic fuel development and validation in FY18. The material models with the most mature development are binary uranium-zirconium and ternary uranium-plutonium-zirconium alloys for fuel and HT9 for cladding. The first material models were incorporated from open literature sources, which include mechanical and thermal material properties that are functions of temperature, porosity, and zirconium concentration, swelling, fission gas release, zirconium diffusion, creep, and sodium coolant channel boundary conditions. These material models have been utilized to simulate ERB-II fuel pins and the results compared to measurements. The EBR-II experiment measurements mostly consist of cladding strain and zirconium redistribution. As such, comparisons to EBR-II measurements are currently limited to these two figures of merit. Simulations and comparisons to experiment measurements have also been done for transient testing of EBR-II fuel pins in TREAT, which included temperature measurements. Preliminary comparisons between Bison calculations and experiment measurements are favorable. These comparisons have also highlighted the importance of the fuel swelling and fission gas release models on cladding strain. Also, Bison metallic fuel simulations are currently being run in support of ATR experiments and VTR exploratory design calculations. Further development and evaluation of individual material models and fuel system models are planned for FY19.

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“…For the α + δ phase: (10) For the γ phase: (11) For the β + γ transition phase: (12) where ( 13) and ( 14)…”

Section: Specific Heatmentioning

confidence: 99%

BISON and MARMOT Development for Modeling Fast Reactor Fuel Performance

Gamble¹,

Williamson²,

Schwen³

et al. 2015

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BISON and MARMOT are two codes under development at the Idaho National Laboratory for engineering scale and lower length scale fuel performance modeling. So far, the majority of development has been focused on fuels of light water reactors. It is desired to add capabilities for fast reactor applications to these codes. The fast reactor fuel types under consideration are metal (U-Pu-Zr) and oxide (MOX). The cladding types of interest include 316SS, D9, and HT9. The purpose of this report is to outline the proposed plans for code development and provide an overview of the models added to the BISON and MARMOT codes for fast reactor fuel behavior through the end of FY-2015. A brief overview of preliminary discussions on the formation of a bilateral agreement between the Idaho National Laboratory and the National Nuclear Laboratory in the United Kingdom is presented.

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Creep behaviour of δ-phase of U–Zr system by impression creep technique

Cited by 15 publications

References 44 publications

BISON Theory Manual The Equations behind Nuclear Fuel Analysis

BISON Theory Manual The Equations behind Nuclear Fuel Analysis

Summary and Assessment of Metal Fuel Capabilities in Bison

BISON and MARMOT Development for Modeling Fast Reactor Fuel Performance

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