skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: BWR Progression Problems

Technical Report ·
DOI:https://doi.org/10.2172/1838995· OSTI ID:1838995
 [1];  [1];  [2]
  1. North Carolina State Univ., Raleigh, NC (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

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.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC05-00OR22725
OSTI ID:
1838995
Report Number(s):
ORNL/TM-2020/1792; TRN: US2302670
Country of Publication:
United States
Language:
English

Similar Records

VUSAT - A VERA-CS Uncertainty and Sensitivity Analysis Toolkit
Journal Article · Sat Jul 01 00:00:00 EDT 2017 · Transactions of the American Nuclear Society · OSTI ID:1838995

Development and Assessment of CTF for Pin-resolved BWR Modeling
Conference · Sun Jan 01 00:00:00 EST 2017 · OSTI ID:1838995

Implementation of a Pressure Correction Term in the CTF Subchannel Code
Journal Article · Sat Jul 01 00:00:00 EDT 2017 · Transactions of the American Nuclear Society · OSTI ID:1838995