Experiments in High-Temperature Helium Facility: E
A high-temperature helium test facility (HTHF) has
99 GENERAL AND MISCELLANEOUS↗
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Thermal hydraulic performance testing of printed circuit heat exchangers in a high-temperature helium test facility
Not Available
Mylavarapu, Sai K.↗
APS-TD Helium Cryogenic Facilities
Cryogenic System: • CMTF cryogenic system is supplied by a state of the art Superfluid Cryogenic Plant to supply 40K, 5K, and 2K helium up to 500 W. 2K operations achievable through cold or warm compression systems. Currently Supports: • Cryo Module Test Stand 1 (CMTS1) used to test 1.3 GHz & 3.9 GHz cryomodules for the LCLS-II project. • PIP-II Injection Test Stand (PIP-II IT) program to test the front end of the future PIP-II Linac.and production cryomodules
43 PARTICLE ACCELERATORS↗
Performance Characterization of the Production Facility Prototype Helium Flow System
The roots blower in use at ANL for in-beam experiments and also at LANL for flow tests was sized for 12 mm diameter disks and significantly less beam heating. Currently, the disks are 29 mm in diameter, with a 12 mm FWHM Gaussian beam spot at 42 MeV and 2.86 μA on each side of the target, 5.72 μA total. The target design itself is reported elsewhere. With the increased beam heating, the helium flow requirement increased so that a larger blower was need for a mass flow rate of 400 g/s at 2.76 MPa (400 psig). An Aerzen GM 12.4 blower was selected, and is currently being installed at the LANL facility for target and component flow testing. This report describes this blower/motor/pressure vessel package and the status of the facility preparations. Blower performance (mass flow rate as a function of loop pressure drop) was measured at 4 blower speeds. Results are reported below.
07 ISOTOPE AND RADIATION SOURCES↗
Design of experimental facility for helium gas component testing
Not Available
Balderrama Prieto, Silvino A. (ORCID:0000000339418↗
Performance tests of helium circulator under abnormal cooling conditions - 18523
Helium circulator is one of the key equipment of High-temperature Gas-cooled Reactor Pebble-bed Module (HTR-PM) and the unique rotating equipment of primary loop. It transports heat generated by fission reactions from reactor core to steam generator by forcing helium circulating in primary loop. As the study on the characteristics of helium circulator in HTGR was limited and the advanced designs integrated with many new technologies, a prototype of helium circulator was manufactured. It was supported by Active Magnetic Bearings (AMBs), and was assembled in a pressure vessel. The prototype was tested in Engineering Test Facility - Helium Circulator (ETF-HC), which is a full scale, rated flow rate and power, engineering test loop. Although performance tests under normal operation condition were successfully fulfilled, the complete features and performance still need further verification, especially for abnormal cooling conditions. Thus performance tests under abnormal cooling operation conditions were carried out. Tests such as temporary coolant loss of motor and AMBs cooler and abnormal high-temperature cooling water condition were fulfilled. All performance tests results showed that helium circulator met the entire requirement of HTR-PM plant under abnormal cooling conditions and validated its safety and reliability. (authors)
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Endurance test of helium circulator for HTR-PM - 18531
High-temperature Gas-cooled Reactor Pebble-bed Module (HTR-PM) will be built as the world's first pebble-bed type modular HTGR commercial demonstration plant according to Chinese National science and technology program. HTR-PM will be expected to begin generating electricity in the end of 2017 in Shidao bay of China. Helium circulator is one of critical component of HTR-PM, which circulates reactor coolant through the reactor core and steam generators. The helium circulator was designed to be a vertical layout and its rotor was supported by active magnet bearings (AMBs). The whole circulator including motor and cooler was sealed in a pressure vessel. Since it is a large mechanical and electrical equipment and the design is totally advanced integrated with many new technologies, experiment study of helium circulator would be significant for safe and reliable operation of HTR-PM plant in the future. For the lack of engineering experience of this equipment, it was necessary to manufacture a prototype for tests. Meanwhile, Engineering Test Facility- Helium Circulator. ETF-HC was built in Institute of Nuclear and New Energy Technology (INET) for the tests. The prototype is completely same as the real machine for the plant. After