The Experts below are selected from a list of 42678 Experts worldwide ranked by ideXlab platform
M. G. Bell - One of the best experts on this subject based on the ideXlab platform.
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The Tokamak Fusion Test Reactor
Magnetic Fusion Energy, 2016Co-Authors: M. G. BellAbstract:This chapter describes the design, operational regimes and results of the Tokamak Fusion Test Reactor (TFTR) which operated at the Princeton Plasma Physics Laboratory from 1982 to 1997. TFTR was a large tokamak (plasma current up to 3 MA) equipped with high power auxiliary heating by neutral beam injection (up to 40MW) and RF waves (up to 11 MW) and excellent plasma diagnostics. After developing and characterizing regimes of operation in deuterium plasmas with temperatures and density approaching those required for a fusion Reactor, TFTR conducted an extensive research program with deuterium-tritium plasmas between 1993 and 1997. In addition to investigating the confinement of fusion alpha particles and the effects of isotopic mass on confinement, many issues of relevance to the development of magnetic fusion Reactors were studied, such as RF heating and current drive in mixed-species plasmas, tritium handling and tritium retention in plasma-facing components.
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alpha particle driven toroidal alfven eigenmodes in the tokamak fusion Test Reactor
Physical Review Letters, 1997Co-Authors: R Nazikian, M. G. Bell, R. V. Budny, C. E. Bush, R E Bell, S H Batha, Z Chang, Yang Chen, C Z Cheng, D S DarrowAbstract:Alpha-particle-driven toroidal Alfven eigenmodes (TAEs) have been observed for the first time in deuterium-tritium (D-T) plasmas on the tokamak fusion Test Reactor (TFTR). These modes are observed 100–200 ms following the end of neutral beam injection in plasmas with reduced central magnetic shear and elevated central safety factor [q(0) > 1]. Mode activity is localized to the central region of the discharge ({lt}0.5) with magnetic fluctuation level B⊥/B∥ ~ 10⁻⁵ and toroidal mode numbers in the range n=2–4, consistent with theoretical calculations of α -TAE stability in TFTR.
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enhancement of tokamak fusion Test Reactor performance by lithium conditioning
Physics of Plasmas, 1996Co-Authors: D K Mansfield, J. D. Strachan, M. G. Bell, R. V. Budny, K W Hill, S D Scott, E S Marmar, J A Snipes, J L Terry, S H BathaAbstract:Wall conditioning in the Tokamak Fusion Test Reactor (TFTR) [K. M. McGuire et al., Phys. Plasmas 2, 2176 (1995)] by injection of lithium pellets into the plasma has resulted in large improvements in deuterium–tritium fusion power production (up to 10.7 MW), the Lawson triple product (up to 1021 m−3 s keV), and energy confinement time (up to 330 ms). The maximum plasma current for access to high‐performance supershots has been increased from 1.9 to 2.7 MA, leading to stable operation at plasma stored energy values greater than 5 MJ. The amount of lithium on the limiter and the effectiveness of its action are maximized through (1) distributing the Li over the limiter surface by injection of four Li pellets into Ohmic plasmas of increasing major and minor radius, and (2) injection of four Li pellets into the Ohmic phase of supershot discharges before neutral‐beam heating is begun.
S H Batha - One of the best experts on this subject based on the ideXlab platform.
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alpha particle driven toroidal alfven eigenmodes in the tokamak fusion Test Reactor
Physical Review Letters, 1997Co-Authors: R Nazikian, M. G. Bell, R. V. Budny, C. E. Bush, R E Bell, S H Batha, Z Chang, Yang Chen, C Z Cheng, D S DarrowAbstract:Alpha-particle-driven toroidal Alfven eigenmodes (TAEs) have been observed for the first time in deuterium-tritium (D-T) plasmas on the tokamak fusion Test Reactor (TFTR). These modes are observed 100–200 ms following the end of neutral beam injection in plasmas with reduced central magnetic shear and elevated central safety factor [q(0) > 1]. Mode activity is localized to the central region of the discharge ({lt}0.5) with magnetic fluctuation level B⊥/B∥ ~ 10⁻⁵ and toroidal mode numbers in the range n=2–4, consistent with theoretical calculations of α -TAE stability in TFTR.
