Results 1 - 10 of 201
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[en] The Chinese Fusion Engineering Test Reactor (CFETR) Central Solenoid Model Coil is being fabricated by the Institute of Plasma Physics Chinese Academy of Sciences. The Model Coil is comprised of Nb3Sn and NbTi modules held together by a preload structure. It will operate at 4.5 K to produce a peak field of 12 T at 48 kA. In order to investigate the feasibility and integrity of the Model Coil design before its manufacturing, the mechanical performance has been evaluated for the room temperature preload, 4.5 K stand-by and 48 kA operating conditions. A 1/15 3D detailed model that consists of jackets, insulations, bladders, buffers and preload structure, is constructed and simulated using the coupled structural-thermal-electromagnetic solver of ANSYS. In contrary to a smeared winding pack model, our analysis with the detailed model can directly and precisely simulate the differential thermal contraction effect of the preload structure, jacket and insulations, as well as the electromagnetic load acting on the jacket. The detailed deformation and stress behaviors of the Model Coil are illustrated and discussed. The results indicate that the final design of the CFETR Central Solenoid Model Coil is reasonably conservative and satisfy the design criteria. (paper)
[en] Flow-induced plastic collapse of stacked fuel plate assemblies was first noted in experimental reactors such as the ORNL High Flux Reactor Assembly and the Engineering Test Reactor (ETR). The ETR assembly is a stack of 19 thin flat rectangular fuel plates separated by narrow channels through which a coolant flows to remove the heat generated by fission of the fuel within the plates. The uranium alloyed plates have been noted to buckle laterally and plastically collapse at the system design coolant flow rate of 10.7 m/s, thus restricting the coolant flow through adjacent channels. A methodology and criterion are developed for predicting the plastic collapse of ETR fuel plates. The criterion is compared to some experimental results and the Miller critical velocity theory. (orig./HP)
[en] This paper describes a control system recently designed for the Engineering Test Reactor (ETR) at INEL to provide transient experiment capability for this 175 MW thermal, light water, reactor. The heart of the control system is a Power Transient Controller (PTC), a triple-redundant computer-based unit capable of driving the reactor through preprogrammed power transients of arbitrary complexity. This is done in an automatic closed-loop manner by generating a reference power function and computing real-time drive signals to two shim rods in response to multiple reactor power measurements. PTC software is developed on a PDP-11/60 host computer at the ETR facility, and defines the demand function, control algorithms, signal conditioning routines, PTC reactor scram criteria and so forth. The software is then down loaded to the PTC over a serial line. Thus, conceivably, separate reactor experiments could be run within minutes by sequentially down loading preprogrammed software stored on the 11/60 disk
[en] The Chinese Fusion Engineering Test Reactor (CFETR) represents the next generation of full superconducting fusion reactors in China. Recently, CFETR was redesigned with a larger size and will be operated in two phases. To reduce the heat flux on the target plate, a snowflake (SF) divertor configuration is proposed. In this paper we show that by adding two dedicated poloidal field (PF) coils, the SF configuration can be achieved in both phases. The equilibria were calculated by TEQ code for a range of self-inductances l i3. The coil currents were calculated at some fiducial points in the flattop phase. The results indicate that the PF coil system has the ability to maintain a long flattop phase in 7.5 and 10 MA inductive scenarios for the single null divertor (SND) and SF divertor configurations. The properties of the SF configuration were also analyzed. The connection length and flux expansion of the SF divertor were both increased significantly over the SND. (paper)
[en] A comprehensive research facility project was approved in December 2018 with funding of 345 million EUR, to support the research and development of the China Fusion Engineering Test Reactor (CFETR). As part of this project, a full-size CFETR toroidal field (TF) coil will be designed, manufactured and tested by the Institute of Plasma Physics Chinese Academy of Sciences. Two options are being explored in parallel for the TF coil design, using either circle-in-square or rectangular cable-in-conduit conductors (CICCs). The rectangular CICC has been reported to have some merits for a DEMO TF coil, as reported in designs of the EU-DEMO and K-DEMO. First this paper presents the progress in the conceptual design of the CFETR TF coil with rectangular CICCs, according to the most recent reference single-null configuration and radial build of CFETR. Then, electromagnetic analyses are performed to give the magnetic field distributions, toroidal field ripple, in-plane and out-of-plane Lorentz loads. Finally, 3D global and 2D local mechanical analyses are conducted, and the detailed mechanical behavior of the TF coil is illustrated and discussed. Our analyses indicate that the present TF design is reasonable, considering the ITER criteria, and provides valuable insight into the mechanical behavior of the CFETR TF coil system. (paper)
[en] The Japanese high temperature gas reactor program is centered on the High Temperature Engineering Test Reactor (HTTR), which has a thermal power of 30 MW and 950 C maximum coolant outlet temperature. The HTTR achieved criticality in November 1998 and has undergone a series of rise-to-power tests (Fujikawa 2004). In December 2001, an outlet temperature of 850 C was achieved and in April 2004 a temperature of 950 C was achieved. As of July 2004, the reactor had operated for 224 effective full power days (EFPD). The planned core life cycle is 660 EFPD (Verfondern 2000). It is planned to couple a high temperature process heat application to the HTTR through its intermediate heat exchanger in the future.
[en] The Chinese Fusion Engineering Test Reactor (CFETR), a next-generation fully superconducting fusion reactor, is in the design stages. In this paper, we present three snowflake (SF) divertor configurations (SF+, exact SF, SF−), to demonstrate the possibility of attaining these SF configurations with two special additional poloidal-field (PF) coils set on the CFETR, where all PF coils are outside the TF coils. Starting from a single null divertor (SND), a sequence of desirable SF configurations can be realized whereby the PF-coil currents are below the maximal design limits. Compared to the SND, the potential properties of these SFDs, including low-poloidal-field area, flux expansion, connection length, are analyzed and presented in this paper. As the required currents in some PF coils are higher for a SFD than a SND, an operating space of coil currents for the SFD was calculated at a range of the internal inductance (li) and flux states. The result indicates that though the current in CS1 PF coil limits access to the lower li and flux state region, the PF coils system can provide ∼30 Wb for the flattop phase.
[en] In July, 1979, EG and G Idaho, Inc. was requested to evaluate the ETR Fuel Element Shipping Container for compliance with existing transport regulations, in order to ship GETR fuel elements from Vallecitos, California to the INEL. Technical report PR-T-79-011 (TR-466), ATR Fuel Element Shipping Container Safety Analysis, was used as a basis for this evaluation. The safety analysis contained in technical report PR-T-79-011 (TR-466) was performed utilizing the ATR, ETR, MTR, and SPERT shipping containers. The report determined the ETR Fuel Element Shipping Container does comply with the existing transport regulations for a Type A quantity, Fissile Class I shipping container. The ETR and GETR fuel elements are essentially identical in physical size, construction, and fissile material content, the analysis documented in this report has determined the shipment of GETR fuel elements in the ETR shipping container to be safe and pose no threat to the public health and safety