scholarly journals CFD as a Tool for the Analysis of the Mechanical Integrity of Light Water Nuclear Reactors

10.5772/52691 ◽  
2013 ◽  
Author(s):  
Hernan Tinoco
Keyword(s):  
Nuclear Reactors ◽  
Light Water ◽  
Mechanical Integrity

Importance of self-shielding for improving sensitivity coefficients in light water nuclear reactors

2014 ◽  
Vol 63 ◽  
pp. 417-426 ◽  
Author(s):  
Basma Foad ◽  
Toshikazu Takeda
Keyword(s):  
Nuclear Reactors ◽  
Light Water ◽  
Sensitivity Coefficients

Behaviour of CS and I In Zirconia Based Fuel

1998 ◽  
Vol 540 ◽  
Author(s):  
C. Degueldre ◽  
M. Pouchon ◽  
M. Doebli ◽  
G. Ledergerber
Keyword(s):  
Incident Energy ◽  
Nuclear Reactors ◽  
Fission Products ◽  
Concentration Profiles ◽  
Reactor Safety ◽  
Inert Matrix Fuel ◽  
Light Water ◽  
Inert Matrix ◽  
Stepwise Heating ◽  
Implantation Depth

AbstractA zirconia based ceramic is foreseen as an inert matrix fuel for burning excess plutonium in light water nuclear reactors. For reactor safety reasons the behaviour of volatile fission products such as cesium and iodine must be studied since a retention of fission products is favourable for licensing the studied inert matrix fuel. In this study, implantation of Cs and I was performed into polycrystalline (Zr0.85, Y0.15)O1.925 samples. The implantation depth was selected on the basis of the ability to observe by Rutherford backscattering spectroscopy (RBS) the behaviour of Cs and I after treatment. With a 1 MeV incident energy, the ions are implanted at a depth of 200 nm as predicted by TRIM. After implantations full quantification of I and Cs concentration profiles was performed by RBS. The implantation profiles are measured as a function of sample temperature during stepwise heating programs. It is interesting to observe retention of Cs and I at relatively high temperature (e.g. for 2 h, below 900 K for Cs and below 1400 K for I). This behaviour is likely to be due to the size and interactions of these species in the zirconia solid solution.

Modeling of Complex Wear Behavior Associated with Grid-to-Rod Fretting in Light Water Nuclear Reactors

JOM ◽  
2016 ◽  
Vol 68 (11) ◽  
pp. 2938-2943 ◽  
Author(s):  
P. J. Blau ◽  
J. Qu ◽  
R. Lu
Keyword(s):  
Nuclear Reactors ◽  
Wear Behavior ◽  
Light Water

Economic viability of light water small modular nuclear reactors: General methodology and vendor data

2019 ◽  
Vol 103 ◽  
pp. 248-258 ◽  
Author(s):  
Geoffrey A. Black ◽  
Fatih Aydogan ◽  
Cassandra L. Koerner
Keyword(s):  
Nuclear Reactors ◽  
Economic Viability ◽  
Light Water ◽  
General Methodology

Development of a Predictive Wear Model for Grid-to-Rod Fretting in Light Water Nuclear Reactors

2013 ◽  
pp. 139-158 ◽  
Author(s):  
Peter J. Blau ◽  
Areg V. Hayrapetian ◽  
Michael J. Demkowicz
Keyword(s):  
Nuclear Reactors ◽  
Wear Model ◽  
Light Water

Understanding the Atomic-Level Chemistry and Structure of Oxide Deposits on Fuel Rods in Light Water Nuclear Reactors Using First Principles Methods

JOM ◽  
2016 ◽  
Vol 68 (11) ◽  
pp. 2912-2921 ◽  
Author(s):  
Zs. Rak ◽  
C. J. O’Brien ◽  
D. W. Brenner ◽  
D. A. Andersson ◽  
C. R. Stanek
Keyword(s):  
First Principles ◽  
Nuclear Reactors ◽  
Atomic Level ◽  
Fuel Rods ◽  
Light Water

Organic Iodide Formation During Severe Accidents in Light Water Nuclear Reactors

1987 ◽  
Vol 78 (1) ◽  
pp. 34-42 ◽  
Author(s):  
Edward C. Beahm ◽  
Yun-Ming Wang ◽  
Simon J. Wisbey ◽  
William E. Shockley
Keyword(s):  
Nuclear Reactors ◽  
Light Water ◽  
Severe Accidents

Modeling of Spacer Influence on Post-Dryout Heat Transfer in Heated Channels

2006 ◽  
Author(s):  
Henryk Anglart
Keyword(s):  
Heat Transfer ◽  
Heat Transfer Enhancement ◽  
Phenomenological Model ◽  
Nuclear Reactors ◽  
Light Water Reactors ◽  
Transfer Enhancement ◽  
Light Water ◽  
Operational Conditions ◽  
Transfer Processes ◽  
Water Reactors

Post-dryout heat transfer plays an important role in safe and economical operations of Light Water Reactors (LWR). This type of heat transfer is avoided under normal operational conditions of nuclear reactors; however, it may occur in transient or accidential situations. To estimate the risk of clad damages due to increase of temperature associated with the occurrence of post-dryout, it is necessary to properly model heat transfer processes under such conditions. The influence of various parameters on heat transfer downstream of spacer has been investigated. It is concluded that heat transfer enhancement due to spacers is largely under-predicted for flows with relatively low quality. For such flows the effect of droplets impinging heated walls is significant and must properly be taken into account. The phenomenological model presented in this paper shows a superior accuracy over correlations and presents a potential to capture the phenomenon of rewetting that occurs downstream of spacers.

A review on hydrogen generation, explosion, and mitigation during severe accidents in light water nuclear reactors

2018 ◽  
Vol 43 (4) ◽  
pp. 1939-1965 ◽  
Author(s):  
R. Gharari ◽  
H. Kazeminejad ◽  
N. Mataji Kojouri ◽  
A. Hedayat
Keyword(s):  
Hydrogen Generation ◽  
Nuclear Reactors ◽  
Light Water ◽  
Severe Accidents
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