1 There exists probability of fuel assembly damage in PWR during refueling period.

2 The load following reactor ( PWR ) is studied. A three - dimensional fuzzy control system of boron concentration is designed.

3 An economic analysis code used for PWR tuel cycle is develpped.

4 The natural circulation ability of PWR (pressurized water reactor) coolant system is one of inherent safeties of this kind NPP (nuclear power plant).

5 Control rods are used in a PWR typically to change the power level and also to shut down the reactor.

6 After having completed the model analysis of the pressurized water reactor (PWR) core barrel in an 1:10 model, the dynamic characteristics are obtained.

7 This paper studied the modeling and controlling of PWR and developed simulation software as well.

8 The analytical method is recommended for PWR design and operational analysis for its simplicity and conserv...

9 Presented is a model for the multi region and variable node PWR core.

10 The flow accelerated corrosion(FAC) to equipments by the high flux feed water occurs easily in steam and water systems of secondary loop of PWR .

11 It can be applied to the design and core reloading calculation of PWR.

12 In this thesis, the problem about the load following of Pressurized water reactor ( PWR ) is researched.

13 The drive is different from electric - magnetic drive for PWR or hydraulic drive for BWR.

14 The pressurizer is a very important device which controls the system pressure in pressurized water reactor ( PWR ).

15 In this paper, the method for transient characteristic calculation of PWR coolant system is studied and a model is developed.

16 An error that affects the integrity of system operation such as a detected address parity error or an invalid PWR _GOOD signal.

17 This one is the familiar one, inadvertent opening of a pressurised safety or relief valve in a PWR or a safety valve in a BWR.

18 The paper is to analyze the transient behavior of an experiment of Passive Residual Heat Removal (PRHR) system of advanced PWR secondary side by RELAP5.

19 The hybrid breeders can provide plenty of fissile material for PWR or FBR.

20 TPFAP is a transmisssion probabilily fuel assembly code package for burnup calculations on BWR and PWR.

21 This article introduces the construction type, thermal calculation, designreguirement, operation, maintenance and so on for steam pressurizer of PWR.

22 Counterflow condensation is one of the important core cooling mechanisms during a loss of coolant accident (LOCA) of PWR.

23 In order to carry out the test modeling LOCA of PWR, it is necessary to develop a device simulating pipe ruptures.

24 The results show that heaving has less effect upon the primary Loop's coolant flow rate and PWR output power in case of forced circulation but strongly influences natural circulation ability.

25 This model can be used to analyze thermal-hydraulic transient behaviour of inverted U-tube steam generators in PWR power plants.

26 A real time model of simulation of secondary system for PWR nuclear power unit is presented.

27 This paper described benchmark test noise signal analysis of PWR and gets some useful results.

28 The comparison of the computational results for reactor core of PWR and BWR are also presented.