Static three-dimensional ARROTTA benchmarking
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5772523
ARROTTA (Advanced Reactor Rapid Operational TransienT Analyzer) is a three-dimensional analytic nodal diffusion theory computer code. It has been developed for spatial kinetics applications and was sponsored by the Electric Power Research Institute (EPRI). The results presented here are part of the benchmarking and validation of the ARROTTA steady-state initializer and its associated numerical methodology. These results demonstrate the accuracy and efficiency of the ARROTTA steady-stage initializer for a variety of benchmarks, including a three-dimensional problem with full thermal-hydraulic feedback.
- Research Organization:
- S. Levy, Inc., Campbell, CA
- OSTI ID:
- 5772523
- Report Number(s):
- CONF-851115-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 50; ISSN TANSA
- Country of Publication:
- United States
- Language:
- English
Similar Records
The advanced nodal transient analysis code ARROTTA
PWR benchmarking of ARROTTA at beginning of life
Three-dimensional transient analysis capability in SIMULATE-3
Conference
·
Fri Jun 01 00:00:00 EDT 1990
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:6179228
PWR benchmarking of ARROTTA at beginning of life
Conference
·
Sun Oct 30 00:00:00 EDT 1988
· Transactions of the American Nuclear Society
·
OSTI ID:5916550
Three-dimensional transient analysis capability in SIMULATE-3
Journal Article
·
Fri Dec 30 23:00:00 EST 1994
· Transactions of the American Nuclear Society
·
OSTI ID:89270
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
A CODES
ACCURACY
BENCHMARKS
COMPUTER CODES
DIFFERENTIAL EQUATIONS
ENERGY TRANSFER
EPRI
EQUATIONS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
MECHANICS
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
RADIATION FLUX
REACTOR KINETICS
STEADY-STATE CONDITIONS
THREE-DIMENSIONAL CALCULATIONS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
A CODES
ACCURACY
BENCHMARKS
COMPUTER CODES
DIFFERENTIAL EQUATIONS
ENERGY TRANSFER
EPRI
EQUATIONS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
KINETICS
MECHANICS
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
RADIATION FLUX
REACTOR KINETICS
STEADY-STATE CONDITIONS
THREE-DIMENSIONAL CALCULATIONS