scholarly journals Probability of pipe fracture in the primary coolant loop of a PWR plant. Volume 9. PRAISE computer code user's manual. Load Combination Program Project I final report

1981 ◽  
Author(s):  
E.Y. Lim
Keyword(s):  
Computer Code ◽  
Final Report ◽  
Primary Coolant ◽  
Load Combination ◽  
Coolant Loop

Buildup and Decay Analysis of Corrosion Products Activity in Primary Coolant Loop of AP-1000

2018 ◽  
Author(s):  
Fiaz Mahmood ◽  
Huasi Hu ◽  
Liangzhi Cao
Keyword(s):  
Radiation Exposure ◽  
Operating Conditions ◽  
Corrosion Products ◽  
Normal Operation ◽  
Reactor Operation ◽  
Primary Coolant ◽  
Reactor Control ◽  
Power Regulation ◽  
Coolant Loop ◽  
Control Regime

The broad half-life range of Activated Corrosion Products (ACPs) results in major radiation exposure throughout reactor operation and shutdown. The movement of unpredicted activity hot spots in coolant loop can bring about huge financial and dosimetric impacts. The PWR operating experience depicts that activity released during reactor operation and shutdown cannot be estimated through a simple correlation. This paper seeks to analyze buildup and decay behavior of ACPs in primary coolant loop of AP-1000 under normal operation, power regulation and shutdown modes. The application of a well-tested mathematical model is extended in an in-house developed code CPA-AP1000, to simulate the behavior of dominant Corrosion Products (CPs), by programing in MATLAB. The MCNP code is used as a subroutine of the program to model the reactor core and execute energy dependent neutron flux calculations. It is observed that short-lived CPs (56Mn, 24Na) build up rapidly under normal operation mode and decay quickly after the reactor is shutdown. The long-lived CPs (59Fe, 60Co, 99Mo) have exhibited slow buildup under normal operating conditions and likewise sluggish decay after the shutdown. To analyze activity response during reactor control regime, operating power level is promptly decreased and in response specific activity of CPs also followed decreasing trend. It is noticed that activity of CPs drops slowly during reactor control regime in comparison to emergency scram. The results are helpful in estimating radiation exposure caused by ACPs during accessibility of the equipment in coolant loop, under normal operation, power regulation and shutdown modes. Moreover, current analyses provide baseline data for further investigations on ACPs in AP-1000, being a new reactor design.

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