Alloying effects on the corrosion behavior of binary Nb-based and Mo-based alloys in liquid Li

Saito, Junichi; Inoue, Satoshi; Kano, Shigeki; Yuzawa, Toshikatsu; Furui, Mitsuaki; Morinaga, Masahiko

doi:10.1016/s0022-3115(98)00460-7

Cited by 6 publications

(5 citation statements)

References 4 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Data on wet corrosion of the candidate structural materials were obtained from the open literature [12][13][14][15][16][17][18][19]. As a general outcome of this study, alkali metals, such as Na, are found to be less corrosive than lead-bismuth alloys.…”

Section: Corrosion Of Core Internalsmentioning

confidence: 99%

“…While from the mechanical point of view, Mo-TZM alloy seems to be the preferable high temperature material, some engineering issues emerge. Oxidation of this alloy at high temperature is a concern [4,16] as well as manufacturability and welding. While oxidation of ODS steels does not seem to be a particular issue [13], manufacturability and welding presents similar issues to Mo-TZM alloy.…”

Section: Proposed Materials and Design Guidelinesmentioning

confidence: 99%

“…In addition the dose reduction from the core provides the necessary fission product release barriers, allowing for confinement instead of containment. The criteria that no longer apply due to the modified confinement are Containment Design (16) and Containment Heat Removal (38). The design criteria Containment Atmospheric Cleanup (41), Containment Design Basis (50), Fracture Prevention of Containment Pressure Boundary (51), Primary Containment Isolation (56), and Closed Systems Isolation Valves (57) are still valid and will be met in the final design.…”

Section: San Andreas Faultmentioning

confidence: 99%

“…The properties of the candidate structural materials were obtained from the open literature [3][4][5][6][7][8][9][10][11][12][13][14][15][16][17][18], in particular from databases on materials proposed for high-temperature fusion applications.…”

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

Solid0Core Heat-Pipe Nuclear Batterly Type Reactor

Greenspan¹

2008

View full text Add to dashboard Cite

This project was devoted to a preliminary assessment of the feasibility of designing an Encapsulated Nuclear Heat Source (ENHS) reactor to have a solid core from which heat is removed by liquid-metal heat pipes (HP). Like the SAFE 400 space nuclear reactor core, the HP-ENHS core is comprised of fuel rods and HPs embedded in a solid structure arranged in a hexagonal lattice in a 3:1 ratio. The core is oriented horizontally and has a square rather cylindrical cross section for effective heat transfer. The HPs extend from the two axial reflectors in which the fission gas plena are embedded and transfer heat to an intermediate coolant that flows by natural-circulation. The HP-ENHS is designed to preserve many features of the ENHS including 20-year operation without refueling, very small excess reactivity throughout life, natural circulation cooling, walkaway passive safety, and robust proliferation resistance. The target power level and specific power of the HP-ENHS reactor are those of the reference ENHS reactor. Compared to previous ENHS reactor designs utilizing a lead or lead-bismuth alloy natural circulation cooling system, the HP-ENHS reactor offers a number of advantageous features including: (1) significantly enhanced passive decay heat removal capability; (2) no positive void reactivity coefficients; (3) relatively lower corrosion of the cladding (4) a core that is more robust for transportation; (5) higher temperature potentially offering higher efficiency and hydrogen production capability. This preliminary study focuses on five areas: material compatibility analysis, HP performance analysis, neutronic analysis, thermal-hydraulic analysis and safety analysis. Of the four hightemperature structural materials evaluated, Mo TZM alloy is the preferred choice; its upper estimated feasible operating temperature is 1350 K. HP performance is evaluated as a function of working fluid type, operating temperature, wick design and HP diameter and length. Sodium is the preferred working fluid and the HP working temperature can be as high as 1300 K. It is feasible to achieve criticality and to maintain a nearly zero burn-up reactivity swing for at least 20 EFPY with an average linear heat generation rate (LHR) of 90W/cm. The preferred design utilizes nitride fuel made of natural nitrogen and loaded with depleted uranium and TRU from LWR spent fuel cooled for approximately 30 years. The preferred intermediate coolant is LiF-BeF ; its average outlet temperature is ~ 1040K. Effective heat transfer to the intermediate coolant is obtained with HPs extending out of the core less than 50 cm. The required reactor vessel height is significantly smaller than that of the reference ENHS: 9 vs. ~20 m. The vessel diameter is slightly larger: 4 vs. ~ 3.5 m. In conclusion, it appears feasible to design a HP-ENHS reactor to achieve its primary design objectives. The resulting HP-ENHS reactor concept is unique in offering sustainable proliferation-resistant nuclear energy that can be delivered at very high temperatures. A number of outsta...

show abstract

Section: Corrosion Of Core Internalsmentioning

confidence: 99%

Section: Proposed Materials and Design Guidelinesmentioning

confidence: 99%

Section: San Andreas Faultmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Solid0Core Heat-Pipe Nuclear Batterly Type Reactor

Greenspan¹

2008

View full text Add to dashboard Cite

show abstract

“…For example, the Mo, Nb, Ta and W alloys are expected to be one of the super-heat resisting materials durable in severe nuclear environments of fast breeder reactor [1]. It is known that Mo, Nb, Ta and W metals are mutually soluble and can form solid-solution refractory alloys with each other in any proportion.…”

Section: Introductionmentioning

confidence: 99%

Analytic calculation of formation enthalpies directly from interatomic potentials for binary and ternary refractory metal systems

Dai

Xing-Lai

et al. 2010

Sci. China Technol. Sci.

View full text Add to dashboard Cite

An analytic method is proposed to calculate the formation enthalpy directly from empirical n-body potential and applied to the binary and ternary systems consisting of the refractory metals Mo, Nb, Ta and W. It turns out that the calculated enthalpies are in overall agreement with experimental observations and some other theoretical calculations. Interestingly, it shows that the formation enthalpies of the ternary systems are significantly affected by those of the constituent binary systems. n-body potential, refractory materials, ternary systems, thermodynamic computations Citation:Dai Y, Li J H, Che X L, et al. Analytic calculation of formation enthalpies directly from interatomic potentials for binary and ternary refractory metal systems. Sci China Tech Sci

show abstract

Corrosion characteristics of Mo and TZM alloy for plasma facing components in molten lithium at 623 K

Meng

et al. 2022

Corrosion Science

View full text Add to dashboard Cite

Alloying effects on the corrosion behavior of binary Nb-based and Mo-based alloys in liquid Li

Cited by 6 publications

References 4 publications

Solid0Core Heat-Pipe Nuclear Batterly Type Reactor

Solid0Core Heat-Pipe Nuclear Batterly Type Reactor

Analytic calculation of formation enthalpies directly from interatomic potentials for binary and ternary refractory metal systems

Corrosion characteristics of Mo and TZM alloy for plasma facing components in molten lithium at 623 K

Contact Info

Product

Resources

About