Relevant bibliographies by topics / Versatile Test Reactor

Academic literature on the topic 'Versatile Test Reactor'

Author: Grafiati
Published: 10 December 2022
Last updated: 28 January 2023

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Journal articles on the topic "Versatile Test Reactor"

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Ritter, Christopher, Jeren Browning, Peter Suyderhoud, Ross Hays, AnnMarie Marshall, Kevin Han, Taylor Ashbocker, John Darrington, and Lee Nelson. "Versatile Test Reactor Open Digital Engineering Ecosystem." INSIGHT 25, no. 1 (March 2022): 56–60. http://dx.doi.org/10.1002/inst.12374.

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Jarrett, Michael, and Florent Heidet. "ENRICHMENT ZONING STUDY FOR THE VERSATILE TEST REACTOR." EPJ Web of Conferences 247 (2021): 12007. http://dx.doi.org/10.1051/epjconf/202124712007.

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The primary mission of the Versatile Test Reactor (VTR) is to provide peak fast flux in excess of 4.0 x 1015n/cm2-s to support fuel and material testing. To achieve a high fast flux, it is beneficial to maximize the flux peaking in the center of the core. With a single enrichment zone, a highly peaked flux distribution produces a highly peaked power distribution. Coolant inlet orifices can be designed to handle the peaked power distribution but orifice design can be simplified if a more even radial power distribution can be achieved. An approach to reduce the power peaking factor is to use enrichment zoning, which would improve coolant flow homogeneity. Several alternative VTR core configurations are considered with two enrichment zones (15 wt% Pu and 20 wt% Pu). These alternative configurations require more assemblies to maintain reactivity than the reference VTR core, which leads to failure to achieve the design criterion for experimental fast flux with the target core power. Configurations using 20 wt% Pu with different fuel assembly designs having smaller and larger fuel volume fractions are also analyzed. The case having a larger fuel volume fraction reduces the number of fuel assemblies required for criticality, which keeps the experimental flux higher. Configurations with volume fraction zoning can slightly decrease the peaking factor while maintaining the desired fast flux, although some thermal hydraulic limits may not be satisfied. Volume fraction zoning configurations may offer benefits, but determining the feasibility of these configurations requires further thermal hydraulic design and analysis work beyond the scope of the present work.
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Heidet, F., and J. Roglans-Ribas. "CORE DESIGN ACTIVITIES OF THE VERSATILE TEST REACTOR – CONCEPTUAL PHASE." EPJ Web of Conferences 247 (2021): 01010. http://dx.doi.org/10.1051/epjconf/202124701010.

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The Versatile Test Reactor (VTR) is a new fast spectrum test reactor being developed in the United States under the direction of the US Department of Energy, Office of Nuclear Energy. The VTR mission is to enable accelerated testing of advanced reactor fuels and materials required for advanced reactor technologies. This includes neutron irradiation capabilities which would support alternate coolants including molten salt, lead/lead-bismuth eutectic mixture, gas, and sodium. The VTR aims at addressing most of the needs of the various stakeholders, which is primarily composed of advanced reactor technologists, developers and vendors, as well as a number of others interested parties. Design activities are underway targeting a first criticality date by 2026, with General Electric recently joining the project to contribute to the VTR plant design. Current efforts are focused on all aspects of the VTR design, with the core design being at the center of the initial steps. The VTR is currently proposed as a 300 MWth sodium-cooled fast reactor able to reach peak fast flux levels in excess of 4.0x1015 n/cm2-s (and total flux level of about 6.0x1015 n/cm2-s). In this configuration, it is using ternary metallic fuel with reactor-grade plutonium and 5% low-enriched uranium.
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Kouhia, Virpi, Heikki Purhonen, Vesa Riikonen, Markku Puustinen, Riitta Kyrki-Rajamäki, and Juhani Vihavainen. "PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications." Science and Technology of Nuclear Installations 2012 (2012): 1–8. http://dx.doi.org/10.1155/2012/548513.

