Thermal Hydraulic Analysis on the Water Lead Lithium Cooled Blanket for CFETR

A new type of Water Lead Lithium Cooled (WLLC) blanket that adopts the modular design scheme, water cooling the structure components, liquid PbLi as breeder and coolant, and SiC as the thermal insulator between PbLi and structures is under development as a candidate blanket concept for the Chinese Fusion Engineering Test Reactor (CFETR). Based on a poloidal-radial slice model, thermal hydraulic analysis is performed for this blanket to validate the feasibility of design goals. Results show that the present design can achieve the outlet temperature in the range of 600–700 °C, with all the material temperatures safely below the upper limits. A series of sensitivity analyses are also carried out. It indicates that the thermal conductivity (TC) of SiC would have a significant influence on the temperature field, streamlines and pressure drop; that is, lower TC of SiC can maintain the temperature of PbLi at a high level, and induce an increased number of vortices in the liquid PbLi flow as well as a larger pressure drop. On this basis, the joint effects of the TC of SiC and inlet velocity on the performance of blanket thermal hydraulics are analyzed, then the so-called “attainable region” is proposed. Finally, optimization design studies are carried out by decreasing the width of the front channel. Comparison results show that the present design is the most reasonable.

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Pressure Drop Analysis of a Pressure-Channel Type SuperCritical Water-Cooled Reactor

Volume 15: Safety, Reliability and Risk; Virtual Podium (Posters) ◽

10.1115/imece2013-67383 ◽

2013 ◽

Cited By ~ 1

Author(s):

A. Dragunov ◽

W. Peiman

Keyword(s):

Pressure Drop ◽

Supercritical Water ◽

Nuclear Reactor ◽

Hydraulic Analysis ◽

Pressure Drops ◽

One Dimensional ◽

Supercritical Water Cooled Reactor ◽

Thermal Hydraulic Analysis ◽

Pressure Channel ◽

Channel Type

Pressure drop calculation and temperature profiles associated with fuel and sheath are important aspects of a nuclear reactor design. The main objective of this paper is to determine the pressure drop in a fuel channel of a SuperCritical Water-cooled Reactor (SCWR) and to calculate the temperature profile of the sheath and the fuel bundles. One-dimensional steady-state thermal-hydraulic analysis was conducted. In this study, the pressure drops due to friction, acceleration, local losses, and gravity were calculated at supercritical conditions.

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Validation of the COTENP Code: A Steady-State Thermal-Hydraulic Analysis Code for Nuclear Reactors with Plate Type Fuel Assemblies

Science and Technology of Nuclear Installations ◽

10.1155/2018/9874196 ◽

2018 ◽

Vol 2018 ◽

pp. 1-17

Author(s):

Duvan A. Castellanos-Gonzalez ◽

João Manoel Losada Moreira ◽

José Rubens Maiorino ◽

Pedro Carajilescov

Keyword(s):

Steady State ◽

Pressure Drop ◽

Fuel Assembly ◽

Nuclear Reactors ◽

Nucleate Boiling ◽

Hydraulic Analysis ◽

Fuel Assemblies ◽

Thermal Hydraulic Analysis ◽

Type Fuel ◽

Plate Type

This article presents the validation of the Code for Thermal-hydraulic Evaluation of Nuclear Reactors with Plate Type Fuels (COTENP), a subchannel code which performs steady-state thermal-hydraulic analysis of nuclear reactors with plate type fuel assemblies operating with the coolant at low pressure levels. The code is suitable for design analysis of research, test, and multipurpose reactors. To solve the conservation equations for mass, momentum, and energy, we adopt the subchannel and control volume methods based on fuel assembly geometric data and thermal-hydraulic conditions. We consider the chain or cascade method in two steps to facilitate the analysis of whole core. In the first step, we divide the core into channels with dimensions equivalent to that of the fuel assembly and identify the assembly with largest enthalpy rise as the hot assembly. In the second step, we divide the hot fuel assembly into subchannels with size equivalent to one actual coolant channel and similarly identify the hot subchannel. The code utilizes the homogenous equilibrium model for two-phase flow treatment and the balanced drop pressure approach for the flow rate determination. The code results include detailed information such as core pressure drop, mass flow rate distribution, coolant, cladding and centerline fuel temperatures, coolant quality, local heat flux, and results regarding onset of nucleate boiling and departure of nucleate boiling. To validate the COTENP code, we considered experimental data from the Brazilian IEA-R1 research reactor and calculated data from the Chinese CARR multipurpose reactor. The mean relative discrepancies for the coolant distribution were below 5%, for the coolant velocity were 1.5%, and for the pressure drop were below 10.7%. The latter discrepancy can be partially justified due to lack of information to adequately model the IEA-R1 experiment and CARR reactor. The results show that the COTENP code is sufficiently accurate to perform steady-state thermal-hydraulic design analyses for reactors with plate type fuel assemblies.

