Lead-cooled system design and challenges in the frame of Generation IV International Forum

Cinotti, L.; Smith, Craig F.; Sekimoto, Hiroshi; Mansani, L.; Reale, Marco; Sienicki, James J.

doi:10.1016/j.jnucmat.2011.04.042

Cited by 71 publications

(22 citation statements)

References 2 publications

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“…Heavy liquid metals are considered as potential coolants in fast reactor designs and have potentially advantageous physical and thermal-hydraulic properties [1][2][3][4]. The primary factor limiting the technological viability of the Pb and Pb-Bi eutectic is their corrosive nature towards structural steels.…”

Section: Introductionmentioning

confidence: 99%

Characterisation of Oxides by Advanced Techniques

Duchoň

Halodová

Lorincink

et al. 2018

Acta Metall. Slovaca

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For the safe development of GenIV nuclear reactors, it is necessary to study the compatibility of structural materials with new coolants. Current work describes the behavior of ferriticmartensitic steel T91 in a Heavy Liquid Metal environment. Specimens were pre-stressed up to yield strength and subsequently exposed to the lead-bismuth eutectic (LBE) under static conditions for 2000 hours. The goal was to identify the susceptibility to crack initiation under selected experimental conditions. The examination of metal-LBE interface was done in a reference position of the sample using the SEM equipped with EDX. Formation of oxide scales observed on the interface had no signs of crack initiation. The oxide was characterized by a twolayer structure. A TEM lamella was created from the sample by a FIB in-situ lift-out technique and it was subsequently analyzed in HRTEM. Individual oxide layers were identified and characterized by SAED, EELS and EDS techniques. Finally, STEM-HAADF and EFTEM techniques were used to visualize the matrix-oxide interface.

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Section: Introductionmentioning

confidence: 99%

Characterisation of Oxides by Advanced Techniques

Duchoň

Halodová

Lorincink

et al. 2018

Acta Metall. Slovaca

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“…However, several challenges including robust processing of highly radioactive salt mixture and corrosion of circuit components remain unsolved [27]. LFR has low capital cost due to simple design, and also efficiently utilizes neutron and uranium [28]. Disadvantages are mainly due to the dense, corrosive and erosive nature of the lead, including higher pumping power and safety problem.…”

Section: Nuclear Energy and Sodium-cooled Fast Reactormentioning

confidence: 99%

Effects of Nuclear Energy on Sustainable Development and Energy Security: Sodium-Cooled Fast Reactor Case

Lee

Yoon

2016

Sustainability

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Abstract:We propose a stepwise method of selecting appropriate indicators to measure effects of a specific nuclear energy option on sustainable development and energy security, and also to compare an energy option with another. Focusing on the sodium-cooled fast reactor, one of the highlighted Generation IV reactors, we measure and compare its effects with the standard pressurized water reactor-based nuclear power, and then with coal power. Collecting 36 indicators, five experts select seven key indicators to meet data availability, nuclear energy relevancy, comparability among energy options, and fit with Korean energy policy objectives. The results show that sodium-cooled fast reactors is a better alternative than existing nuclear power as well as coal electricity generation across social, economic and environmental dimensions. Our method makes comparison between energy alternatives easier, thereby clarifying consequences of different energy policy decisions.

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“…The neutronic characteristics of the LFR core also allow for long-life cores, resulting in a significant extension of reactor cycle, which minimizes the proliferation risk and diversion of weapon-usable heavy isotopes. Lead also retains volatile contaminants produced in the fission process and during activation of the coolant, especially isotopes of cesium and iodine [8].…”

Section: Lead-cooled Fast Reactormentioning

confidence: 99%

“…For the neutron transport calculations, the MCB may use various evaluated crosssection libraries processed for the arbitrary temperature step in ENDF [12] format; e.g., JEF, JEFF, JENDL, ENDF-B/VI-8, EAF 8 , and others. The additional sets of nuclear data are required for the simulation of nuclide formation due to the natural decay and nuclear reactions.…”

Section: Nuclear Datamentioning

confidence: 99%

The MCB Code for Numerical Modeling of Fourth Generation Nuclear Reactors

Oettingen

Cetnar

Mirowski

2015

csci

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R&D in the nuclear reactor physics demands state-of-the-art numerical tools that are able to characterize investigated nuclear systems with high accuracy. In this paper, we present the Monte Carlo Continuous Energy Burnup Code (MCB) developed at AGH University's Department of Nuclear Energy. The code is a versatile numerical tool dedicated to simulations of radiation transport and radiation-induced changes in matter in advanced nuclear systems like Fourth Generation nuclear reactors.We present the general characteristics of the code and its application for modeling of Very-High-Temperature Reactors and Lead-Cooled Fast Rectors. Currently, the code is being implemented on the supercomputers of the Academic Computer Center (CYFRONET) of AGH University and will soon be available to the international scientific community.

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Lead-cooled system design and challenges in the frame of Generation IV International Forum

Cited by 71 publications

References 2 publications

Characterisation of Oxides by Advanced Techniques

Characterisation of Oxides by Advanced Techniques

Effects of Nuclear Energy on Sustainable Development and Energy Security: Sodium-Cooled Fast Reactor Case

The MCB Code for Numerical Modeling of Fourth Generation Nuclear Reactors

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