Published 1987 | Version v1
Journal article

Trench fast reactor design using the microcomputer

  • 1. Iowa State Univ., Ames (USA)

Description

This project is a study of alternative liquid-metal-cooled fast power reactor system concepts. Specifically, an unconventional primary system is being conceptually designed and evaluated. The project design is based primarily on microcomputer analysis through the use of computational modules. The reactor system concept is a long, narrow pool with a long, narrow reactor called a trench-type pool reactor in it. The reactor consists of five core-blanket modules in a line. Specific power is to be modest, permitting long fuel residence time. Two fuel cycles are currently being considered. The reactor design philosophy is that of the inherently safe concept. This requires transient analysis dependent on reactivity coefficients: prompt fuel, including Doppler and expansion, fuel expansion, sodium temperature and void, and core expansion. Conceptual reactor design is done on a microcomputer. A part of the trench reactor project is to develop a microcomputer-based system that can be used by the user for scoping studies and design. Current development includes the neutronics and fuel management aspects of the design. Thermal-hydraulic analysis and economics are currently being incorporated into the microcomputer system. The system is menu-driven including preparation of program input data and of output data for displays in graphics form

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
55
Series
Trans. Am. Nucl. Soc.
Journal Page Range
627-628
ISSN
0003-018X
CODEN
TANSA

Conference

Title
American Nuclear Society winter meeting.
Dates
15-19 Nov 1987.
Place
Los Angeles, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
20003914
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BREEDING BLANKETS; COMPUTER CALCULATIONS; CONTROL ELEMENTS; HEAT TRANSFER; HYDRAULICS; LIQUID METAL COOLED REACTORS; PRIMARY COOLANT CIRCUITS; REACTOR KINETICS; SPECIFICATIONS
Descriptors DEC
COOLING SYSTEMS; ENERGY TRANSFER; KINETICS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS

Optional Information

Secondary number(s)
CONF-8711195--.