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This paper describes construction and experimental research activities with two test facilities, PACTEL and PWR PACTEL. The PACTEL facility, comprising of reactor pressure vessel parts, three loops with horizontal steam generators, a pressurizer, and emergency core cooling systems, was designed to model the thermal-hydraulic behaviour of VVER-440-type reactors. The facility has been utilized in miscellaneous applications and experiments, for example, in the OECD International Standard Problem ISP-33. PACTEL has been upgraded and modified on a case-by-case basis. The latest facility configuration, the PWR PACTEL facility, was constructed for research activities associated with the EPR-type reactor. A significant design basis is to utilize certain parts of PACTEL, and at the same time, to focus on a proper construction of two new loops and vertical steam generators with an extensive instrumentation. The PWR PACTEL benchmark exercise was launched in 2010 with a small break loss-of-coolant accident test as the chosen transient. Both facilities, PACTEL and PWR PACTEL, are maintained fully operational side by side.
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Choi, Hangbok, Robert W. Schleicher, Kirill Shapovalov, Chris Ellis, and John Bolin. "Feasibility study of a gas cartridge loop for the versatile test reactor." Nuclear Engineering and Design 377 (June 2021): 111111. http://dx.doi.org/10.1016/j.nucengdes.2021.111111.

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Rivas, Andy, Nicolas P. Martin, Samuel E. Bays, Giuseppe Palmiotti, Zhiwen Xu, and Jason Hou. "Nuclear data uncertainty propagation applied to the versatile test reactor conceptual design." Nuclear Engineering and Design 392 (June 2022): 111744. http://dx.doi.org/10.1016/j.nucengdes.2022.111744.

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Choi, Hangbok, Long V. Nguyen, Mohammad Alavi, Jonathan Lowe, Albert James, John Bolin, Chun Fu, and Chris Ellis. "Conceptual design of gas cartridge loop components for the Versatile Test Reactor." Nuclear Engineering and Design 389 (April 2022): 111696. http://dx.doi.org/10.1016/j.nucengdes.2022.111696.

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Martin, Nicolas, Ryan Stewart, and Sam Bays. "A multiphysics model of the versatile test reactor based on the MOOSE framework." Annals of Nuclear Energy 172 (July 2022): 109066. http://dx.doi.org/10.1016/j.anucene.2022.109066.

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Simpson, Michael. "Review of Redox Potential Control Options for Molten Salt Reactors." ECS Meeting Abstracts MA2022-02, no. 12 (October 9, 2022): 753. http://dx.doi.org/10.1149/ma2022-0212753mtgabs.

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Redox potential control is a fundamental requirement to minimize corrosion of metals in neutron irradiated molten salts, including fission reactor fuel, fission reactor coolant, and fusion reactor blanket. In this presentation, the focus will be placed upon metallic redox buffers—including beryllium, zirconium, and lithium. The study of beryllium for this function spans several decades and includes use in the Molten Salt Reactor Experiment (MSRE) in addition to proposed use in a fusion blanket. A fascinating aspect of this subject is the phase behavior of the metallic redox buffer. Evidence has been published that some of the metals—including beryllium and lithium actually dissolve into their host salts in the zero oxidation state. This provides the capability for a fast, homogenous reaction sans mass transfer limits. But redox buffering has also been reported from the reaction of molten salt with zirconium metal rods. It is proposed that these reactions can be categorized as either short range (homogenous) or long range (electrochemical cell) electronically mediated reactions. Data on metal solubility, electrochemical measurements, and corrosion control will be presented from the MSRE to very recent work in support of the Versatile Test Reactor. Open questions will be posed with the intention of encouraging the audience to propose new theories and experiments to test those theories.
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Goetz, K. C., S. M. Cetiner, and C. Celik. "Development of a Fast-Spectrum Self-Powered Neutron Detector for Molten Salt Experiments in the Versatile Test Reactor." EPJ Web of Conferences 253 (2021): 05006. http://dx.doi.org/10.1051/epjconf/202125305006.