prototype fabrication, nitrogen test was firstly conducted in the factory by the manufacturer, designer and users. After successful factory test, the prototype was delivered to INET to be tested in ETF-HC. Although nitrogen simulation test had been completed successfully, helium endurance test has been continually carried out in ETF-HC for one and half years because of several sealing problems caused by helium. After solving all kinds of problem in the field, helium circulator run continuously 50 hours under rated condition. Furthermore, 50 service cycles test was conducted in ETF-HC. More than 500 operation hours was accumulated during endurance test. Throughout the final performance test, a conclusion can be made that the helium circulator performance met the design requirements and its feasibility, availability and reliability was verified. (authors)
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DEVELOPMENT AND DEMONSTRATION OF A SUPERCRITICAL HELIUM-COOLED CRYOGENIC VISCOUS COMPRESSOR PROTOTYPE FOR THE ITER VACUUM SYSTEM
As part of the vacuum system for the ITER fusion project, a cryogenic viscouscompressor (CVC) is being developed to collect hydrogenic exhaust gases from the toruscryopumps and compress them to a high enough pressure by regeneration for pumping tothe tritium reprocessing facility. Helium impurities that are a byproduct of the fusionreactions pass through the CVC and are pumped by conventional vacuum pumps andexhausted to the atmosphere. Before the development of a full-scale CVC, a representative,small-scale test prototype was designed, fabricated, and tested. With cooling provided bycold helium gas, hydrogen gas was introduced into the central column of the test prototypepump at flow rates between 0.001 g/s and 0.008 g/s. Based on the temperatures and flowrates of the cold helium gas, different percentages of hydrogen gas were frozen to the column surface wall as the hydrogen gas flow rate increased. Results from the measured temperatures and pressures will form a benchmark that will be used to judge future heattransfer enhancements to the prototype CVC and to develop a computational fluid dynamicmodel that will help develop design parameters for the full-scale CVC.
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Fabrication and Design Aspects of High-Temperature Compact Diffusion Bonded Heat Exchangers
The Very High Temperature Reactor (VHTR) using gas-cooled reactor technology is anticipated to be the reactor type for the Next Generation Nuclear Plant (NGNP). In this reactor concept with an indirect power cycle system, a high-temperature and high integrity Intermediate Heat Exchanger (IHX) with high effectiveness is required to efficiently transfer the core thermal output to a secondary fluid for electricity generation, hydrogen production, and/or industrial process heat applications. At present, there is no proven IHX concept for VHTRs. The current Technology Readiness Level (TRL) status issued by NGNP to all components associated with the IHX for reduced nominal reactor outlet temperatures of 750–800 degrees C is 3 on a 1–10 scale, with 10 indicating omplete technological maturity. Among the various potential IHX concepts available, diffusion bonded heat exchangers (henceforth called printed circuit heat exchangers, or PCHEs) appear promising for NGNP applications. The design and fabrication of this key component of NGNP with Alloy 617, a candidate high-temperature structural material for NGNP applications, are the primary focus of this paper. In the current study, diffusion bonding of Alloy 617 has been demonstrated, although the optimum diffusion bonding process parameters to engineer a quasi interface-free joint are yet to be determined. The PCHE fabrication related processes, i.e., photochemical etching and diffusion bonding are discussed for Alloy 617 plates. In addition, the authors’ experiences with these non-conventional machining and joining techniques are discussed. Two PCHEs are fabricated using Alloy 617 plates and are being experimentally investigated for their thermal-hydraulic performance in a High-Temperature Helium Facility (HTHF). The HTHF is primarily of Alloy 800H construction and is designed to facilitate experiments at temperatures and pressures up to 800 degrees C and 3 MPa, respectively. Furthermore, some preliminary microstructural and mechanical property characterization studies of representative diffusion bonded Alloy 617 specimens are presented. The characterization studies are restricted and less severe from an NGNP perspective but provide sufficient confidence to ensure safe operation of the heat exchangers in the HTHF. The test results are used to determine the design operating conditions for the PCHEs fabricated.
