scholarly journals Occupational dose reduction at nuclear power plants: Annotated bibliography of selected readings in radiation protection and ALARA. Volume 7

1993 ◽  
Author(s):  
D.G. Kaurin ◽  
T.A. Khan ◽  
S.G. Sullivan ◽  
J.W. Baum
2018 ◽  
Vol 183 (4) ◽  
pp. 503-513 ◽  
Author(s):  
Tae Young Kong ◽  
Gamal Akabani ◽  
John W Poston

Abstract One of the most important issues in the nuclear power industry is the implementation of the 2007 Recommendations of the International Commission on Radiological Protection (ICRP) published in ICRP Publication 103. These recommendations include the implementation of the concept of dose constraints for occupationally exposed workers at nuclear power plants (NPPs). When considering these changes from a cost–benefit standpoint, the implementation of dose constraints is still highly controversial. This study analysed annual occupational dose distributions to determine whether a dose constraint is needed for occupationally exposed workers at the US NPPs. Results of the analysis showed that the use of dose constraints had no positive impact on radiation safety of workers at NPPs in the USA. In fact, it appears that the implementation of dose constraints will impose an unnecessary regulatory burden on licensees. Based on these results, implementation of dose constraints is not recommended.


Author(s):  
Claude Faidy

On December 2005, the French regulator issued a new regulation for French nuclear power plants, in particular for pressure equipment (PE). This regulation need first to agree with non-nuclear PE regulation and add to that some specific requirements, in particular radiation protection requirements. Different advantages are in these proposal, it’s more qualitative risk oriented and it’s an important link with non-nuclear industry. Only few components are nuclear specific. But, the general philosophy of the existing Codes (RCC-M, KTA or ASME) have to be improved. For foreign Codes, it’s plan to define the differences in the user specifications. In parallel to that, a new safety classification has been developed by French utility. The consequences is the need to cross all these specifications to define a minimum quality level for each components or systems. In the same time a new concept has been developed to replace the well known “Leak Before Break methodology” by the “Break Exclusion” methodology. This paper will summarize the key aspects of these different topics and regularly compare with ASME practices.


Atomic Energy ◽  
2008 ◽  
Vol 105 (2) ◽  
pp. 90-98
Author(s):  
A. P. Pyshko ◽  
A. Yu. Plotnikov ◽  
A. V. Son’ko

2011 ◽  
Vol 100 (1) ◽  
pp. 35-38 ◽  
Author(s):  
Michael R. Blevins ◽  
Ralph L. Andersen

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