A Reactor Water Level and Pressure Prediction Method Under Small Loss-of-Coolant-Accident Conditions in Boiling Water Reactors

1985 ◽  
Vol 71 (2) ◽  
pp. 402-410 ◽  
Author(s):  
Yukiharu Ohga ◽  
Kohyu Fukunishi
Keyword(s):  
Water Level ◽  
Prediction Method ◽  
Boiling Water ◽  
Boiling Water Reactors ◽  
Reactor Water ◽  
Small Loss ◽  
Loss Of Coolant Accident ◽  
Loss Of Coolant ◽  
Water Reactors ◽  
Accident Conditions

Closed Model for Calculation of Differential Pressure After a Loss of Coolant Accident in Boiling Water Reactors

2009 ◽  
Author(s):  
Alexander Kratzsch ◽  
Wolfgang Ka¨stner ◽  
Rainer Hampel
Keyword(s):  
Differential Pressure ◽  
Boiling Water ◽  
Boiling Water Reactors ◽  
Insulation Material ◽  
Closed Model ◽  
Loss Of Coolant Accident ◽  
Safety Research ◽  
Loss Of Coolant ◽  
Water Reactors ◽  
Residual Heat

The paper deals with the calculation of differential pressure on sieves after a loss of coolant accident (LOCA) in boiling water reactors. One of the main features in reactor safety research is the safe heat dissipation from the reactor core and the reactor containment of light-water reactors. In the case of loss of coolant accident the possibility of the entry of insulation material into the reactor containment and the building sump of the reactor containment and into the associated systems to the residual heat exhaust is a serious problem. This can lead to a handicap of the system functions. To ensure the residual heat exhaust it is necessary the emergency cooling systems to put in operation which transport the water from the sump to the condensation chamber and directly to the reactor pressure vessel. A high allocation of the sieves with fractionated insulation material, in the sump can lead to a blockage of the sieves, inadmissibly increase of differential pressure, build-up at the sieves and to malfunctioning pumps. Hence, the scaling and retention of fractionated insulation material in the building sump of the reactor containment must be estimated. This allows the potential plant status in case of incidents to be assessed. The differential pressure is the essential parameter for the assessment of allocation of the sieves.

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.

Features of a control blade degradation observed in situ during severe accident conditions in boiling water reactors

2019 ◽  
Vol 56 (5) ◽  
pp. 440-453 ◽  
Author(s):  
Anton Pshenichnikov ◽  
Saishun Yamazaki ◽  
David Bottomley ◽  
Yuji Nagae ◽  
Masaki Kurata
Keyword(s):  
Boiling Water ◽  
Severe Accident ◽  
Boiling Water Reactors ◽  
Water Reactors ◽  
Accident Conditions
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