Research on Adsorption Performance of Type III Adsorber Used in Nuclear Power Plant

Author(s):  
Xin Xu ◽  
Lian-tao Yu

Based on operational principle and performance analysis of type III adsorber, a set of test platform for type III adsorber adsorption performance test is designed. After testing of the prototype and analyzing the test data, it is concluded that the prototype is qualified to be used in nuclear power plant and it fills the gap in China.

Author(s):  
Komandur S. Sunder Raj

The nuclear power industry is presently witnessing a renaissance. Global warming, greenhouse effects, concerns with use of as well as rising costs of fossil fuels, the desire to be weaned from foreign oil are all factors driving the need for increased reliance on nuclear power. Consequently, nuclear power plant owners are seeking to maximize the value of their generating assets through various means: improved operation, performance, capacity, availability, reliability and efficiency; license renewals, and; power uprates. Capacity factors are currently averaging well over 90% and, forced outage rates have decreased significantly, reflecting the maturation of operating and maintenance practices. In recognition of low fuel and relatively stable operating costs of their nuclear facilities, nuclear power plant owners have not only applied for license renewals, but have also upgraded the operation and, added electrical generating capacity to the operating units. Using a case study, this paper describes current efforts in maximizing the value of existing nuclear power plant generating assets. The focus of the paper is on maximizing benefits through improved operations and performance.


1989 ◽  
Vol 66 (6) ◽  
pp. 479-483
Author(s):  
F. M. Mitenkov ◽  
V. V. Vasil'eva ◽  
V. S. Vostokov ◽  
V. S. Gorbunov ◽  
N. P. Zaets ◽  
...  

2013 ◽  
Vol 475-476 ◽  
pp. 1721-1724 ◽  
Author(s):  
Dong Xiao Niu ◽  
Zong Yun Song

Fussy evaluation model will be used in this article to evaluate the operational safety performance of nuclear power plant. Through the combination of the existing three indicator system, the article builds a safety performance indicator system and fatherly establishes evaluation matrix of the importance level and performance level,then gets the weigh and confidence of every indicator. Finally, the evaluation results of the operational safety performance of nuclear power plant can be obtained after analyzing the confidence and evaluation matrix.


Author(s):  
Yinhui Lan ◽  
Cuizhu He ◽  
Yuangang Duan ◽  
Feihua Liu

As one of the most important equipment for reactivity control, Control Rod Drive Mechanism (CRDM), which is widely used in pressurized water reactor (PWR) nuclear power plant, has a series of important security functions. As an important component of the claw part in CRDM, the nonmagnetic shim materials have big influence on the movable latch lock plunger releasing current of CRDM. When cutting off the coil power, the nonmagnetic shim materials can block the magnetic circuit between the pole and latch lock plunger effectively and reduce the remanence suction force between magnetic pole and latch lock plunger, which can promote a quick latch lock plunger’s action and finish the step-jump and rod-release. In this paper, we introduce the background of non-conformance of the movable latch lock plunger releasing current of CRDM of PWR plant simply, and then we analyze the reasons of the non-conformance in detail, including a comprehensive analysis of various factors and a series of retest conclusions. Through specific analysis, the important role of nonmagnetic shims in CRDM and its big influence on movable latch lock plunger releasing current are proved. Based on research and test results, we show our optimized measures on the movable latch lock plunger releasing current in detail, from the perspective of technical specification for raw materials and improved processing technology during production. At last, one latch unit which occurred the movable latch lock plunger releasing current non-conformance and experienced a 1.7 million steps performance test is used in the following performance verification test. Being installed in this latch mechanism, our nonmagnetic shims finished an integral series of cold test, hot test and cold test after hot test. All of the test results meet our design requirements and all of the releasing current under cold condition is better than the results of 1.7 million steps performance test. Especially, the independently developed nonmagnetic shims improved the movable latch lock plunger releasing current significantly. In addition, other current results of hot test are equal to that of 1.7 million steps performance test. In conclusion, these optimized measures may not only provide data for solving the problem completely, but also provide reference for the manufacture of nonmagnetic shim materials in the future nuclear power plant.


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