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enhancement of tokamak fusion Test Reactor performance by lithium conditioning
Physics of Plasmas, 1996Co-Authors: D K Mansfield, J. D. Strachan, M. G. Bell, R. V. Budny, K W Hill, S D Scott, E S Marmar, J A Snipes, J L Terry, S H BathaAbstract:Wall conditioning in the Tokamak Fusion Test Reactor (TFTR) [K. M. McGuire et al., Phys. Plasmas 2, 2176 (1995)] by injection of lithium pellets into the plasma has resulted in large improvements in deuterium–tritium fusion power production (up to 10.7 MW), the Lawson triple product (up to 1021 m−3 s keV), and energy confinement time (up to 330 ms). The maximum plasma current for access to high‐performance supershots has been increased from 1.9 to 2.7 MA, leading to stable operation at plasma stored energy values greater than 5 MJ. The amount of lithium on the limiter and the effectiveness of its action are maximized through (1) distributing the Li over the limiter surface by injection of four Li pellets into Ohmic plasmas of increasing major and minor radius, and (2) injection of four Li pellets into the Ohmic phase of supershot discharges before neutral‐beam heating is begun.
Frances M. Marshall - One of the best experts on this subject based on the ideXlab platform.
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Advanced Test Reactor -- Testing Capabilities and Plans AND Advanced Test Reactor National Scientific User Facility -- Partnerships and Networks
2008Co-Authors: Frances M. MarshallAbstract:The Advanced Test Reactor (ATR), at the Idaho National Laboratory (INL), is one of the world’s premier Test Reactors for providing the capability for studying the effects of intense neutron and gamma radiation on Reactor materials and fuels. The physical configuration of the ATR, a 4-leaf clover shape, allows the Reactor to be operated at different power levels in the corner “lobes” to allow for different Testing conditions for multiple simultaneous experiments. The combination of high flux (maximum thermal neutron fluxes of 1E15 neutrons per square centimeter per second and maximum fast [E>1.0 MeV] neutron fluxes of 5E14 neutrons per square centimeter per second) and large Test volumes (up to 122 cm long and 12.7 cm diameter) provide unique Testing opportunities. For future research, some ATR modifications and enhancements are currently planned. In 2007 the US Department of Energy designated the ATR as a National Scientific User Facility (NSUF) to facilitate greater access to the ATR for material Testing research by a broader user community. This paper provides more details on some of the ATR capabilities, key design features, experiments, and plans for the NSUF.
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Advanced Test Reactor - A National Scientific User Facility
2008Co-Authors: Frances M. Marshall, Jeff B. Benson, Mary Catherine ThelenAbstract:The Advanced Test Reactor (ATR), at the Idaho National Laboratory (INL), is a large Test Reactor for providing the capability for studying the effects of intense neutron and gamma radiation on Reactor materials and fuels. The ATR is a pressurized, light-water, high flux Test Reactor with a maximum operating power of 250 MWth. The INL also has several hot cells and other laboratories in which irradiated material can be examined to study material irradiation effects. In 2007 the US Department of Energy (DOE) designated the ATR as a National Scientific User Facility (NSUF) to facilitate greater access to the ATR and the associated INL laboratories for material Testing research by a broader user community. This paper highlights the ATR NSUF research program and the associated educational initiatives.
