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]
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
Similar Records
STEALTH: a Lagrange explicit finite difference code for solids, structural, and thermohydraulic analysis. Volume 1B: user's manual - input instructions. Computer code manual. [PWR; BWR]
'STEALTH' a Lagrange explicit finite-difference code for solids structural, and thermohydraulic analysis. Technical report. [Nuclear reactor design]
STEALTH: a Lagrange explicit finite difference code for solids, structural, and thermohydraulic analysis. Volume 6: piping systems manual. Computer code manual
Technical Report
·
Sat Oct 31 23:00:00 EST 1981
·
OSTI ID:6762261
'STEALTH' a Lagrange explicit finite-difference code for solids structural, and thermohydraulic analysis. Technical report. [Nuclear reactor design]
Technical Report
·
Tue Jun 01 00:00:00 EDT 1976
·
OSTI ID:7217134
STEALTH: a Lagrange explicit finite difference code for solids, structural, and thermohydraulic analysis. Volume 6: piping systems manual. Computer code manual
Technical Report
·
Sun Feb 28 23:00:00 EST 1982
·
OSTI ID:6759826
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FINITE DIFFERENCE METHOD
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
ITERATIVE METHODS
MECHANICS
NUMERICAL SOLUTION
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR INTERNALS
REACTOR SAFETY
REACTORS
S CODES
SAFETY
STRESS ANALYSIS
STRESSES
THERMAL STRESSES
THERMODYNAMICS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BWR TYPE REACTORS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FINITE DIFFERENCE METHOD
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
ITERATIVE METHODS
MECHANICS
NUMERICAL SOLUTION
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR INTERNALS
REACTOR SAFETY
REACTORS
S CODES
SAFETY
STRESS ANALYSIS
STRESSES
THERMAL STRESSES
THERMODYNAMICS
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS