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This publication investigates the process of improving an existing liquid cooled battery module in terms of lightweight design and cooling capabilities for production processes suitable for series production by using a holistic approach. It starts by identifying components with too high efforts using a method called Extended Target Weighing Approach (ETWA) and continues using complementary CFD and thermal simulations to guide the conceptualization of new solutions methodically. While conceptualizing and designing the parts to improve on key aspects of the battery module, a new tool was developed to select the best combination of material, process and manufacturing for these components. For this particular battery module, using the ETWA, we identified the cell mount, the housing and the plethora of components responsible for the sealing functionality as too heavy. Due to this, simulations of the coolant flow and temperature distribution were performed to guide the design choices for the cell mount. The thermal and CFD simulations revealed that a reduction of the initial cell mount height is possible while keeping the maximum temperatures within reason. Housing concepts were developed considering design limitations due to the manufacturing processes recommended by the selection tool. The used tool chain enabled an objective and comprehensible decision-making to optimize the battery module considering lightweight design and cooling capabilities.

Affection of static pressure may cause some error when differential pressure transmitter be used. Based on the reactor coolant flow rate measurement arithmetic do not calculates affection of static pressure, analysis is performed on the TP1RCP59 procedure in the reactor coolant flow rate measurement, during the commissioning of Unit 1 of Fuqing Nuclear Power Plant. Together with site tests and test verification. It has been found that the calibration arithmetic of TP1RCP59 is right, but not perfect. Once the Sensor should be replaced ,better arithmetic is provided by this article. Meanwhile the differential pressure used to calculate the reactor coolant flow rate is not exact, which should be ameliorated.

The theoretical results of mathematical modelling of the operation of a porous compact heat exchanger with the results of experimental studies are checked. Methods of comparing the results are given. Satisfactory errors in the thermohydraulic characteristics were obtained.

This paper intends to elucidate challenges in some aspects of the hardware design of future generation computers. We use a system model, a stack of integrated circuit cards cooled by a dielectric coolant (FC77). A set of equations is developed to describe the relationships between the system throughput, the volume, the power consumption, and those concerning the details of internal organization such as signal and power line dimensions and coolant path width. The calculated values of throughput, volume, and power are projected on a state point in a graph of the figures-of-merit pair, the computational density, and the computational efficiency. By manipulating the empirical parameters imbedded in the model, the state point is steered to follow the evolutionary line that runs through the points corresponding to the existing supercomputers of several generations. Then, calculation is extended on state points for future prospective computers with target system throughputs. The results point to the needs for research and development effort on thermal management and materials development. As for thermal management of exa- and zeta-scale computers, we need to refocus heat transfer research. Coolant channels will have very large length-to-width ratios (several thousand), while the heat flux on the channel surface is quite low. Micro-fluidics to guarantee stable coolant flow in such long micro-channels will be of primary importance in place of the means to deal with high heat flux. We also need to develop novel materials for signal transmission lines and cooling, particularly in the development of zeta-scale computers.

This paper investigates heat transfer and flow of U-shaped cooling passage with ribs in gas turbine blade by numerical methods. The Reynolds number ranges from 10000 to 40000, and there are three cooling passages with aspect ratio of 0.5, 1, 2, then the study conducts comparative analysis for a variety of programs in case of rotating. The results show that, ribs improve cooling performance of U-shaped passage significantly while obviously increase coolant flow loss. Heat transfer capability of passage wall is proportional to Reynolds number, but overall flow loss remain basically unchanged. Rotation improve first passage heat transfer clearly by Coriolis force while there is little effect on second passage, and it does not affect overall flow loss of U-shaped cooling passage.

Complex thermal-hydraulic and severe accident phenomenon is selected during Severe Accident Management. Deterministic approach is considered while assessing the consequences by severe accident due to Loss of Coolant Accident (LOCA) in vertical nuclear fuel channel. Mitigatory or Severe Accident Management has been used to arrest the temperature of clad such that it remains fairly below its softening limit. Method for establishment of minimum coolant flow through a nuclear fuel channel subsequent to LOCA is discussed in the paper. Concept of rewetting provides dependable foundation to Accident Management and is convenient in achieving the transient thermal analysis of clad. The results of analysis were found in close agreement with authors own experimental data and the data available by various other researchers. One of the important objectives of Accident Management is to control the generation of even a small size opening in clad subsequent to LOCA. In-depth study of severe accident is made by considering the clad filled with fuel and clad alone separately. In addition the paper brings out the accident management aspects with selected literature survey on Severe Accident Management.

A crucial aspect of nuclear monitoring is the identification of the two-phase flow regimes that occur in heated pipes. A novel efficient, non-invasive, on-line artificial neural network approach to two-phase flow regime identification is put forward; the general regression architecture has been employed. Through the utilization of a single input expressing the mean intensity of each image, satisfactory identification of the flow regime of sequences of images from neutron radiography coolant flow videos is accomplished. The proposed approach is not only more computationally efficient than existing conventional signal processing techniques and computational intelligence methodologies, but also - at worst - comparable to them in terms of identification accuracy.

The flow velocity of liquid metal coolant can be determined through the measurements of temperature fluctuation recorded by a pair of temperature sensors placed certain distance apart along the flow. Traditionally, this was done using a cross-correlation algorithm to estimate the transit time of the coolant, and thus its velocity. This widely used cross-correlation algorithm, however, suffers from the ambiguity in reading of measurements. To alleviate this problem, the transfer function estimation approach was recently proposed which tends to give more accurate results. In this paper, we introduce a new algorithm that can further improve the accuracy in the transit time estimation using an adaptive inverse system model at a higher cost of computation. When real-time computation is a concern, we propose a second algorithm based on an adaptive filtering approach which makes a sound trade-off between accuracy and computation cost. This algorithm incurs less processing time than the first proposed algorithm with higher accuracy than the two aforementioned conventional algorithms.

In continuous casting of steel a number of parameters have to be set, such as the casting temperature, casting speed and coolant flows that critically affect the safety, quality and productivity of steel production. We have implemented an optimization tool consisting in an optimization algorithm and casting process simulator. The paper describes the process, the optimization task, and the proposed optimization approach, and shows illustrative results of its application on an industrial casting machine where spray coolant flows were optimized. In the comparative study, two variants of an evolutionary algorithm and the downhill simplex method were used, and they were all able to significantly improve the manual setting of coolant flows.

Thermal-structure calculation are performed and the results are used to predict the lifetime of a possible ITER EPP blanket. The calculations, performed with the aid of a finite element analysis code, use the first wall configuration and coolant flow parameters of the helium cooled martensitic steel, European blanket design proposed for DEMO, but assume loading conditions anticipated in the ITER EPP. The calculations and analysis of the results suggest that the zero-fatigue lifetime (creep damage only) for low coolant temperature (315.5 C) is 6.2 years, and for high coolant temperature (375.0 C) is 3.08 years.