An overview of neutron irradiation effects in LMFBR materials

Straalsund, J.L.; Powell, R.W.; Chin, Bryan A.

doi:10.1016/0022-3115(82)90499-8

Cited by 46 publications

(18 citation statements)

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“…Such a large volume change inevitably affects both thermo-mechanical properties and structural stability of material components in nuclear reactors as well as their successful and safe operation. Therefore, extensive experiments [3][4][5][6][7][8][9][10][11][12] and modeling [13][14][15][16][17][18] investigations have been carried out since void swelling was first observed in 1967 by Cawthorne and Fulton in stainless steel samples in the Dounready Fast Reactor [19]. The basic mechanisms responsible for void formation and growth, and the evolution of the damaged microstructure have been established during elevated temperature (0.3T m ~0.5T m , where T m is the melting temperature) irradiation.…”

Section: Introductionmentioning

confidence: 99%

Phase-field modeling of void evolution and swelling in materials under irradiation

et al. 2011

Sci. China Phys. Mech. Astron.

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Void swelling is an important phenomenon observed in both nuclear fuels and cladding materials in operating nuclear reactors. In this work we develop a phase-field model to simulate void evolution and void volume change in irradiated materials. Important material processes, including the generation of defects such as vacancies and self-interstitials, their diffusion and annihilation, and void nucleation and evolution, have been taken into account in this model. The thermodynamic and kinetic properties, such as chemical free energy, interfacial energy, vacancy mobility, and annihilation rate of vacancies and interstitials, are expressed as a function of temperature and/or defect concentrations in a general manner. The model allows for parametric studies of critical void nucleus size, void growth kinetics, and void volume fraction evolutions. Our simulations demonstrated that void swelling displays a quasi-bell shape distribution with temperature often observed in experiments. radiation, void swelling, vacancies, interstitials, phase-field model PACS: 61.80.Az, 61.72.Ji, 03.65.Vf

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Section: Introductionmentioning

confidence: 99%

Phase-field modeling of void evolution and swelling in materials under irradiation

et al. 2011

Sci. China Phys. Mech. Astron.

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“…They were selected for study based on their better high-temperature strength than stainless steel, improved high-temperature thermal creep strength, and excellent sodium compatibility. 18,19 Further, like stainless steel, there is substantial industrial experience in the processing, fabrication, and joining of these alloys. Under irradiation, the alloys with more than 40 wt.% nickel also underwent less swelling than stainless steel.…”

Section: Superalloysmentioning

confidence: 99%

Space fission reactor structural materials: Choices past, present, and future

Busby

Leonard

2007

JOM

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Nuclear powered spacecraft will enable missions well beyond the capabilities of current chemical, radioisotope thermoelectric generator and solar technologies. The use of fi ssion reactors for space applications has been studied for over 50 years. Structural material performance has often limited the potential performance of space reactors. Space fi ssion reactors are an extremely harsh environment for structural materials with high temperatures, high neutron fi elds, potential contact with liquid metals, and the need for up to 15-20 year reliability with no inspection or preventative maintenance. Many different structural materials have been proposed. While all of those proposed meet many of the requirements for space reactor service, none satisfy all of them. However, continued development and testing may resolve these issues and provide qualifi ed materials for fi ssion reactors for space power.

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“…He, [4] but this reaction requires production of 59 Ni first and results in an incubation time for helium production. Helium generation is very dependent on the energy spectrum, cross section and fluence and has been reported as atomic parts per million (appm) versus fluence for a variety of fast, thermal and mixed spectrums [9,[29][30][31][32][33].…”

Section: Radiation-induced Embrittlementmentioning

confidence: 99%

“…From 1974 to 1985, Ni-base alloys were investigated for advanced cladding and duct materials for the United States Liquid Metal Fast Breeder Reactor (LMFBR) [2]. Ni-base alloys were selected on the basis of their swelling resistance, sodium compatibility and high temperature thermal creep strength, coupled with an extensive industrial base for processing, fabrication and joining [3,4]. Early experiments revealed that Ni-base alloys with greater than about 40% Ni had excellent swelling resistance [5].…”

Section: Introductionmentioning

confidence: 99%

Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System

Angeliu¹,

Ward²,

Witter³

2006

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Abstract. Ni-base alloys were considered for the Prometheus space reactor pressure vessel with operational parameters of ~900 K for 15 years and fluences up to 160x10 20 n/cm 2 (E>0.1 MeV). This paper reviews the effects of irradiation on the behavior of Ni-base alloys and shows that radiation-induced swelling and creep are minor considerations compared to significant embrittlement with neutron exposure. While the mechanism responsible for radiation-induced embrittlement is not fully understood, it is likely a combination of helium embrittlement and solute segregation that can be highly dependent on the alloy composition and exposure conditions. Transmutation calculations show that detrimental helium levels would be expected at the end of life for the inner safety rod vessel (thimble) and possibly the outer pressure vessel, primarily from high energy (E>1 MeV) n,α reactions with 58 Ni.Helium from 10 B is significant only for the outer vessel due to the proximity of the outer vessel to the BeO control elements. Recommendations for further assessments of the material behavior and methods to minimize the effects of radiation damage through alloy design are provided. 2PACS Code: 61.82.-d

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An overview of neutron irradiation effects in LMFBR materials

Cited by 46 publications

References 1 publication

Phase-field modeling of void evolution and swelling in materials under irradiation

Phase-field modeling of void evolution and swelling in materials under irradiation

Space fission reactor structural materials: Choices past, present, and future

Assessing the Effects of Radiation Damage on Ni-base Alloys for the Prometheus Space Reactor System

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