会议专题

Estimation of One-through Direct Thermodynamic Cycle Parameters for Supercritical Water Cooled Reactor

The most of nuclear power plant (NPP) designs with supercritical water cooled reactor (SCWR) consider the direct steam cy cle with a steam supplied from reactor to turbine and with intermediate steam overheating as a basic variant. The main advantage of such a scheme is a lack of steam generator. It is proposed to provide the maximum use of industrial equipment manufacture technology, as well as the implementation of turbines, reactor vessels, heat exchangers mastered in reactor building technique. With the purpose to achieve a situation when the maximum steam enthalpy difference is produced by live steam it was suggested to arrange steam overheater just after Intermediate Pressure Turbine (IPT) in thermal scheme of SCWR. However, the problem could arise to get increased moisture that is impermissible for turbine blades’ operation. It is of great interest to estimate parameters and steel intensity of basic equipment in different thermal schemes. During long time in fossil fuel power engineering, a system of regenerative heating of feed water included such elements as low pressure and high pressure heaters (LPH, HPH) located between condenser and boiler; deaerator; condensate and feed pumps (CP, FP). New problems arise when turbines with power more than 800 MW are put into operation. The vessel of deaerator is an object of increased danger, that is why it must be kept under steady watch during campaign, as well as maintenance expends are required. Authors have considered two variants of steam overheating localization. There are: (1) overheater is placed between High Pressure and Intermediate Pressure Turbines; 2) overheater is placed between Intermediate Pressure and Low Pressure Turbines. The overheater heat transfer surface was estimated; in the second scheme it is bigger than in the first scheme. But the increased wall thickness in the overheater vessel is needed. Also authors have performed calculations of thermodynamic parameters of 1600 MW supercritical water cooled reactor facility based on two turbines К-800-240-5 for the following schemes: (1) eight-stage system of feed water heating consisting of mixing heaters: four low pressure heaters, deaerator, three high pressure heaters arranged in two lines and (2) deaerator-free scheme with rearranged flows of water and steam. Results of the researches fulfilled allow defining further directions in optimization of element’s design and thermal scheme in whole.

Supercritical water reactor thermodynamic cycle deaerator

G.P.Bogoslovskaya V.M.Abdulkadyrov

State Scientific Centre of the Russian Federation – Institute for Physics and Power Engineering name State Scientific Centre of the Russian Federation –Institute for Physics and Power Engineering named

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

1102-1114

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)