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Thermal-Hydraulic Analysis of Heavy Oil Transportation in Heated Sandwich Pipelines

24th International Conference on Offshore Mechanics and Arctic Engineering: Volume 3 ◽

10.1115/omae2005-67109 ◽

2005 ◽

Author(s):

Jian Su ◽

Segen F. Estefen

Keyword(s):

Pressure Drop ◽

Heavy Oil ◽

Oil Production ◽

Power Input ◽

High Viscosity ◽

Electrical Heating ◽

Hydraulic Analysis ◽

Numerical Studies ◽

Oil Transportation ◽

Thermal Hydraulic Analysis

Heavy oil production in deepwater is a major challenge to pipeline technology due to high viscosity and associated high pressure drop. In this paper, we propose to apply active electrical heating in multilayered composite pipelines for heavy oil production in deepwater. A thermal-hydraulic analysis is carried out to evaluate the pressure drop reduction and power input requirement. We concluded by comparative numerical studies that the heated sandwich pipeline provides a significant pressure drop reduction and thus a boost of mass flow rate of the oil production for a given available pressure drop between the wellhead and the separator.

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Thermal-hydraulic analysis of flow in rib-roughened passages with application to gas-cooled nuclear reactors

Proceedings of the Sixth International Symposium On Turbulence, Heat and Mass Transfer ◽

10.1615/ichmt.2009.turbulheatmasstransf.910 ◽

2009 ◽

Cited By ~ 2

Author(s):

Amir Keshmiri ◽

Mark A. Cotton ◽

Yacine Addad ◽

Dominique R. Laurence

Keyword(s):

Nuclear Reactors ◽

Hydraulic Analysis ◽

Thermal Hydraulic Analysis ◽

Rib Roughened

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THERMAL HYDRAULIC ANALYSIS OF SPENT FUEL SUBASSEMBLY DURING TRANSPORTATION FROM FBTR TO REPROCESSING FACILITY

Equipment ◽

10.1615/ihtc13.p7.10 ◽

2006 ◽

Author(s):

D. Sujish ◽

C. Meikandamurthy ◽

T. R. Ellappan ◽

M. Rajan ◽

G. Vaidyanathan

Keyword(s):

Spent Fuel ◽

Hydraulic Analysis ◽

Thermal Hydraulic Analysis

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THERMAL-HYDRAULIC ANALYSIS CODE FOR PLATE-TYPE FUEL NUCLEAR REACTORS

10.26678/abcm.encit2016.cit2016-0142 ◽

2016 ◽

Author(s):

Duvan Castellanos ◽

PEDRO CARAJILESCOV ◽

José Rubens Maiorino

Keyword(s):

Nuclear Reactors ◽

Hydraulic Analysis ◽

Thermal Hydraulic Analysis ◽

Type Fuel ◽

Plate Type

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A Comparative Study on Fault Detection Methods for Gas Turbine Combustion Systems

Energies ◽

10.3390/en14020389 ◽

2021 ◽

Vol 14 (2) ◽

pp. 389

Author(s):

Jinfu Liu ◽

Zhenhua Long ◽

Mingliang Bai ◽

Linhai Zhu ◽

Daren Yu

Keyword(s):

Fault Detection ◽

Gas Turbine ◽

Gas Turbines ◽

Operating Conditions ◽

Detection Methods ◽

Distribution Model ◽

Outlet Temperature ◽

Combustion System ◽

Comparison Results ◽

Gas Turbine Combustion

As one of the core components of gas turbines, the combustion system operates in a high-temperature and high-pressure adverse environment, which makes it extremely prone to faults and catastrophic accidents. Therefore, it is necessary to monitor the combustion system to detect in a timely way whether its performance has deteriorated, to improve the safety and economy of gas turbine operation. However, the combustor outlet temperature is so high that conventional sensors cannot work in such a harsh environment for a long time. In practical application, temperature thermocouples distributed at the turbine outlet are used to monitor the exhaust gas temperature (EGT) to indirectly monitor the performance of the combustion system, but, the EGT is not only affected by faults but also influenced by many interference factors, such as ambient conditions, operating conditions, rotation and mixing of uneven hot gas, performance degradation of compressor, etc., which will reduce the sensitivity and reliability of fault detection. For this reason, many scholars have devoted themselves to the research of combustion system fault detection and proposed many excellent methods. However, few studies have compared these methods. This paper will introduce the main methods of combustion system fault detection and select current mainstream methods for analysis. And a circumferential temperature distribution model of gas turbine is established to simulate the EGT profile when a fault is coupled with interference factors, then use the simulation data to compare the detection results of selected methods. Besides, the comparison results are verified by the actual operation data of a gas turbine. Finally, through comparative research and mechanism analysis, the study points out a more suitable method for gas turbine combustion system fault detection and proposes possible development directions.

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