Validation of NESTLE against static reactor benchmark problems

Journal Article · Mon Dec 30 23:00:00 EST 1996 · Transactions of the American Nuclear Society

OSTI ID:436993

Mosteller, R D ^[1]

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1. Los Alamos National Laboratory, NM (United States)

The NESTLE advanced nodal 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 Canada deuterium uranium (CANDU) heavy-water reactors (HWRs).

• OSTI ID: 436993
• Report Number(s): CONF-9606116--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 74; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
66 PHYSICS
99 GENERAL AND MISCELLANEOUS
CANDU TYPE REACTORS
HTGR TYPE REACTORS
MULTIGROUP THEORY
N CODES
NEUTRON DIFFUSION EQUATION
NODAL EXPANSION METHOD
WATER COOLED REACTORS