Validation of NESTLE against static reactor benchmark problems

Conference · Thu Feb 01 00:00:00 EST 1996

OSTI ID:225064

Mosteller, R D

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. (LANL), Los Alamos, 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; TRN: 96:012716
• Resource Relation: Conference: Annual meeting of the American Nuclear Society (ANS), Reno, NV (United States), 16-20 Jun 1996; Other Information: PBD: [1996]
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR PHYSICS
PWR TYPE REACTORS
HTGR TYPE REACTORS
CANDU TYPE REACTORS
N CODES
REACTOR FUELING
BENCHMARKS
NODAL EXPANSION METHOD
ITERATIVE METHODS
TWO-DIMENSIONAL CALCULATIONS
THREE-DIMENSIONAL CALCULATIONS
STEADY-STATE CONDITIONS