Safety Assessment of SiC Cladding Oxidation under Loss-of-Coolant Accident Conditions in Light Water Reactors

2013 ◽  
Vol 183 (2) ◽  
pp. 210-227 ◽  
Author(s):  
Youho Lee ◽  
Thomas J. McKrell ◽  
Chao Yue ◽  
Mujid S. Kazimi
Keyword(s):  
Safety Assessment ◽  
Light Water Reactors ◽  
Light Water ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Water Reactors ◽  
Accident Conditions

Reflood Investigation of Model Fuel Assemblies of Light-Water Reactors for a Loss-of-Coolant Accident

Atomic Energy ◽  
2014 ◽  
Vol 116 (5) ◽  
pp. 343-349 ◽  
Author(s):  
S. S. Bazyuk ◽  
N. Ya. Parshin ◽  
E. B. Popov ◽  
Yu. A. Kuzma-Kichta
Keyword(s):  
Light Water Reactors ◽  
Light Water ◽  
Loss Of Coolant Accident ◽  
Model Fuel ◽  
Fuel Assemblies ◽  
Loss Of Coolant ◽  
Water Reactors

Iodine-steel reactions under severe accident conditions in light-water reactors

1996 ◽  
Vol 166 (3) ◽  
pp. 357-365 ◽  
Author(s):  
F. Funke ◽  
G.-U. Greger ◽  
S. Hellmann ◽  
A. Bleier ◽  
W. Morell
Keyword(s):  
Severe Accident ◽  
Light Water Reactors ◽  
Light Water ◽  
Water Reactors ◽  
Accident Conditions

Evaluation and Prediction of Critical Overhang Length Under Pipe Whip Accident

1986 ◽  
Vol 108 (2) ◽  
pp. 182-187
Author(s):  
T. Yano ◽  
N. Miyazaki ◽  
S. Miyazono
Keyword(s):  
Estimation Method ◽  
Plastic Collapse ◽  
Light Water Reactors ◽  
Pipe Length ◽  
Loss Of Coolant Accident ◽  
Overhang Length ◽  
Water Reactors ◽  
The Moment ◽  
Accident Conditions ◽  
Good Agreement

When the pipe length between break exit and restraint is long in the pipe whip accident, the pipe will undergo a plastic collapse as the moment increases. The length at which plastic collapse may occur is called the critical overhang length, (OH)cr. The experimental results of (OH)cr show good agreement with the prediction by a static simplified estimation method for (OH)cr although the pipe whipping is a dynamic phenomenon. The diagrams of (OH)cr are also described for a range of sizes of stainless steel pipe under the loss of coolant accident conditions of light water reactors.

scholarly journals Demonstration of Multi-Physics Evaluation of Fuel Rod Burst Probability With Burnup Extension Under LBLOCA Conditions

2020 ◽  
Author(s):  
Hongbin Zhang ◽  
Cole Blakely ◽  
Jianguo Yu
Keyword(s):  
Operating Time ◽  
Economic Benefits ◽  
Pressurized Water ◽  
Fuel Rod ◽  
Current Limit ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Water Reactors ◽  
Accident Conditions ◽  
Operating Cycles

Abstract Extending the fuel discharge burnup level, e.g., from the current limit of rod averaged discharge burnup limit of 62 GWD/MT to a proposed new limit of 75 GWD/MT, can provide significant economic benefits to the current fleet of operating light water reactors (LWRs). It allows for longer operating cycles and improved resource utilization. The major economic gain of longer operating cycles is attributable to the increased capacity factor resulting from decreased refueling time as a fraction of total operating time, as well as fewer assemblies to be discharged for a given amount of energy produced. The main licensing challenges for higher burnup fuel are to ensure fuel rod safety under design basis accident conditions, especially under large-break loss-of-coolant accident (LBLOCA) and reactivity insertion accident (RIA). In this work, two-year cycle core design for a typical 4-loop pressurized water reactor (PWR) is performed with enrichment increased up to 6% and burnup extended to 75 GWD/MT. The fuel rod burst potential evaluations under large-break loss-of-coolant accident (LBLOCA) conditions are subsequently performed using the multi-physics best estimate plus uncertainty analysis framework LOTUS (LOCA Toolkit for the U.S. LWRs) and the preliminary results are presented.

scholarly journals Normal and Accidental Scenarios Analyses with MELCOR 1.8.2 and MELCOR 2.1 for the DEMO Helium-Cooled Pebble Bed Blanket Concept

2015 ◽  
Vol 2015 ◽  
pp. 1-9
Author(s):  
Bruno Gonfiotti ◽  
Sandro Paci
Keyword(s):  
Severe Accident ◽  
Fusion Reactors ◽  
Transfer System ◽  
Light Water Reactors ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Pressure Peak ◽  
Water Reactors ◽  
Heat Transfer System ◽  
Do So

As for Light Water Reactors (LWRs), one of the most challenging accidents for the future DEMOnstration power plant is the Loss of Coolant Accident, which can trigger the pressurization of the confinement structures and components. Hence, careful analyses have to be executed to demonstrate that the confinement barriers are able to withstand the pressure peak within design limits and the residual cooling capabilities of the Primary Heat Transfer System are sufficient to remove the decay heat. To do so, severe accident codes, as MELCOR, can be employed. In detail, the MELCOR code has been developed to cope also with fusion reactors, but unfortunately, these fusion versions are based on the old 1.8.x source code. On the contrary, for LWRs, the newest 2.1.x versions are continuously updated. Thanks to the new features introduced in these latest 2.1.x versions, the main phenomena occurring in the helium-cooled blanket concepts of DEMO can be simulated in a basic manner. For this purpose, several analyses during normal and accidental DEMO conditions have been executed. The aim of these analyses is to compare the results obtained with MELCOR 1.8.2 and MELCOR 2.1 in order to highlight the differences among the results of the main thermal-hydraulic parameters.

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