Published 1986 | Version v1
Journal article

Out-of-core nuclear fuel cycle optimization utilizing an engineering workstation

  • 1. North Carolina State Univ., Raleigh (USA)

Description

Within the past several years, rapid advances in computer technology have resulted in substantial increases in their performance. The net effect is that problems that could previously only be executed on mainframe computers can now be executed on micro- and minicomputers. The authors are interested in developing an engineering workstation for nuclear fuel management applications. An engineering workstation is defined as a microcomputer with enhanced graphics and communication capabilities. Current fuel management applications range from using workstations as front-end/back-end processors for mainframe computers to completing fuel management scoping calculations. More recently, interest in using workstations for final in-core design calculations has appeared. The authors have used the VAX 11/750 minicomputer, which is not truly an engineering workstation but has comparable performance, to complete both in-core and out-of-core fuel management scoping studies. In this paper, the authors concentrate on our out-of-core research. While much previous work in this area has dealt with decisions concerned with equilibrium cycles, the current project addresses the more realistic situation of nonequilibrium cycles

Additional details

Publishing Information

Journal Title
Trans. Am. Nucl. Soc.
Journal Volume
52
Series
Trans. Am. Nucl. Soc.
Journal Page Range
94-96
ISSN
0003-018X
CODEN
TANSA

Conference

Title
American Nuclear Society annual meeting.
Dates
15-20 Jun 1986.
Place
Reno, NV (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19106395
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; COMPUTER CALCULATIONS; COMPUTER GRAPHICS; FUEL MANAGEMENT; MANAGEMENT; MONTE CARLO METHOD; OPTIMIZATION; PWR TYPE REACTORS; REACTOR KINETICS
Descriptors DEC
ENRICHED URANIUM REACTORS; KINETICS; NUCLEAR MATERIALS MANAGEMENT; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-860610--Summs.