Calculation method of steam exhaust system parameters of nuclear power plant
A discharge system and calculation method technology, applied in calculation, computer-aided design, design optimization/simulation, etc., can solve problems such as long development cycle, high cost, and difficulty
Inactive Publication Date: 2020-11-03
NO 719 RES INST CHINA SHIPBUILDING IND
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Problems solved by technology
The nuclear power plant simulation system covers reactor physics, main coolant system, secondary circuit system, power system, and control system. The development cycle is long, difficult, and costly, which affects the iterative design of the steam discharge system and related systems, thereby affecting nuclear power. The overall design progress of the device
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[0184] The present invention will be further described in detail below in conjunction with specific examples, but these examples should not be construed as limiting the present invention.
[0185] This example is based on the following assumptions: the temperature negative feedback effect of the moderator and fuel is not considered; the power is linearly related to the position of the control rod; the delay effect of the control rod is considered; the temperature of the main coolant is consistent with that of the adjacent structure; The average temperature of the main coolant is calculated by parameters; the number of steam generators is aggregated into one, and the aggregate parameters include flow rate, fluid and structural quality, and heat exchange area; the feedwater flow rate changes linearly with time after changing the load to reach the flow rate corresponding to the target load After changing the load, considering the discharge valve signal and action delay, the steam ...
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The invention relates to a calculation method of parameters of a vapor discharging system of a nuclear power device. The method includes the following steps of (1) conducting initialization; (2) calculating the vapor flow, the coefficient of a pressure relieving device, the opening degree of a discharging valve and the pressure drop of a pipeline; (3) calculating vapor flow, water feeding flow, acirculation ratio, an average heat exchange coefficient, reactor power, average temperature of a main cooling agent, recirculating water flow and circulating water flow at the current moment; (4) obtaining the vapor temperature at the current moment after calculation; (5) obtaining the saturated vapor pressure at the current moment; (6) obtaining an enthalpy value of a water outlet of a heat transmission area at the current moment n; (7) calculating the temperature of a vapor and water separation area at the current moment; (8) calculating the temperature of a drop area at the current moment;(9) obtaining an enthalpy value of an inlet of the heat transmission area at the current moment; (10) calculating a one-time side heat exchange coefficient of a vapor generator at the current moment;(11) calculating the temperature of the cooling agent at an outlet of a reactor at the current moment; (12) repeatedly executing the step 2, step 3... and step 17; (13) determining the upper limit value of the temperature of the cooling agent at the outlet of the reactor and the upper limit value of the vapor pressure. The calculation method of the parameters of the vapor discharging system of thenuclear power device is simple and easy to use.
Description
technical field [0001] The invention relates to steam discharge, in particular to a method for calculating parameters of a steam discharge system of a nuclear power plant. Background technique [0002] The steam discharge system is an important system to ensure the safe operation of nuclear power plants. After a sudden and large drop in the turbine load, the reactor power cannot change as quickly as the turbine generator load, and the function of the steam discharge system is to discharge the steam directly to the condenser in a controlled manner during this process, thereby providing the reactor with a The "artificial" load method is used to reduce the temperature transient and pressure transient range of the reactor main coolant in the nuclear steam supply system, and at the same time limit the maximum working pressure of the steam system to ensure the safe operation of the nuclear power plant. [0003] The parameter design of the steam discharge system should fully consi...
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IPC IPC(8): G06F30/20G06F119/08
CPCG06F30/20G06F2119/08
Inventor 刘现星罗小雨孙海军程堃张靖刘磊王珺唐征明李广围
Owner NO 719 RES INST CHINA SHIPBUILDING IND