An Analysis of Testing Requirements for Fluoride Salt Cooled High Temperature Reactor Components

Holcomb, David Eugene; Cetiner, Mustafa Sacit; Flanagan, G.F.; Peretz, F.J.; Yoder, G.L.

doi:10.2172/970926

Cited by 26 publications

(41 citation statements)

References 18 publications

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“…This structure is typical of existing power plants and is currently sized to allow two parallel turbine-generator sets. An attached structure (10) houses the intermediate salt-to-steam cycle heat exchangers and some turbine facility support equipment. A low wing on the turbine building houses the condensate/feedwater equipment.…”

Section: Fig 7 Overall Plant Layoutmentioning

confidence: 99%

AHTR Mechanical, Structural, and Neutronic Preconceptual Design

Varma¹,

Holcomb²,

Peretz³

et al. 2012

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Section: Fig 7 Overall Plant Layoutmentioning

confidence: 99%

AHTR Mechanical, Structural, and Neutronic Preconceptual Design

Varma¹,

Holcomb²,

Peretz³

et al. 2012

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“…7 Li, 4,5,18 which implies that further separation will be impractical because of limitations in isotope separation technology and prohibitive costs. Furthermore, 6 Li can be generated in situ when lithium fluoride-beryllium fluoride (FLiBe) coolant salt is circulated in a neutron-rich environment (e.g., in the core).…”

Section: Coolant Salt Compositionmentioning

confidence: 99%

“…1,5 If the FliBe coolant were to be replaced with some other primary coolant salt, other candidate salts would have to meet the same strict requirements, including thermal stability at high temperature, stability in a neutron rich environment, and suitable thermolytic properties. 18,19 Primary salt mixtures must also be compatible with the uranium, plutonium and thorium salts that act as fuel, and which may be dissolved in the primary salt (as in a fuel salt); alternatively these could leak into the primary salt if the fuel is physically separated from the salt (as in a pebble bed or prismatic type FHR). Secondary coolants also need to be specified for thermal properties; however compatibility with fluorinated fissile isotopes (such as UF 4 or PuF 4 ) is necessary only in the event of catastrophic failures that lead to mixing of the primary and secondary coolants.…”

Section: Coolant Salt Compositionmentioning

confidence: 99%

Tritium Formation and Mitigation in High Temperature Reactors

Sabharwall¹,

Stoots²

2012

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Tritium is a radiologically active isotope of hydrogen. It is formed in nuclear reactors by neutron absorption and ternary fission events and can subsequently escape into the environment. In order to prevent the tritium contamination of proposed reactor buildings and surrounding sites, this paper examines the root causes and potential solutions for the production of this radionuclide, including materials selection and inert gas sparging. A model is presented that can be used to predict permeation rates of hydrogen through metallic alloys at temperatures from 450-750ιC. Results of the diffusion model are presented for one steadystate value of tritium production in the reactor.

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“…Laser Doppler velocimetry has been suggested for determining the primary coolant mass flow within helium-cooled HTGRs by monitoring the velocity of entrained graphite dust particles within the flow . A potentially related flow measurement method, optically based diaphragm deflection measurement, is being considered as a potential technique for direct high-temperature measurement of differential pressures in liquid salt flowmeters (Holcomb et al 2009). …”

Section: Introductionmentioning

confidence: 99%

“…Remote optical vibration monitoring may be particularly effective for the in-vessel EM pump and motor components used in pool-type AdvSMR designs, as well as reactor superstructure components used in all designs. A potentially related method, optically based diaphragm deflection measurement, has been suggested as a possibly advantageous technique for direct high-temperature measurement of differential pressures in liquid salt flowmeters (Holcomb et al 2009). …”

Section: Introductionmentioning

confidence: 99%

Technical Readiness and Gaps Analysis of Commercial Optical Materials and Measurement Systems for Advanced Small Modular Reactors

Anheier¹,

Suter²,

Qiao³

et al. 2013

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Energy Research and Development Roadmap and industry stakeholders by evaluating optically based instrumentation and control (I&C) concepts for advanced small modular reactor (AdvSMR) applications. These advanced designs will require innovative thinking in terms of engineering approaches, materials integration, and I&C concepts to realize their eventual viability and deployment. The primary goals of this report include:1. Establish preliminary I&C needs, performance requirements, and possible gaps for AdvSMR designs based on best-available published design data.2. Document commercial off-the-shelf (COTS) optical sensors, components, and materials in terms of their technical readiness to support essential AdvSMR in-vessel I&C systems.3. Identify technology gaps by comparing the in-vessel monitoring requirements and environmental constraints to COTS optical sensor and materials performance specifications.4. Outline a future research, development, and demonstration (RD&D) program plan that addresses these gaps and develops optical-based I&C systems that enhance the viability of future AdvSMR designs.The DOE-NE roadmap outlines RD&D activities intended to overcome technical barriers that currently limit advances in nuclear energy. As part of this strategy, DOE-NE is sponsoring research on advanced reactor supportive technologies to reduce the identified barriers. Key challenges that must be overcome include the high capital costs to develop nuclear power plants, maintaining safety performance as the reactor fleet expands, minimizing nuclear waste, and maintaining strong proliferation resistance. AdvSMR designs are a major component of this strategy, because these designs offer a number of unique advantages. The modular and small size of AdvSMR designs naturally lead to reduced capital investments and, potentially, construction savings through factory fabrication. However, new economic and technical challenges accompany the many attractive features offered by AdvSMR designs. Specifically, the modest power output of AdvSMRs does not provide the economy of scale afforded by large reactors. In addition, many of the AdvSMR designs operate at much higher temperatures than lightwater reactors and require instrumentation to withstand harsh, in-vessel environments arising from unconventional, chemically aggressive coolants and unique reactor system configurations.Addressing these I&C challenges will be critically important to the AdvSMR development program to ensure the viability and future success of advanced reactor designs. Solutions will likely be found through evolution of conventional reactor technology, and the development of entirely new concepts. Early pressure/boiling water reactors used conventional I&C technologies (e.g., thermocouples, ionchambers, strain-gauge pressure sensors) to satisfy design requirements. Because these technologies worked well in the relatively low-temperature reactor designs, the demand for alternate I&C technologies was limited. At the time, optical-based reactor monitoring concepts were g...

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An Analysis of Testing Requirements for Fluoride Salt Cooled High Temperature Reactor Components

Cited by 26 publications

References 18 publications

AHTR Mechanical, Structural, and Neutronic Preconceptual Design

AHTR Mechanical, Structural, and Neutronic Preconceptual Design

Tritium Formation and Mitigation in High Temperature Reactors

Technical Readiness and Gaps Analysis of Commercial Optical Materials and Measurement Systems for Advanced Small Modular Reactors

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