An Overview of Corrosion Issues for the Design and Operation of High-Temperature Lead- and Lead-Bismuth-Cooled Reactor Systems

Ballinger, R. G.; Lim, Jeongyoun

doi:10.13182/nt04-a3540

Cited by 103 publications

(45 citation statements)

References 19 publications

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“…The primary factor limiting the technological viability of the Pb and Pb-Bi eutectic is their corrosive nature towards structural steels. Such coolant has tendency to corrode/dissolute alloying elements from the fuel cladding and structural materials [1,[5][6][7][8][9] within the reactor and causes liquid metal embrittlement (LME) [1,[10][11][12][13][14]. Oxide scales are known to be able to protect the structural alloys against the liquid metal corrosion [1,7].…”

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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“…Reactor systems experience a temperature gradient along the coolant path. Therefore, without a protective layer between a material and lead coolant, removal of materials from hot regions and their deposition in cooler regions can occur [Ballinger, et al, 2004]. This phenomenon creates a buildup of corrosion products which can potentially plug heat exchanger tubes.…”

Section: Chemical Propertiesmentioning

confidence: 99%

Flexible Conversion Ratio Fast Reactor Systems Evaluation

Todreas¹,

Hejzlar²

2008

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This is the final report under award DE-FC07-06ID14733, Project No. 06-040. Conceptual designs of lead-cooled and liquid salt-cooled fast flexible conversion ratio reactors were developed. Both concepts have cores rated at 2400MWt placed in a largepool-type vessel with dual-free level, which also contains four intermediate heat exchangers (IHXs) coupling a primary coolant to a compact and efficient supercritical CO 2 Brayton cycle power conversion system. Decay heat is removed passively using an enhanced Reactor Vessel Auxiliary Cooling System (RVACS) and a Passive Secondary Auxiliary Cooling System (PSACS). The most important findings were that (1) it is feasible to design the lead-cooled and salt-cooled reactor with the flexible conversion ratio (CR) in the range of CR=0 and CR=1 in a manner that achieves inherent reactor shutdown in unprotected accidents, (2) the salt-cooled reactor requires Lithium thermal Expansion Modules (LEM) to overcome the inherent salt coolant's large positive coolant temperature reactivity coefficient, (3) the preferable salt for fast spectrum high power density cores is NaCl-KCl-MgCl 2 as opposed to fluoride salts due to its better thermalhydraulic and neutronic characteristics, and (4) both reactor concepts achieve about 30% higher power density than the gas-cooled fast reactor, but attain power density 3 times smaller than that of the sodium-cooled reactor.

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“…Of interest to LBETF operations is the high-energy accelerator used in the specialized detection system. The accelerator is a transportable, pulsed electron accelerator (INL VARITRON) used to produce energetic (8)(9)(10)(11)(12) MeV) x-ray (bremsstrahlung) radiation.…”

Section: Inl Locationmentioning

confidence: 99%

“…A special issue of Nuclear Technology presented the actinide burning Pb (or Pb-alloy) cooled fission reactor concept. [3][4][5][6][7][8][9][10] The nine coordinated papers in this dedicated issue provide an inclusive review of the project, and demonstrate INL's technical competence in Pb-alloy cooled reactors.…”

Section: Introductionmentioning

confidence: 99%

Idaho National Laboratory Lead or Lead-Bismuth Eutectic (LBE) Test Facility - R&D Requirements, Design Criteria, Design Concept, and Concept Guidance

Loewen¹,

Demkowicz²

2005

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SUMMARYThe Idaho National Laboratory Lead-Bismuth Eutectic Test Facility will advance the state of nuclear technology relative to heavy-metal coolants (primarily Pb and Pb-Bi), thereby allowing the U.S. to maintain the pre-eminent position in overseas markets and a future domestic market. The end results will be a better qualitative understanding and quantitative measure of the thermal physics and chemistry conditions in the molten metal systems for varied flow conditions (single and multiphase), flow regime transitions, heat input methods, pumping requirements for varied conditions and geometries, and corrosion performance. Furthering INL knowledge in these areas is crucial to sustaining a competitive global position.This fundamental heavy-metal research supports the National Energy Policy Development Group's stated need for energy systems to support electrical generation.

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An Overview of Corrosion Issues for the Design and Operation of High-Temperature Lead- and Lead-Bismuth-Cooled Reactor Systems

Cited by 103 publications

References 19 publications

Characterisation of Oxides by Advanced Techniques

Characterisation of Oxides by Advanced Techniques

Flexible Conversion Ratio Fast Reactor Systems Evaluation

Idaho National Laboratory Lead or Lead-Bismuth Eutectic (LBE) Test Facility - R&D Requirements, Design Criteria, Design Concept, and Concept Guidance

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