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The self-powered neutron detector (SPND) is a widely used flux monitor in thermal nuclear reactors. Although this is a mature technology, the current state of the art is tuned for a thermal neutron spectrum, so many of the devices currently in use lack sensitivity to fast neutrons. Because current in SPNDs is produced through nuclear reactions with the neutron flux inside a reactor, sensitivity in SPNDs is determined by the neutron cross section of the neutron-sensitive portion of the detector, termed the emitter. This neutron cross section drops by orders of magnitude between thermal and fast neutron energies for many emitters in currently used SPNDs, with a corresponding drop in current from the detector. This paper discusses efforts to develop a fast-spectrum self-powered neutron detector (FS-SPND) that is sensitive to neutrons with energies ranging from 0.025 eV up to 1 MeV. An in-depth analysis of Evaluated Nuclear Data File (ENDF)/B-VII.1 neutron-capture cross sections was performed, and four new materials were identified that are suitable emitter candidates for use in measuring fast neutrons. All four materials are stable mid-shell nuclei in the region between doubly magic 132Sn and 208Pb. Each candidate was simulated with the Geant4 Monte Carlo simulation toolkit to optimize overall detector efficiency.
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Book chapters on the topic "Versatile Test Reactor"

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Woolstenhulme, Nicolas. "The Transient Reactor Test Facility (TREAT)." In Nuclear Reactors [Working Title]. IntechOpen, 2021. http://dx.doi.org/10.5772/intechopen.101275.

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Constructed in the late 1950s, the Transient Reactor Test facility (TREAT) provided numerous transient irradiations until operation was suspended in 1994. It was later refurbished, and resumed operations in 2017 to meet the data needs of a new era of nuclear fuel safety research. TREAT uses uranium oxide dispersed in graphite blocks to yield a core that affords strong negative temperature feedback. Automatically controlled, fast-acting transient control rods enable TREAT to safely perform extreme power maneuvers—ranging from prompt bursts to longer power ramps—to broadly support research on postulated accidents for many reactor types. TREAT’s experiment devices work in concert with the reactor to contain specimens, support in situ diagnostics, and provide desired test environments, thus yielding a uniquely versatile facility. This chapter summarizes TREAT’s design, history, current efforts, and future endeavors in the field of nuclear-heated fuel safety research.
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Rocha, Roberta Jachura. "Accelerated Aging Tests of HTPB-Based Propellants." In Energetic Materials Research, Applications, and New Technologies, 246–71. IGI Global, 2018. http://dx.doi.org/10.4018/978-1-5225-2903-3.ch012.

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In the late twentieth century, liquid and solid propulsion technologies have been integrated into hybrid engines currently apllied in propulsion launch vehicles and missiles. The reaction of polyol (HTPB) and diisocyanate (IPDI) provides the most versatile of the binders in the production of solid propellants due to its ability to withstand high loads combined with low cost and ease of processing. A propellant based on HTPB obtained in this study was submitted to natural and accelerated aging tests, seeking to evaluate the modifications of mechanical properties as tensile strength, elongation and hardness up to 360 days. The mechanism considered in the aging process is the increase of crosslink density by breaking the double bond contained in the HTPB molecule, which causes the instability of the propellant, increasing its handling risk. Samples of these propellants subjected to aging presented variations in their properties that match the values available in the literature.
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Conference papers on the topic "Versatile Test Reactor"

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Fanning, T., and T. Sumner. "Versatile Test Reactor Pump Coastown Assessment." In 2020 ANS Virtual Winter Meeting. AMNS, 2020. http://dx.doi.org/10.13182/t123-33119.

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Fanning, T., and T. Sumner. "Analysis of Versatile Test Reactor Pump Overcooling Transients." In 2020 ANS Virtual Winter Meeting. AMNS, 2020. http://dx.doi.org/10.13182/t123-33118.

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Heidet, F. "Shutdown Worth Requirements for the Versatile Test Reactor." In Tranactions - 2019 Winter Meeting. AMNS, 2019. http://dx.doi.org/10.13182/t30994.

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Andrus, J., M. Bucknor, D. Gerstner, and D. Grabaskas. "Safety Design Strategy for the Versatile Test Reactor." In Tranactions - 2019 Winter Meeting. AMNS, 2019. http://dx.doi.org/10.13182/t31325.

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Thomas, J., T. Fanning, and T. Sumner. "Safety Analysis of the Conceptual Versatile Test Reactor Design." In 2020 ANS Virtual Winter Meeting. AMNS, 2020. http://dx.doi.org/10.13182/t123-33116.

