Validation of NESTLE against static reactor benchmark problems
Conference
·
OSTI ID:225064
The NESTLE advanced modal code was developed at North Carolina State University with support from Los Alamos National Laboratory and Idaho National Engineering Laboratory. It recently has been benchmarked successfully against measured data from pressurized water reactors (PWRs). However, NESTLE`s geometric capabilities are very flexible, and it can be applied to a variety of other types of reactors. This study presents comparisons of NESTLE results with those from other codes for static benchmark problems for PWRs, boiling water reactors (BWRs), high-temperature gas-cooled reactors (HTGRs) and CANDU heavy- water reactors (HWRs).
- Research Organization:
- Los Alamos National Lab., NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 225064
- Report Number(s):
- LA-UR--95-4488; CONF-9606116--1; ON: DE96007351
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
BENCHMARKS
BWR TYPE REACTORS
CANDU TYPE REACTORS
HTGR TYPE REACTORS
ITERATIVE METHODS
N CODES
NODAL EXPANSION METHOD
PWR TYPE REACTORS
REACTOR FUELING
REACTOR PHYSICS
STEADY-STATE CONDITIONS
THREE-DIMENSIONAL CALCULATIONS
TWO-DIMENSIONAL CALCULATIONS
22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
BENCHMARKS
BWR TYPE REACTORS
CANDU TYPE REACTORS
HTGR TYPE REACTORS
ITERATIVE METHODS
N CODES
NODAL EXPANSION METHOD
PWR TYPE REACTORS
REACTOR FUELING
REACTOR PHYSICS
STEADY-STATE CONDITIONS
THREE-DIMENSIONAL CALCULATIONS
TWO-DIMENSIONAL CALCULATIONS