Chemical Research and Development for Molten-Salt Breeder Reactors.

Grimes, W.R.

doi:10.2172/4355677

Cited by 44 publications

(78 citation statements)

References 2 publications

(1 reference statement)

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“…The 229 Th, available at both sites was recovered from 233 U, which was in long-term storage at ORNL. This 233 U was produced in kilogram quantities in the 1960s by neutron irradiation of 232 Th in molten salt breeder reactors [28]. Another radionuclide of interest, 223 Ra, has a half-life of 11.4 days and also emits four alpha particles in its decay chain.…”

Section: Heavy α-Emittersmentioning

confidence: 99%

New developments in the experimental data for charged particle production of medical radioisotopes

Ditrói

Tárkányi

Takács

et al. 2015

J Radioanal Nucl Chem

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The goal of the present work is to give a review of developments achieved experimentally in the field of nuclear data for medically important radioisotopes in the last three years. The availability and precision of production related nuclear data is continuously improved mainly experimentally. This review emphasizes a couple of larger fields: the Mo/Tc generator problem and the generator isotopes in general, heavy alpha-emitters and the rare-earth elements. Other results in the field of medical radioisotope production are also listed.

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Section: Heavy α-Emittersmentioning

confidence: 99%

New developments in the experimental data for charged particle production of medical radioisotopes

Ditrói

Tárkányi

Takács

et al. 2015

J Radioanal Nucl Chem

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“…Hence, multicomponent eutectic mixtures characterized by a single melting point are needed to reduce the melting temperature to less than 500°C. Combining multiple salts to form a eutectic composition provides compositional and phase stability, and therefore, uniform thermophysical properties in the operating temperature range (Grimes et al 1972;Ingersoll et al 2007). …”

Section: Applicationsmentioning

confidence: 99%

Technology Development Roadmap for the Advanced High Temperature Reactor Secondary Heat Exchanger

Sabharwall¹,

McCllar²,

Siahpush³

et al. 2012

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Date v EXECUTIVE SUMMARYThis Technology Development Roadmap (TDRM) study presents the path forward for deploying large-scale molten salt secondary heat exchangers and presents the benefits of using molten salt as the heat transport medium for advanced high temperature reactors. The roadmap will aid in the development and selection of the required heat exchanger for power production (the first anticipated process heat application), and other process heat applications, such as, hydrogen, methanol to gasoline, and ammonia production. It also (a) establishes the current state of readiness for molten salt secondary heat exchanger technology, (b) defines a path forward that systematically and effectively tests this technology to overcome areas of uncertainty, (c) demonstrates the achievement of an appropriate level of maturity prior to construction and plant operation, and (d) identifies issues and prioritizes future work for maturing the state of secondary heat exchangers technology.The TDRM was developed to identify the research and development activities, modeling, design, fabrication, and scaled testing that must occur to satisfy the requirements of advancing technological readiness. TDRMs provide the framework and structure required to systematically perform decision analysis, reduce risk, and mature technologies in a cost effective and timely manner. The roadmap uses the Technology Readiness Level (TRL) as a measure of the level of technical maturity of a technology, that is, the ability to design, fabricate, and deploy a component or system. The Secondary Heat Exchanger (SHX) is currently at a TRL-3 and the challenges addressed in this study must be overcome to mature this technology into a viable and reliable heat transfer system. Also addressed in this study is the potential future work, which will help in further enhancing the SHX TRL.This study discusses the results of a preliminary design analysis of the SHX. The efficient transfer of energy for industrial applications depends on the ability to incorporate cost-effective heat exchangers between the nuclear heat transport system and industrial process heat transport system. The heat exchanger required for AHTR is subjected to a unique set of conditions that bring with them several design challenges not encountered in standard heat exchangers. The somewhat corrosive molten salts, especially at higher temperatures, require materials throughout the system to avoid corrosion, and adverse high-temperature effects such as creep.Fuels salts received considerable testing and development in the Molten Salt Reactor Experiment (MSRE) program at Oak Ridge National Laboratory during the 1950s through 1970s, but relatively little research has been conducted on coolant salts. The corrosion data for various alloys in coolant salts (i.e., FLiBe, FLiNaK, KCl-MgCl 2 , NaNO 2 -NaNO 3 -KNO 3 and KF-ZrF 4 ) are too limited for reliable comparisons of corrosion resistance of the various alloys, or the relative aggressiveness of these molten salts.Tritium produced in the Advanced ...

