A Modeling Study of Parameters ControIIing Local Concentration Processes in Pressurized Water Reactor Steam Generators

1994 ◽  
Vol 108 (2) ◽  
pp. 256-265 ◽  
Author(s):  
Peter J. Millett ◽  
James M. Fenton
Author(s):  
Xuhua Ye ◽  
Minjun Peng ◽  
Jiange Liu

An investigation on the thermal hydraulic characteristics of the passive residual heat removal system (PRHRS) which is used in an integral pressurized water reactor (INSURE-100) is presented in this paper. The main components of primary coolant system are enclosed in reactor vessel. Primary fluid flow circle is natural circulation. The PRHRS can remove the energy from the primary side as long as the residual heat exchanger (RHE) is submerged in the emergency cooldown tank (ECT). The parameter study is performed by considering the effects of an effective height between the steam generators and the RHE and a valve actuation time, which are useful for the design of the PRHRS. The mass flow in the PRHRS has been affected by the height difference between the steam generators and the RHE. The pressure peak of the primary side and PRHRS has been affected by the valve action time.


2000 ◽  
Vol 200 (1-2) ◽  
pp. 295-302 ◽  
Author(s):  
H Takamatsu ◽  
T Matsunaga ◽  
Robert M Wilson ◽  
T Kusakabe

Author(s):  
Qian Ma ◽  
Peiwei Sun

A new multi-purpose modular small pressurized water reactor with once-through steam generators is being designed in China. Its key parameters are different from traditional large pressurized water reactor. There are sixteen once-through steam generators divided into two groups inside of the pressure vessel. The four coolant pumps are located on the periphery of the pressure vessel. The coolant is heated by the core and transported the heat to the secondary loop by once-through steam generators. The superheated steam is generated, and its dynamics are different from those of U-tube steam generators. The relationship between the reactor and turbine is also complicated and needs to investigate. The control strategies of traditional large pressurized water reactor cannot be applied directly to the small reactor with once-through steam generators. Therefore, it is necessary to investigate suitable control strategies of the multi-purpose modular small reactor with once-through steam generators. Three control strategies are proposed and investigated in this study: turbine-leading, reactor-leading and feedwater-leading. With the reactor-leading strategy, the reactor power is adjusted by moving the control rod. The coolant temperature follows the change of the reactor power. Feedwater flow is applied to regulate the steam pressure. The steam flow rate follows the change of the feedwater flow rate to satisfy the demand power. With the turbine-leading strategy, the steam valve is adjusted which will influence the steam flow to satisfy the demand power. The feedwater-leading control strategy is adjusting the feed water flow rate corresponding to the demand power which has been measured. And reactor power and turbine load vary with feedwater flow rate. Input-output pairings of the control systems are determined based on the different strategies and proportion-integral-derivative (PID) controllers are tuned to meet the control requirements. To evaluate the performance of control strategies, power maneuvering events including a 10%FP (Full Power) step change and a ramp change with a rate of 5%FP/min are simulated. The processes of important control parameters varying with time are compared and evaluated to obtain the suitable one. Conclusions can be drawn from the simulation analyses of the control performance. The reactor-leading control strategy is best for the base-load operation. The turbine-leading control strategy is more suitable for load-following operation. The feedwater leading control strategy can be applied to load-following operation with smooth load adjustment.


1989 ◽  
Vol 111 (4) ◽  
pp. 371-377
Author(s):  
P. J. Langford

Tube vibration and wear potential in the U-bend region of pressurized water reactor (PWR) steam generators is reduced by enhanced design bases and fabrication procedures. Applicable vibration mechanisms are described and related to field experience to focus the development program which led to the enhancements. Technical bases were developed from flow-induced vibration tests and shaker tests in which the tube/antivibration bar (AVB) wear-producing forces and motions were characterized in terms of work rate. Fixtures to control weld shrinkage and instruments to measure tube/AVB fit-up were developed for fabrication. Assembly and application experience, including measurement of fabricated tube bundle/AVB fit-up, is summarized for several advanced steam generators. Implications for enhanced operating experience relative to conventional design configurations are noted.


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