scholarly journals FABRICATION COSTS FOR PLUTONIUM FUEL ELEMENTS. PART E. THE VARIATION IN FABRICATION COST WITH SOME FUEL DESIGN PARAMETERS.

1967 ◽  
Author(s):  
C.H. Bloomster
Keyword(s):  
Design Parameters ◽  
Fabrication Cost ◽  
Fuel Design ◽  
Plutonium Fuel ◽  
Fuel Elements ◽  
Fabrication Costs

Parametric Study on the Fluid Elastic Instability Factor of the Fuel Rod for a PWR Plant

2010 ◽  
Author(s):  
Hyeong Koo Kim ◽  
Sang Youn Jeon ◽  
Kyou Seok Lee ◽  
Jeong Ha Kim ◽  
Sang Jong Lee
Keyword(s):  
Parametric Study ◽  
The Other ◽  
Design Parameters ◽  
Elastic Instability ◽  
Direct Relation ◽  
Spacer Grid ◽  
Fuel Rod ◽  
Flow Mixing ◽  
Fuel Design ◽  
Instability Factor

The main objective of this study is to estimate the effects of some considerable fuel design parameters on the fluid elastic instability behavior of the fuel rod. For the estimation, 6 fuel design parameters which seem to have direct relation with fluid elastic instability behavior of the fuel rod have been selected and examined using the PLUS7 fuel rod for OPR1000 PWR plants in Korea. Those are fuel rod creep-down, spacer grid stiffness, spacer grid spring relaxation, inactive spacer grid spring, intermediate flow mixing grid effect and fuel rod damping. As a result, the fluid elastic instability factors are insensitive with spacer grid stiffness, relaxation and intermediate flow mixing grid effect, but the other parameters need to be controlled and evaluated appropriately to maintain stability with proper margins.

Plutonium fuel and fuel elements for power reactors

1977 ◽  
Vol 43 (5) ◽  
pp. 1063-1068 ◽  
Author(s):  
I. S. Golovnin ◽  
A. S. Zaimovskii ◽  
T. S. Men'shikova ◽  
N. P. Agapova ◽  
Yu. K. Bibilashvili ◽  
...  
Keyword(s):  
Plutonium Fuel ◽  
Fuel Elements

scholarly journals Starting Point, Keys and Milestones of a Computer Code for the Simulation of the Behaviour of a Nuclear Fuel Rod

2011 ◽  
Vol 2011 ◽  
pp. 1-11 ◽  
Author(s):  
Armando C. Marino
Keyword(s):  
Nuclear Fuel ◽  
Extreme Case ◽  
Computer Code ◽  
National Commission ◽  
Fuel Rod ◽  
Safety Margins ◽  
Starting Point ◽  
Fuel Design ◽  
Advanced Fuel ◽  
Fuel Elements

The BaCo code (“Barra Combustible”) was developed at the Atomic Energy National Commission of Argentina (CNEA) for the simulation of nuclear fuel rod behaviour under irradiation conditions. We present in this paper a brief description of the code and the strategy used for the development, improvement, enhancement, and validation of a BaCo during the last 30 years. “Extreme case analysis”, parametric (or sensitivity), probabilistic (or statistic) analysis plus the analysis of the fuel performance (full core analysis) are the tools developed in the structure of BaCo in order to improve the understanding of the burnup extension in the Atucha I NPP, and the design of advanced fuel elements as CARA and CAREM. The 3D additional tools of BaCo can enhance the understanding of the fuel rod behaviour, the fuel design, and the safety margins. The modular structure of the BaCo code and its detailed coupling of thermo-mechanical and irradiation-induced phenomena make it a powerful tool for the prediction of the influence of material properties on the fuel rod performance and integrity.

scholarly journals PanDao fabrication cost impact analysis software tool for optical designers

2020 ◽  
Vol 238 ◽  
pp. 03014
Author(s):  
Marco Tinner ◽  
Irina Livshits ◽  
Oliver Faehnle
Keyword(s):  
Optical System ◽  
Impact Analysis ◽  
Software Tool ◽  
Design Stage ◽  
Design Parameters ◽  
Analysis Software ◽  
Fabrication Cost ◽  
Cost Impact

A new software tool, called PanDao, for optical system designers is presented enabling during the design stage a simulation of the optimum fabrication chain and technologies needed as well as a fabrication cost impact analysis of design parameters and tolerances.

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