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Physical control oriented model of large scale refrigerators to synthesize advanced control schemes. Design, validation, and first control results
In this paper, a physical method to obtain control-oriented dynamical models of large scale cryogenic refrigerators is proposed, in order to synthesize model-based advanced control schemes. These schemes aim to replace classical user experience designed approaches usually based on many independent PI controllers. This is particularly useful in the case where cryoplants are submitted to large pulsed thermal loads, expected to take place in the cryogenic cooling systems of future fusion reactors such as the International Thermonuclear Experimental Reactor (ITER) or the Japan Torus-60 Super Advanced Fusion Experiment (JT-60SA). Advanced control schemes lead to a better perturbation immunity and rejection, to offer a safer utilization of cryoplants. The paper gives details on how basic components used in the field of large scale helium refrigeration (especially those present on the 400W @1.8K helium test facility at CEA-Grenoble) are modeled and assembled to obtain the complete dynamic description of controllable subsystems of the refrigerator (controllable subsystems are namely the Joule-Thompson Cycle, the Brayton Cycle, the Liquid Nitrogen Precooling Unit and the Warm Compression Station). The complete 400W @1.8K (in the 400W @4.4K configuration) helium test facility model is then validated against experimental data and the optimal control of both the Joule-Thompson valve and the turbine valve is proposed, to stabilize the plant under highly variable thermals loads. This work is partially supported through the European Fusion Development Agreement (EFDA) Goal Oriented Training Program, task agreement WP10-GOT-GIRO.
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Advanced Reactors-Intermediate Heat Exchanger (IHX) Coupling: Theoretical Modeling and Experimental Validation
The overall goal of the research project was to model the behavior of the advanced reactorintermediate heat exchange system and to develop advanced control techniques for off-normal conditions. The specific objectives defined for the project were: 1. To develop the steady-state thermal hydraulic design of the intermediate heat exchanger (IHX); 2. To develop mathematical models to describe the advanced nuclear reactor-IHX-chemical process/power generation coupling during normal and off-normal operations, and to simulate models using multiphysics software; 3. To develop control strategies using genetic algorithm or neural network techniques and couple these techniques with the multiphysics software; 4. To validate the models experimentally The project objectives were accomplished by defining and executing four different tasks corresponding to these specific objectives. The first task involved selection of IHX candidates and developing steady state designs for those. The second task involved modeling of the transient and offnormal operation of the reactor-IHX system. The subsequent task dealt with the development of control strategies and involved algorithm development and simulation. The last task involved experimental validation of the thermal hydraulic performances of the two prototype heat exchangers designed and fabricated for the project at steady state and transient conditions to simulate the coupling of the reactor- IHX-process plant system. The experimental work utilized the two test facilities at The Ohio State University (OSU) including one existing High-Temperature Helium Test Facility (HTHF) and the newly developed high-temperature molten salt facility.
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Facile time-of-flight methods for characterizing pulsed superfluid helium droplet beams
We present two facile time-of-flight (TOF) methods of detecting superfluid helium droplets and droplets with neutral dopants. Without an electron gun and with only a heated filament and pulsed electrodes, the electron impact ionization TOF mass spectrometer can resolve ionized helium clusters such as He{sub 2}{sup +} and He{sub 4}{sup +}, which are signatures of superfluid helium droplets. Without ionizing any helium atoms, multiphoton non-resonant laser ionization of CCl{sub 4} doped in superfluid helium droplets at 266 nm generates complex cluster ions of dopant fragments with helium atoms, including (He){sub n}C{sup +}, (He){sub n}Cl{sup +}, and (He){sub n}CCl{sup +}. Using both methods, we have characterized our cryogenic pulsed valve—the Even-Lavie valve. We have observed a primary pulse with larger helium droplets traveling at a slower speed and a rebound pulse with smaller droplets at a faster speed. In addition, the pickup efficiency of dopant is higher for the primary pulse when the nozzle temperature is higher than 13 K, and the total time duration of the doped droplet pulse is only on the order of 20 μs. These results stress the importance of fast and easy characterization of the droplet beam for sensitive measurements such as electron diffraction of doped droplets.
