BWR Progression Problems

Chase Lawing; Scott Palmtag; Mehdi Asgari

doi:10.2172/1838995

BWR Progression Problems

Chase Lawing, Scott Palmtag, Mehdi Asgari

Power Reactor Modeling

Research output: Book/Report › Commissioned report

Abstract

Under the Consortium for the Advanced Simulation of Light Water Reactors (CASL) Program, the Virtual Environment for Reactor Applications (VERA) was developed with the primary focus to model pressurized water reactors (PWRs). Recently, a new project was started to extend the modeling capability in VERA to model boiling water reactors (BWRs). The new project is called “Modeling and Analysis of Exelon BWRs for Eigenvalue and Thermal Limits Predictability,” and it is led by Oak Ridge National Laboratory (ORNL) and Exelon with participation from Global Nuclear Fuel and three universities: North Carolina State University (NCSU), the University of Michigan, and the University of Illinois.

Original language	English
Place of Publication	United States
DOIs	https://doi.org/10.2172/1838995
State	Published - 2021

Keywords

22 GENERAL STUDIES OF NUCLEAR REACTORS

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10.2172/1838995

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title = "BWR Progression Problems",

abstract = "Under the Consortium for the Advanced Simulation of Light Water Reactors (CASL) Program, the Virtual Environment for Reactor Applications (VERA) was developed with the primary focus to model pressurized water reactors (PWRs). Recently, a new project was started to extend the modeling capability in VERA to model boiling water reactors (BWRs). The new project is called “Modeling and Analysis of Exelon BWRs for Eigenvalue and Thermal Limits Predictability,” and it is led by Oak Ridge National Laboratory (ORNL) and Exelon with participation from Global Nuclear Fuel and three universities: North Carolina State University (NCSU), the University of Michigan, and the University of Illinois.",

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AU - Palmtag, Scott

AU - Asgari, Mehdi

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AB - Under the Consortium for the Advanced Simulation of Light Water Reactors (CASL) Program, the Virtual Environment for Reactor Applications (VERA) was developed with the primary focus to model pressurized water reactors (PWRs). Recently, a new project was started to extend the modeling capability in VERA to model boiling water reactors (BWRs). The new project is called “Modeling and Analysis of Exelon BWRs for Eigenvalue and Thermal Limits Predictability,” and it is led by Oak Ridge National Laboratory (ORNL) and Exelon with participation from Global Nuclear Fuel and three universities: North Carolina State University (NCSU), the University of Michigan, and the University of Illinois.

KW - 22 GENERAL STUDIES OF NUCLEAR REACTORS

U2 - 10.2172/1838995

DO - 10.2172/1838995

M3 - Commissioned report

BT - BWR Progression Problems

CY - United States

ER -

BWR Progression Problems

Abstract

Keywords

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