Nuclide Composition Benchmark Data Set for Verifying Burnup Codes on Spent Light Water Reactor Fuels

2002 ◽  
Vol 137 (2) ◽  
pp. 111-126 ◽  
Author(s):  
Yoshinori Nakahara ◽  
Kenya Suyama ◽  
Jun Inagawa ◽  
Ryuji Nagaishi ◽  
Setsumi Kurosawa ◽  
...  
Keyword(s):  
Light Water Reactor ◽  
Data Set ◽  
Light Water ◽  
Water Reactor ◽  
Benchmark Data ◽  
Nuclide Composition

Results of reliability test program on light water reactor piping

1994 ◽  
Vol 153 (1) ◽  
pp. 71-86 ◽  
Author(s):  
K. Shibata ◽  
T. Isozaki ◽  
S. Ueda ◽  
R. Kurihara ◽  
K. Onizawa ◽  
...  
Keyword(s):  
Light Water Reactor ◽  
Reliability Test ◽  
Test Program ◽  
Light Water ◽  
Water Reactor

Parametric Study of External Pressure on Steam Generator Tube Bends

2012 ◽  
Author(s):  
Mitch Hokazono ◽  
Clayton T. Smith
Keyword(s):  
Steam Generator ◽  
Parametric Study ◽  
External Pressure ◽  
Light Water Reactor ◽  
Material Strength ◽  
Steam Generators ◽  
Elliptical Cross ◽  
Light Water ◽  
Water Reactor ◽  
Steam Generator Tubes

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.

Conservative Width of High-Burnup Structure in Light Water Reactor UO2Fuel as a Function of Pellet Average Burnup

2008 ◽  
Vol 164 (3) ◽  
pp. 337-347 ◽  
Author(s):  
Yang-Hyun Koo ◽  
Byung-Ho Lee ◽  
Jae-Yong Oh ◽  
Kun-Woo Song
Keyword(s):  
Light Water Reactor ◽  
Light Water ◽  
Water Reactor ◽  
High Burnup
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