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Thermal-hydraulic performance of a high-temperature zigzag-channel printed circuit heat exchanger - 18563
Advanced nuclear reactors, such as high-temperature gas-cooled reactors (HTGRs) from the Generation IV nuclear systems, are designed with the capability of delivering high-pressure, high-temperature helium to power conversion units for electricity generation and industrial plants for process heat applications. The efficiency of the electricity generation and process heat applications of HTGRs is critically dependent upon an intermediate heat exchanger (IHX), which is a key component in transferring thermal energy from the primary coolant to a secondary coolant. Printed circuit heat exchangers (PCHEs) are promising to be employed in HTGR designs due to their capability for high-temperature, high-pressure applications and compactness. In the current study, a laboratory-scale zigzag-channel PCHE was fabricated and its heat transfer and pressure drop characteristics were investigated experimentally in a high-temperature helium test facility (HTHF). A commercial computational fluid dynamics (CFD) code, STARCCM+, was used to simulate the thermal-hydraulic performance of the fabricated PCHE with a simplified geometry model. Comparisons showed some differences between experimental data available for the zigzag-channel PCHE and the numerical results. Local thermal-hydraulic performance analyses indicated that fully-developed flow conditions and periodic changes were not observed, which could be attributed to the temperature variations along the flow channels, resulting in large fluid property variations. In addition, the effects of sharp-edged or rounded zigzag channel geometry were numerically evaluated. The use of rounded corners at each bend of the channels is recommended since this method can reduce the pressure drop on both the hot and cold sides of the heat exchanger while maintaining similar heat transfer capabilities. (authors)
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
A 31 T split-pair pulsed magnet for single crystal x-ray diffraction at low temperature
We have developed a pulsed magnet system with panoramic access for synchrotron x-ray diffraction in magnetic fields up to 31 T and at low temperature down to 1.5 K. The apparatus consists of a split-pair magnet, a liquid nitrogen bath to cool the pulsed coil, and a helium cryostat allowing sample temperatures from 1.5 up to 250 K. Using a 1.15 MJ mobile generator, magnetic field pulses of 60 ms length were generated in the magnet, with a rise time of 16.5 ms and a repetition rate of 2 pulses/h at 31 T. The setup was validated for single crystal diffraction on the ESRF beamline ID06.
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Model based multivariable controller for large scale compression stations. Design and experimental validation on the LHC 18KW cryorefrigerator
In this paper, a multivariable model-based non-linear controller for Warm Compression Stations (WCS) is proposed. The strategy is to replace all the PID loops controlling the WCS with an optimally designed model-based multivariable loop. This new strategy leads to high stability and fast disturbance rejection such as those induced by a turbine or a compressor stop, a key-aspect in the case of large scale cryogenic refrigeration. The proposed control scheme can be used to have precise control of every pressure in normal operation or to stabilize and control the cryoplant under high variation of thermal loads (such as a pulsed heat load expected to take place in future fusion reactors such as those expected in the cryogenic cooling systems of the International Thermonuclear Experimental Reactor ITER or the Japan Torus-60 Super Advanced fusion experiment JT-60SA). The paper details how to set the WCS model up to synthesize the Linear Quadratic Optimal feedback gain and how to use it. After preliminary tuning at CEA-Grenoble on the 400W@1.8K helium test facility, the controller has been implemented on a Schneider PLC and fully tested first on the CERN's real-time simulator. Then, it was experimentally validated on a real CERN cryoplant. The efficiency of the solution is experimentally assessed using a reasonable operating scenario of start and stop of compressors and cryogenic turbines. This work is partially supported through the European Fusion Development Agreement (EFDA) Goal Oriented Training Program, task agreement WP10-GOT-GIRO.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Spin polarized {sup 3}He: From basic research to medical applications
Polarization of {sup 3}He gas by means of optical pumping is well known since the early 1960s with first applications in fundamental physics. Some thirty years later it was discovered, that one can use hyperpolarized {sup 3}He as contrast agent for magnetic resonance imaging of the lung. The wide interest in this new method made it necessary to find ways of polarizing {sup 3}He in large quantities with high polarization degrees. A high performance polarizing facility has been developed at the University of Mainz, designed for centralized production of hyperpolarized {sup 3}He gas. We present the Mainz concept as well as some examples of numerous applications of spin polarized {sup 3}He in fundamental research and medical applications.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
Inductance studies for the Quench Protection system of the Mu2e TS solenoids
This is a preliminary study on the solenoids for the Mu2e experiment. An overview of the Mu2e solenoids is first provided. Then the two solenoid prototypes were tested in the Fermilab Central Helium Liquefying facility. My analysis is focused on measuring and modeling the inductance (self and mutual) of the magnets. This aspect is crucial for Quench Detection Systems and for the control parameters of the power supply driving the magnets. During the first part of my experience at Fermilab, I worked on mathematical mod- els for the magnets to understand their expected behavior. A geometric model based on the Neumann formula was developed and implemented for inductance calculations. This model estimates the inductance (self and mu- tual) of all the Mu2e solenoids. A finite element magnetic model for the two prototype magnets was developed to compare to the results of the geometric model. In the second part of my study I collected measurements on the real Transport Solenoid prototypes. T he solenoids were powered in different configurations in order to identify the circuit model and its parameters. These experiments were first carried on the warm magnets and then on the magnets at a cryo- genic temperature. This allows for a comparison between room temperature and superconducting state.
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