Irradiation creep in non-fissile metals and alloys

Harries, D.R.

doi:10.1016/0022-3115(77)90052-6

Cited by 42 publications

(6 citation statements)

References 42 publications

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“…Mosedale et al 62 described the g=t versus dpa creep curve for STA PE16 as parabolic, though the maximum observed creep rate was similar to that in austenitic steels and Harries 59 represented the creep strain above a threshold dose of 8 dpa (N/2) by For PE16 in a STA condition (1 h at 1080 C plus 16 h at 700 C), creep at dose rates of $5 Â 10 À7 dpa (N/2) s À1 was characterized by an initial period of low strain and an increased creep rate at higher displacement doses.…”

Section: Irradiation Creepmentioning

confidence: 92%

“…Several reviews of irradiation creep data are available in the literature, for example, by Harries, 59 Ehrlich, 60 and Garner, 61 and although these have tended to focus on austenitic steels, the behavior of nickel-based alloys generally appears to be similar. However, some insight into irradiation creep mechanisms is given in Section 4.04.4.1, where the effect of stress on the evolution of dislocation structures is described.…”

Section: Irradiation Creepmentioning

confidence: 99%

“…DFR data for austenitic steels and Nimonic PE16 were reviewed by Mosedale et al 62 and Harries, 59 and results for PE16 were reported in full by Lewthwaite and Mosedale. DFR data for austenitic steels and Nimonic PE16 were reviewed by Mosedale et al 62 and Harries, 59 and results for PE16 were reported in full by Lewthwaite and Mosedale.…”

Section: Irradiation Creepmentioning

confidence: 99%

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Radiation Effects in Nickel-Based Alloys

Boothby

2012

Comprehensive Nuclear Materials

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Section: Irradiation Creepmentioning

confidence: 92%

Section: Irradiation Creepmentioning

confidence: 99%

Section: Irradiation Creepmentioning

confidence: 99%

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Radiation Effects in Nickel-Based Alloys

Boothby

2012

Comprehensive Nuclear Materials

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“…A creep analysis was also performed as a function of the design variables and time dependent applied stress. After evaluating several irradiation creep models [26][27][28][29], we adopted a model which assumes the irradiation creep rate to depend linearly on stress and dpa rate at a given temperature. Irradiation creep coefficients were obtained from the open literature [9,30].…”

Section: Core Mechanical Analysismentioning

confidence: 99%

“…In particular, the modular construction of the core and the molten salt barrier should allow criteria 60 -62 to be met, and the large heat capacity of the salt and the negative temperature coefficient of the core should allow 10-12 to be met. (26), and thus cannot meet Combined Reactivity Control Systems Capability (27).…”

Section: San Andreas Faultmentioning

confidence: 99%

Solid0Core Heat-Pipe Nuclear Batterly Type Reactor

Greenspan¹

2008

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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...

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Irradiation Performance of Cladding and Structural Steels in Liquid Metal Reactors

Garner

2006

Materials Science and Technology

153

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Irradiation creep in non-fissile metals and alloys

Cited by 42 publications

References 42 publications

Radiation Effects in Nickel-Based Alloys

Radiation Effects in Nickel-Based Alloys

Solid0Core Heat-Pipe Nuclear Batterly Type Reactor

Irradiation Performance of Cladding and Structural Steels in Liquid Metal Reactors

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