A New Boiling Water Reactor Core Concept for a Next-Generation Light Water Reactor

1991 ◽  
Vol 96 (1) ◽  
pp. 11-19 ◽  
Author(s):  
Junichi Yamashita ◽  
Akira Nishimura ◽  
Takaaki Mochida ◽  
Osamu Yokomizo
Keyword(s):  
Reactor Core ◽  
Boiling Water ◽  
Light Water Reactor ◽  
Boiling Water Reactor ◽  
Next Generation ◽  
Core Concept ◽  
Light Water ◽  
Water Reactor

New high-performance light water reactor core concept with mixed cycle length operation

2017 ◽  
Vol 42 (1) ◽  
pp. 53-67
Author(s):  
Eun Jeong ◽  
Jiwon Choe ◽  
Peng Zhang ◽  
Ho Cheol Shin ◽  
Deokjung Lee
Keyword(s):  
Cycle Length ◽  
High Performance ◽  
Reactor Core ◽  
Light Water Reactor ◽  
Core Concept ◽  
Light Water ◽  
Water Reactor

Properties of Light Water Reactor Core Melts

1977 ◽  
Vol 32 (3) ◽  
pp. 239-246 ◽  
Author(s):  
S. Nazaré ◽  
G. Ondracek ◽  
B. Schulz
Keyword(s):  
Reactor Core ◽  
Light Water Reactor ◽  
Light Water ◽  
Water Reactor

Chemical Reactions between Light Water Reactor Core Melt and Concrete

1979 ◽  
Vol 46 (2) ◽  
pp. 255-262 ◽  
Author(s):  
Alfred Skokan ◽  
Helmut Holleck ◽  
Martin Peehs
Keyword(s):  
Chemical Reactions ◽  
Reactor Core ◽  
Light Water Reactor ◽  
Light Water ◽  
Water Reactor

Bounding Acoustic Load Development for Boiling Water Reactor Shroud and Shroud Supports

2020 ◽  
Author(s):  
Matthew Walter ◽  
Minghao Qin ◽  
Daniel Sommerville
Keyword(s):  
Pressure Vessel ◽  
Reactor Core ◽  
Reactor Pressure Vessel ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Water Reactor ◽  
Structural Evaluation ◽  
Loss Of Coolant Accident ◽  
Specific Analysis ◽  
Reactor Pressure

Abstract As part of the license basis of a nuclear boiling water reactor pressure vessel, a sudden loss of coolant accident (LOCA) event needs to be analyzed. One of the loads that results from this event is a sudden depressurization of the recirculation line. This leads to an acoustic wave that propagates through the reactor coolant and impacts several structures inside the reactor pressure vessel (RPV). The authors have previously published a PVP paper (PVP2015-45769) which provides a survey of LOCA acoustic loads on boiling water reactor core shrouds. Acoustic loads are required for structural evaluation of core shrouds; therefore, a defensible load is required. The previous research compiled plant-specific data that was available at the time. Since then, additional data has become available which will add to the robustness of the bounding load methodology that was developed. Investigations are also made regarding the shroud support to RPV weld, which was neglected from the previous study. This will allow a practitioner a convenient method to calculate bounding acoustic loads on all shroud and shroud support welds in the absence of a plant-specific analysis.

Neutronic analysis and validation of boiling water reactor core designed by MCNPX code

2015 ◽  
Vol 76 ◽  
pp. 461-468 ◽  
Author(s):  
Ahmed Abdelghafar Galahom ◽  
I.I. Bashter ◽  
Moustafa Aziz
Keyword(s):  
Reactor Core ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Water Reactor ◽  
Mcnpx Code

A Large-Scale Numerical Simulation on Bubbly and Liquid Film Flows in Narrow Fuel Channels

2005 ◽  
Author(s):  
K. Takase ◽  
H. Yoshida ◽  
Y. Ose ◽  
H. Akimoto
Keyword(s):  
Large Scale ◽  
Two Phase Flow ◽  
Reactor Core ◽  
Light Water Reactor ◽  
Phase Flow ◽  
Analysis Method ◽  
Two Phase ◽  
Light Water ◽  
Water Reactor ◽  
Fuel Bundle

In order to predict the water-vapor two-phase flow structure in a fuel bundle of an advanced light-water reactor, large-scale numerical simulations were carried out using a newly developed two-phase flow analysis method and a highly parallel-vector supercomputer. Conventional analysis methods such as subchannel codes need composition equations based on many experimental data. Therefore, it is difficult to obtain highly prediction accuracy on the thermal design of the advanced light-water reactor core if the experimental data are insufficient. Then, a new analysis method using the large-scale direct numerical simulation of water-vapor two-phase flow was proposed. The coalescence and fragmentation of small bubbles were investigated numerically and the bubbly flow dynamics in narrow fuel channels were clarified. Moreover, the liquid film flow inside a tight-lattice fuel bundle which is used to the advanced light-water reactor core was analyzed and the water and vapor distributions around fuel rods and a spacer were estimated quantitatively.

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