A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 1: Phases and Phase Diagrams

Janney, Dawn E.; Hayes, S. L.; Adkins, Cynthia A.

doi:10.1080/00295450.2019.1578573

Cited by 13 publications

(5 citation statements)

References 64 publications

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“…Strangely enough, the f-phase was not reported in recent reviews of the Pu-Zr system [18][19][20] and reported in others. [1,2,21] As for the j-phase (PuZr 2 ), reported in the initial works of, [3,4] Lauthier et al [22] studied samples containing between 15 and 50 at.% Pu and did not observe its formation. The authors mentioned in the abstract (in English) that PuZr 2 can be synthetized from the elements only in the presence of oxygen, which considerably accelerates diffusion.…”

Section: Experimental Reviewmentioning

confidence: 97%

“…According to them, i transforms congruently into (d-Pu) at 608 K and 22 at.% zirconium and is readily distinguishable from the compound h. As only one report of this phase is available, further investigation is needed to confirm its existence and stability. [2] Finally, Maeda et al [30] determined the solidus and liquidus curves of the Pu-Zr system based on plutonium vapor pressure measurements (open symbols in Fig. 4) and calculated the solidus and liquidus boundaries (solid lines) assuming an ideal solution for the liquid phase and a regular solution behavior for the bcc phase (see details [30] ).…”

Section: Experimental Reviewmentioning

confidence: 99%

“…Metallic fuels have many advantages over ceramic fuels because of their high density, high linear and specific power, high breeding ratios, higher thermal conductivity, reduced fabrication costs due to larger diameter fuel elements, and easy fabricability. [1] However, as mentioned in a recent review, [2] understanding phases and phase relationships in advanced metallic nuclear fuels based on the ternary U-Pu-Zr system (e.g. U-20Pu-10Zr, wt%) is of vital importance for predicting their properties and behavior (e.g.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Experimental and Modeling Review of the Plutonium-Zirconium (Pu-Zr) System: Lost in Translation and Over Time?

Perron

Turchi

2020

J. Phase Equilib. Diffus.

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This article presents a review of the phase equilibria of the Pu-Zr system and discusses the contradictory reports on the experimental phase diagram and misinterpretations that have led to confusion over time. In addition, a review of the few Pu-Zr CALculation of PHAse Diagrams (CALPHAD) assessments is presented with emphasis on the heat of formation of the bcc phase, highlighting a disagreement between CALPHAD and ab initio calculations. Based on the information gathered in this study, a critical re-assessment of the Pu-Zr system involving the f (Pu 28 Zr), h (Pu 4 Zr), kinetically hindered j (PuZr 2 ), and once observed i phases is called for.This article is an invited paper selected from presentations at ''PSDK XIV: Phase Stability and Diffusion Kinetics-Gibbs: Phase Equilibria, Diffusion and Materials Design'' held during MS&T'19, September 29-October 3, 2019, in Portland, Oregon. The special sessions were dedicated to honor Dr. Patrice Turchi, recipient of the ASM International 2019 J. Willard Gibbs Phase Equilibria Award ''for outstanding and pioneering contributions in the application of first-principles, quantum-mechanical calculations to the modeling of phase equilibria and thermodynamic behavior of alloys.'' It has been expanded from its original presentation.

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Section: Experimental Reviewmentioning

confidence: 97%

Section: Experimental Reviewmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Experimental and Modeling Review of the Plutonium-Zirconium (Pu-Zr) System: Lost in Translation and Over Time?

Perron

Turchi

2020

J. Phase Equilib. Diffus.

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“…Information about the technologically important alloy U-20 Pu-10 Zr (in weight percent) is even more limited. 65 Researchers at ANL, the Los Alamos National Laboratory (LANL), and the Commissariet à l'Énergie Atomique (CEA) have reported original experimental values for the thermal conductivities of U-Pu-Zr alloys with ~15 to 20 wt% Pu and ~6 to 15 wt% Zr at varying temperatures. [66][67][68][69][70] All the original measurements were reported before ~1970, although they have been repeated in several more recent publications.…”

Section: Iiif Fuel Thermal Conductivitymentioning

confidence: 99%

“…[66][67][68][69][70] All the original measurements were reported before ~1970, although they have been repeated in several more recent publications. 65 The only value for thermal conductivity of the important alloy composition U- 20 Pu-10 Zr (in weight percent) was reported in a CEA report from 1964. The value is 0.084 W/cm K at 296 K (Ref.…”

Section: Iiif Fuel Thermal Conductivitymentioning

confidence: 99%

Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm

et al. 2021

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With the increasing interest in sodium fast reactor technology, as seen by applications to the U.S. Nuclear Regulatory Commission for the OKLO Aurora plant, fuel testing for the TerraPower Traveling Wave Reactor, and the impending construction and startup of the versatile test reactor (VTR), a modernized, accelerated approach to fuel qualification is needed. To guide this effort, a Phenomena Identification Ranking Table-styled analysis was performed for a U-Pu-Zr sodium-free annular fuel system. This analysis evaluated a series of fuel design properties and parameters against their contributions to key fuel performance phenomena. The resulting priority parameters were then reviewed against existing modeling and experimental capabilities to support investigation of the highest-priority parameters. A pathway for qualification was then established using highthroughput, high-volume experiments from MiniFuel and FAST in parallel with advanced physics-based model development. This effort outlines how the first stages of qualification can be reduced from the typical 20+-year development cycle to 5 to 7 years by deploying accelerated irradiation testing platforms. As with any accelerated test, these methods are prototypic in some aspects and less so in others; however, by coupling with advanced fuel performance modeling and simulation capabilities, the larger space of irradiation parameters and material response provided offers advantages for the validation of physics-based models supporting the deployment of novel fuel designs. As a test case, this paper utilizes a proposed Mark II fuel system for the upcoming VTR. Thus, an accelerated qualification method can be tested for the development of MARK II driver fuel so that by the time of VTR startup, lead test assemblies for a Mark II fuel can be initiated.

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Thermophysical and thermochemical properties of U-23wt.%Pu-6wt.%Zr alloy fuel: Computational and high temperature mass spectrometric studies

Trinadh

Manikandan

Bera

et al. 2020

Journal of Nuclear Materials

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A Critical Review of the Experimentally Known Properties of U-Pu-Zr Alloys. Part 1: Phases and Phase Diagrams

Cited by 13 publications

References 64 publications

Experimental and Modeling Review of the Plutonium-Zirconium (Pu-Zr) System: Lost in Translation and Over Time?

Experimental and Modeling Review of the Plutonium-Zirconium (Pu-Zr) System: Lost in Translation and Over Time?

Integrating Advanced Modeling and Accelerated Testing for a Modernized Fuel Qualification Paradigm

Thermophysical and thermochemical properties of U-23wt.%Pu-6wt.%Zr alloy fuel: Computational and high temperature mass spectrometric studies

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