Radiation Protection Experience in RA Heavy Water Research Reactor Important for Decommissioning

Author(s):  
Marko M. Ninkovic

The RA reactor has been in service since the end of 1959. The beginning of the eightieth using of the reactor was interrupted because of some irregular deposits on the fuel elements in the core. Since that time, for about 20 years, the reactor has not been in service and is now being prepared for decommissioning. There have been no serious accidents to the RA reactor during the operation period, but a few small accidents or incidents, which affected the reactor systems and higher exposure of personnel. These incidents were: contamination of the heavy water cooling system by 60Co; flooding of a few hundred liters of heavy water from the heavy water cooling system; the first and single case of fuel element failure in the reactor core. A specific accident called “phantom”; and finally, some irregular deposits on the fuel elements inside the reactor core that were registered. In this paper more detailed data is given on the above mentioned accidents or incidents, their consequences on the reactor systems and personnel and countermeasures taken for reducing danger radioactivity. According to the opinion of the author, these data and lessons learned would be very interesting in general, and especially, for radiological characterization, as one of the first steps in the process of reactor decommissioning.

Author(s):  
Shoji Takada ◽  
Shunki Yanagi ◽  
Kazuhiko Iigaki ◽  
Masanori Shinohara ◽  
Daisuke Tochio ◽  
...  

HTTR is a helium gas cooled graphite-moderated HTGR with the rated power 30 MWt and the maximum reactor outlet coolant temperature 950°C. The vessel cooling system (VCS), which is composed of thermal reflector plates, cooling panel composed of fins connected between adjacent water cooling tubes, removes decay heat from reactor core by heat transfer of thermal radiation, conduction and natural convection in case of loss of forced cooling (LOFC). The metallic supports are embedded in the biological shielding concrete to support the fins of VCS. To verify the inherent safety features of HTGR, the LOFC test is planned by using HTTR with the VCS inactive from an initial reactor power of 9 MWt under the condition of LOFC while the reactor shut-down system disabled. In this test, the temperature distribution in the biological shielding concrete is prospected locally higher around the support because of thermal conduction in the support. A 2-dimensional symmetrical model was improved to simulate the heat transfer to the concrete through the VCS support in addition to the heat transfer thermal radiation and natural convection. The model simulated the water cooling tubes setting horizontally at the same pitch with actual configuration. The numerical results were verified in comparison with the measured data acquired from the test, in which the RPV was heated up to around 110 °C without nuclear heating with the VCS inactive, to show that the temperature is locally high but kept sufficiently low around the support in the concrete due to sufficient thermal conductivity to the cold temperature region.


2011 ◽  
Vol 383-390 ◽  
pp. 4715-4720
Author(s):  
Yan Zhang ◽  
Yan Hua Shen ◽  
Wen Ming Zhang

In order to ensure the reliable and safe operation of the electric driving motor of the articulated dump truck, water cooling system is installed for each motor. For the best performance of the water cooling system, not only the heat transfer should be enhanced to maintain the motor in relatively low temperature, but also the pressure drop in the water cooling system should be reduced to save energy by reducing the power consumption of the pump. In this paper, the numerical simulation of the cooling progress is completed and the temperature and pressure field distribution are obtained. The multi-objective optimization model is established which involves the cooling system structure, temperature field distribution and pressure field distribution. To improve the computational efficiency, the surrogate model of the simulation about the cooling process is established based on the Response Surface Methodology (RSM). After the multi-objective optimization, the Pareto optimal set is obtained. The proper design point, which could make the average temperature and pressure drop of the cooling system relative desirable, is chosen from the Pareto optimal set.


2021 ◽  
pp. 911-919
Author(s):  
Shashikant S. Jadhav ◽  
Avinash K. Parkhe ◽  
Subhash V. Jadhav ◽  
Samadhan J. Shinde

2008 ◽  
Vol 58 (5) ◽  
pp. 1142-1146 ◽  
Author(s):  
M. S. Kim ◽  
K. T. Q. Hoa ◽  
K. S. Baik ◽  
S. C. Park ◽  
C. N. Seong

2019 ◽  
Vol 142 (2) ◽  
Author(s):  
Wenjun Qiu ◽  
Zhengrong Ouyang

Abstract This paper presents an optimal control method for the prediction of parallel centrifugal variable frequency pump performance in any conditions to maximize the total efficiency of the pump system, thereby minimizing energy consumption. First, a theoretical model of parallel water pumping set was established, after which the shaft power model was setup specifically for the off-rating conditions. By combining the typical polynomial fitting method of the efficiency and the shaft power model we brought up, a new optimized control method was proposed. Using this method, the complex optimization task was solved with the optimal control of the operating number selection and speed ratios for parallel variable speed pumps based on the decision-making. The proposed method was subsequently applied to the pumping set of the water-cooling system in High Magnetic Field Facility. The practical testing results of the proposed method showed its superiority over both the primitive and the previous optimal methods, by considerably lowering the power consumption and accurately calculating the performance parameters in any conditions. The method has universality and simplicity for online implementation, which provides a reference for the control methods of parallel centrifugal pumps in variable flow systems with a differential pressure control strategy.


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