STEALTH: a Lagrange explicit finite difference code for solids, structural, and thermohydraulic analysis. Volume 1A: user's manual - theoretical background and numerical equations. Computer code manual. [PWR; BWR]

Technical Report · Sun Nov 01 00:00:00 EST 1981

DOI:https://doi.org/10.2172/7033716· OSTI ID:7033716

Hofmann, R.

A useful computer simulation method based on the explicit finite difference technique can be used to address transient dynamic situations associated with nuclear reactor design and analysis. This volume is divided into two parts. Part A contains the theoretical background (physical and numerical) and the numerical equations for the STEALTH 1D, 2D, and 3D computer codes. Part B contains input instructions for all three codes. The STEALTH codes are based entirely on the published technology of the Lawrence Livermore National Laboratory, Livermore, California, and Sandia National Laboratories, Albuquerque, New Mexico.

• Research Organization: Science Applications, Inc., San Leandro, CA (USA)
• OSTI ID: 7033716
• Report Number(s): EPRI-NP-2080-Vol.1a; ON: DE83900191
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR INTERNALS
TRANSIENTS
COMPUTER CODES
S CODES
THERMAL STRESSES
PWR TYPE REACTORS
HEAT TRANSFER
HYDRAULICS
FINITE DIFFERENCE METHOD
REACTOR SAFETY
STRESS ANALYSIS
THERMODYNAMICS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
ITERATIVE METHODS
MECHANICS
NUMERICAL SOLUTION
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAFETY
STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled