scholarly journals Advanced Light Water Reactor utility requirements document. Part 1, Executive summary

1986 ◽  
Author(s):  
Author(s):  
Leonard I. Loflin

This paper describes the EPRI (Electric Power Research Institute) project to enable the incorporation of Fukushima Lessons Learned into new Advanced Light Water Reactor (ALWR) nuclear plant designs and projects. This includes large scale plants and Small Modular Reactors (SMR). EPRI, working with the bulk of the US nuclear industry, compiled the Utility Requirements Document (URD) for new passive and evolutionary ALWRs. The ∼3,400 pages of functional design and project requirements in the URD became one of the bases documents for the current AP1000, ESBWR and EPR designs. The URD was and is a declaration of requirements of Owners/Operators for any new nuclear plant they might purchase. The 2013 revision 12 of the URD incorporated specific design and project requirements that are directly linked to industry summary conclusions and recommendations concerning the Fukushima event. During 2013 and 2014, EPRI, with assistance from the Department of Energy (DOE), is developing the URD requirements for selected SMRs.


1994 ◽  
Vol 153 (1) ◽  
pp. 71-86 ◽  
Author(s):  
K. Shibata ◽  
T. Isozaki ◽  
S. Ueda ◽  
R. Kurihara ◽  
K. Onizawa ◽  
...  

Author(s):  
Mitch Hokazono ◽  
Clayton T. Smith

Integral light-water reactor designs propose the use of steam generators located within the reactor vessel. Steam generator tubes in these designs must withstand external pressure loadings to prevent buckling, which is affected by material strength, fabrication techniques, chemical environment and tube geometry. Experience with fired tube boilers has shown that buckling in boiler tubes is greatly alleviated by controlling ovality in bends when the tubes are fabricated. Light water reactor steam generator pressures will not cause a buckling problem in steam generators with reasonable fabrication limits on tube ovality and wall thinning. Utilizing existing Code rules, there is a significant design margin, even for the maximum differential pressure case. With reasonable bend design and fabrication limits the helical steam generator thermodynamic advantages can be realized without a buckling concern. This paper describes a theoretical methodology for determining allowable external pressure for steam generator tubes subject to tube ovality based on ASME Section III Code Case N-759-2 rules. A parametric study of the results of this methodology applied to an elliptical cross section with varying wall thicknesses, tube diameters, and ovality values is also presented.


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