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“…Hence, multicomponent eutectic mixtures are needed to reduce the melting temperature to less than 500°C and are characterized by a single melting point. Combining multiple salts to form a eutectic composition provides compositional and phase stability, and therefore, uniform thermophysical properties in the operating temperature range (Grimes et al 1972;Ingersoll et al 2007). …”

Section: Molten Salt As Intermediate Coolantmentioning

confidence: 99%

Process Heat Exchanger Options for the Advanced High Temperature Reactor

Sabharwall¹,

Kim²,

McKellar³

et al. 2011

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This study defines the design options for a secondary heat exchanger that couples the intermediate loop of a molten-salt-cooled nuclear reactor to a power production process. It is the first of several studies needed to select, develop, and demonstrate a secondary heat exchanger. In particular, it identifies design options affecting the functional and operational requirements of the secondary heat exchanger. The reference reactor design and configuration is a 3,400 MW(t) advanced high temperature reactor with three primary heat transfer loops. Multiple power conversion schemes are analyzed for a reactor outlet temperature of approximately 700°C. The applicability of other high temperature process heat applications that might eventually be coupled to the advanced high temperature reactor is also presented. An evaluation of viable secondary heat exchanger concepts is presented along with the parameters such as materials selection, system configuration, and coolant properties that will affect the secondary heat exchanger design. This study sets the stage for the two evaluations-a comparative analysis study and a feasibility study-that will follow. vi vii SUMMARYThe strategic goal of the Advanced Reactor Concept Program for the advanced high temperature reactor (AHTR) is to broaden the environmental and economic benefits of nuclear energy in the U.S. economy by producing power to meet growing energy demands and demonstrating an AHTR's applicability to market sectors not being served by light water reactors. This study is the first of three that will aid in the development and selection of the secondary heat exchanger (SHX) for power production from the AHTR, supporting large-scale deployment. The study identifies design options that will affect the functional and operational requirements of the SHX, and sets the stage for the comparative analysis and feasibility studies that will follow.Heat in the AHTR will be transferred from the reactor core by the primary liquid-salt coolant to an intermediate heat-transfer loop through an intermediate heat exchanger. The intermediate heat-transfer loop will circulate intermediate liquid-salt coolant through as many as three SHXs to transfer the heat to the power production process. Electric power generation was the principal process considered, but other processes were also evaluated because the heat transfer characteristics of molten salt coolants offer some advantages compared to high temperature gases produced by certain other reactor types.A broad comparison of molten salt coolants identified 11 for more detailed analysis, which led to the selection of three as potential intermediate loop coolants: LiF-NaF-KF (FLiNaK), KF-ZrF 4 , and KCl-MgCl 2 . Previous studies, which identified LiF-NaF-KF and KF-ZrF 4 as promising molten salt coolants, were confirmed. The high neutron cross-sections of KCl-MgCl 2 have generally disqualified it from use in the primary loop of thermal reactors, but do not disqualify its use as a coolant in the intermediate loop. Recent evaluations ...

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Chemical Research and Development for Molten-Salt Breeder Reactors.

Cited by 44 publications

References 2 publications

New developments in the experimental data for charged particle production of medical radioisotopes

New developments in the experimental data for charged particle production of medical radioisotopes

Technology Development Roadmap for the Advanced High Temperature Reactor Secondary Heat Exchanger

Process Heat Exchanger Options for the Advanced High Temperature Reactor

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