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Advanced Test Reactor Capabilities and Future Irradiation Plans
2006Co-Authors: Frances M. MarshallAbstract:The Advanced Test Reactor (ATR), located at the Idaho National Laboratory (INL), is one of the most versatile operating research Reactors in the Untied States. The ATR has a long history of supporting Reactor fuel and material research for the US government and other Test sponsors. The INL is owned by the US Department of Energy (DOE) and currently operated by Battelle Energy Alliance (BEA). The ATR is the third generation of Test Reactors built at the Test Reactor Area, now named the Reactor Technology Complex (RTC), whose mission is to study the effects of intense neutron and gamma radiation on Reactor materials and fuels. The current experiments in the ATR are for a variety of customers - US DOE, foreign governments and private researchers, and commercial companies that need neutrons. The ATR has several unique features that enable the Reactor to perform diverse simultaneous Tests for multiple Test sponsors. The ATR has been operating since 1967, and is expected to continue operating for several more decades. The remainder of this paper discusses the ATR design features, Testing options, previous experiment programs, future plans for the ATR capabilities and experiments, and some introduction to the INL and DOE's expectations for nuclear research in the future.
J. L. Rempe - One of the best experts on this subject based on the ideXlab platform.
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In-Situ Creep Testing Capability for the Advanced Test Reactor
Nuclear Technology, 2012Co-Authors: Bong Goo Kim, J. L. Rempe, D. L. Knudson, Keith G. Condie, Bulent H. SencerAbstract:An instrumented creep Testing capability is being developed for specimens irradiated in Pressurized Water Reactor (PWR) coolant conditions at the Advanced Test Reactor (ATR). The Test rig has been developed such that samples will be subjected to stresses ranging from 92 to 350 MPa at temperatures between 290 and 370 °C up to at least 2 dpa (displacement per atom). The status of Idaho National Laboratory (INL) efforts to develop the Test rig in-situ creep Testing capability for the ATR is described. In addition to providing an overview of in-pile creep Test capabilities available at other Test Reactors, this paper reports efforts by INL to evaluate a prototype Test rig in an autoclave at INL’s High Temperature Test Laboratory (HTTL). Initial data from autoclave Tests with 304 stainless steel (304 SS) specimens are reported.
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Enhanced In-Pile Instrumentation at the Advanced Test Reactor
2011 2nd International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications, 2011Co-Authors: J. L. Rempe, D. L. Knudson, Keith G. Condie, Joshua Daw, Troy Unruh, Benjamin M. Chase, Joe Palmer, K. L. DavisAbstract:Many of the sensors deployed at materials and Test Reactors cannot withstand the high flux/high temperature Test conditions often requested by users at U.S. Test Reactors, such as the Advanced Test Reactor (ATR) at the Idaho National Laboratory. To address this issue, an instrumentation development effort was initiated as part of the ATR National Scientific User Facility in 2007 to support the development and deployment of enhanced in-pile sensors. This paper provides an update on this effort. Specifically, this paper identifies the types of sensors currently available to support in-pile irradiations and those sensors currently available to ATR users. Accomplishments from new sensor technology deployment efforts are highlighted by describing new temperature and thermal conductivity sensors now available to ATR users. Efforts to deploy enhanced in-pile sensors for detecting elongation and real-time flux detectors are also reported, and recently-initiated research to evaluate the viability of advanced technologies to provide enhanced accuracy for measuring key parameters during irradiation Testing are noted.
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Instrumentation to Enhance Advanced Test Reactor Irradiations
2009Co-Authors: J. L. Rempe, D. L. Knudson, Keith G. Condie, Joshua Daw, S. C. TaylorAbstract:The Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007 to support U.S. leadership in nuclear science and technology. By attracting new research users - universities, laboratories, and industry - the ATR will support basic and applied nuclear research and development, further advancing the nation's energy security needs. A key component of the ATR NSUF effort is to prove new in-pile instrumentation techniques that are capable of providing real-time measurements of key parameters during irradiation. To address this need, an assessment of instrumentation available and under-development at other Test Reactors has been completed. Based on this review, recommendations are made with respect to what instrumentation is needed at the ATR and a strategy has been developed for obtaining these sensors. Progress toward implementing this strategy is reported in this document. It is anticipated that this report will be updated on an annual basis.
