CAE - nuclear engineering analysis on work-station computers

Conference · Wed Jan 01 00:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6754414

Wessol, D E; Liebelt, K H; Merrill, B J; Nigg, D W; Wheeler, F J

Emergence of the inexpensive and widely available 32-bit-work-station computer is revolutionizing the scientific and engineering computing environment. These systems reach or exceed threshold for many midscale nuclear applications and bridge the gap between the era of expensive computing: cheap people and the era of cheap computing: expensive people. Experience at the Idaho National Engineering Laboratory (INEL) has demonstrated the efficacy of this new computer technology. For the past 1 1/2 yr, a Hewlett-Packard 9000/540 32-bit multi-user microcomputer has been used to perform many calculations typical of a nuclear design effort. This system is similar with respect to performance and memory to such work stations as the SUN-3, HP-9000/32, or the Apollo DN-3000 that are available for under $20,000 for a fully configured single-user station. The system is being used for code development, model setup and checkout, and a full range of nuclear applications. Various one- and two-dimensional discrete ordinates transport codes are used on a routine basis. These include the well-known ANISN code as well as locally developed transport models. Typical one-dimensional multigroup calculations can be executed in clock times <10 min.

• Research Organization: Idaho National Engineering Lab., Idaho Falls
• OSTI ID: 6754414
• Report Number(s): CONF-861102-
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 53; Conference: American Nuclear Society and Atomic Industrial Forum joint meeting, Washington, DC, USA, 16 Nov 1986
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
NUCLEAR ENGINEERING
COMPUTER CALCULATIONS
COMPUTER-AIDED DESIGN
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
FINITE DIFFERENCE METHOD
FUEL MANAGEMENT
GROUP THEORY
HEAT TRANSFER
HYDRAULICS
MONTE CARLO METHOD
ONE-DIMENSIONAL CALCULATIONS
PERFORMANCE
PWR TYPE REACTORS
R CODES
REACTOR KINETICS
S CODES
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS
TWO-DIMENSIONAL CALCULATIONS
COMPUTER CODES
ENERGY TRANSFER
ENGINEERING
FLUID MECHANICS
ITERATIVE METHODS
KINETICS
MATHEMATICS
MECHANICS
NUMERICAL SOLUTION
REACTORS
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS
220100* - Nuclear Reactor Technology- Theory &amp; Calculation