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Andrus, J., D. Gerstner, and T. Reiss. "Conceptual Safety Design Report for the Versatile Test Reactor." In Transactions - 2020 Virtual Conference. AMNS, 2020. http://dx.doi.org/10.13182/t122-31938.

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Heidet, F., and A. Kasam-Griffith. "Detailed Isotopic Fuel Composition for the Versatile Test Reactor." In Tranactions - 2019 Winter Meeting. AMNS, 2019. http://dx.doi.org/10.13182/t31083.

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Andrus, J., D. Gerstner, and T. Reiss. "Conceptual Safety Design Report for the Versatile Test Reactor." In Transactions - 2020 Virtual Conference. AMNS, 2020. http://dx.doi.org/10.13182/t31938.

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Ibarra, L., T. Sumner, and J. Thomas. "Initial Sensitivity Analyses for Versatile Test Reactor Transient Safety Performance." In 2020 ANS Virtual Winter Meeting. AMNS, 2020. http://dx.doi.org/10.13182/t123-33413.

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Henneke, D., D. Gerstner, J. Andrus, J. Li, M. Bucknor, M. Warner, and D. Grabaskas. "Structures, Systems, and Components Classification Criteria for the Versatile Test Reactor." In 2020 ANS Virtual Winter Meeting. AMNS, 2020. http://dx.doi.org/10.13182/t123-33385.

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Reports on the topic "Versatile Test Reactor"

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Youinou, G., P. Henslee, M. Salvatores, G. Palmiotti, R. Wigeland, D. Hill, C. Davis, S. Hayes, J. Bumgardner, and P. Finck. VCTR: A Versatile Coupled Test Reactor Concept. Office of Scientific and Technical Information (OSTI), May 2016. http://dx.doi.org/10.2172/1468965.

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Marschman, Steve, Patrick Hogan, Carl Baily, W. Zollinger, Randall Fielding, Denis Johnston, Blair Grover, et al. Fabricating Fuel for the Versatile Test Reactor. Office of Scientific and Technical Information (OSTI), October 2022. http://dx.doi.org/10.2172/1894683.

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Sen, Ramazan Sonat. Preliminary Options Assessment of Versatile Irradiation Test Reactor. Office of Scientific and Technical Information (OSTI), January 2017. http://dx.doi.org/10.2172/1371520.

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Bremer, Nathan, Darius Lisowski, and Mitch Farmer. Submersible Multistage Centrifugal Pump for Versatile Test Reactor Cartridge Test Loop. Office of Scientific and Technical Information (OSTI), April 2022. http://dx.doi.org/10.2172/1868933.

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Sumner, T., R. Thomas, T. Fanning, J. Thomas, and L. Ibarra. Safety Analysis for the Versatile Test Reactor Conceptual Design. Office of Scientific and Technical Information (OSTI), January 2022. http://dx.doi.org/10.2172/1874798.

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Weaver, Kevan. University Contributions to the Versatile Test Reactor (VTR) ? FY2022. Office of Scientific and Technical Information (OSTI), September 2022. http://dx.doi.org/10.2172/1892321.

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Stevens, Connie. FY2020 April Monthly Status Report for the Versatile Test Reactor. Office of Scientific and Technical Information (OSTI), May 2020. http://dx.doi.org/10.2172/1637595.

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Galloway, Jack. High Fidelity MCNP Modeling of the Versatile Test Reactor [Slides]. Office of Scientific and Technical Information (OSTI), July 2021. http://dx.doi.org/10.2172/1807811.

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Smith, M., G. Aliberti, and F. Heidet. Argonne Reactor Code Software Verification and Validation Plan for the Versatile Test Reactor. Office of Scientific and Technical Information (OSTI), December 2018. http://dx.doi.org/10.2172/1787804.

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Hirschhorn, Jake, Ryan Sweet, and Jeffrey Powers. Metallic Fuel Performance Code Requirements for the Versatile Test Reactor Project. Office of Scientific and Technical Information (OSTI), June 2021. http://dx.doi.org/10.2172/1798590.

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