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new sensors for the advanced Test Reactor national scientific user facility
International Conference on Advancements in Nuclear Instrumentation Measurement Methods and their Applications, 2009Co-Authors: J. L. Rempe, D. L. Knudson, Keith G. Condie, Joshua Daw, Heng Ban, Brandon S Fox, Gordon KohseAbstract:A key component of the Advanced Test Reactor (ATR) National Scientific User Facility (NSUF) effort is to develop and evaluate in-pile instrumentation capable of providing real-time measurements of key parameters during irradiation. This paper describes the strategy for identifying and prioritizing instrumentation needs and the program initiated to develop new or enhanced sensors to address these needs. Accomplishments from this program are illustrated by describing new sensors now available to users of the ATR NSUF with data from irradiation Tests using these sensors. In addition, progress is reported on current research efforts to provide users advanced methods for detecting temperature, fuel thermal conductivity, and changes in sample geometry.
Tatsuo Iyoku - One of the best experts on this subject based on the ideXlab platform.
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safety demonstration Tests using high temperature engineering Test Reactor
Nuclear Engineering and Design, 2004Co-Authors: Shigeaki Nakagawa, Kuniyoshi Takamatsu, Yukio Tachibana, Nariaki Sakaba, Tatsuo IyokuAbstract:Safety demonstration Tests using the high temperature engineering Test Reactor (HTTR) are conducted for demonstrating inherent safety features of high temperature gas-cooled Reactors (HTGRs) as well as for providing core and plant transient data for validation of HTGR safety analysis codes. The safety demonstration Tests are divided to the first phase and second phase Tests. In the first phase Tests, simulation Tests of anticipated operational occurrences and anticipated transients without scram (ATWS) are conducted. The second phase Tests will simulate accidents such as a depressurization accident (loss of coolant accident). The first phase Tests simulating reactivity insertion events and coolant flow reduction events started in FY 2002. The first phase safety demonstration Tests will continue until FY 2005 and the second phase Tests will be carried out from FY 2006.
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Seismic Response of the High-Temperature Engineering Test Reactor Core Bottom Structure
Nuclear Technology, 1992Co-Authors: Tatsuo Iyoku, Shusaku Shiozawa, Yoshiyuki Inagaki, Masatoshi Futakawa, Toshiyo MikiAbstract:This paper discusses the High-Temperature Engineering Test Reactor (HTTR) a 30-MW (thermal) helium gas-cooled rector that uses a prismatic block. The core bottom structure (CBS) of the HTTR consists of an arrangement of graphite components, and it supports the core elements within the Reactor vessel. vibration Tests are performed with two scale models to clarify the seismic response of the CBS. The vibration characteristics of the CBS are clarified quantitatively, and the structural integrity of the graphite components is confirmed.
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Seismic Study of High-Temperature Engineering Test Reactor Core Graphite Structures
Nuclear Technology, 1992Co-Authors: Tatsuo Iyoku, Shusaku Shiozawa, Yoshiyuki Inagaki, Isoharu NishiguchiAbstract:This paper discusses the High-Temperature Engineering Test Reactor (HTTR) a 30-MW (thermal) helium gas-cooled Reactor with a core composed of prismatic graphite blocks piled on core support structures. Safety analyses have been made for the seismic design of the HTTR core using a two-dimensional seismic analysis code called SONATINA-2V, which was developed by the Japan Atomic Energy Research Institute. To evaluate the validity of the SONATINA-2V code and confirm the structural integrity of the core graphite blocks, large-scale seismic Tests are conducted using a half-scale vertical section model and a full-scale seven-column model of the core graphite blocks and the core support structures. The Test results are in good agreement with the analytical ones, and the validity of the analysis code is confirmed. The structural integrity of the core graphite blocks is confirmed by both analytical and Test results.
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Seismic Study of High-Temperature Engineering Test Reactor Core Graphite Structures
Nuclear Technology, 1992Co-Authors: Tatsuo Iyoku, Shusaku Shiozawa, Yoshiyuki Inagaki, Isoharu NishiguchiAbstract:The High-Temperature Engineering Test Reactor (HTTR) is a 30-MW(thermal) helium gas-cooled Reactor with a core composed of prismatic graphite blocks piled on core support structures. Safety analyse...
