Published 1987 | Version v1
Journal article

CENTAR code for extended nonlinear transient analysis of extraterrestrial reactor systems

  • 1. Texas A and M Univ., College Station (USA)

Description

Current interest in the application of nuclear reactor-driven power systems to space missions has generated a need for a systems simulation code to model and analyze space reactor systems; such a code has been initiated at Texas A and M, and the first version is nearing completion; release was anticipated in the fall of 1987. This code, named CENTAR (Code for Extended Nonlinear Transient Analysis of Extraterrestrial Reactor Systems), is designed specifically for space systems and is highly vectorizable. CENTAR is composed of several specialized modules. A fluids module is used to model fluid behavior throughout the system. A wall heat transfer module models the heat transfer characteristics of all walls, insulation, and structure around the system. A fuel element thermal analysis module is used to predict the temperature behavior and heat transfer characteristics of the reactor fuel rods. A kinetics module uses a six-group point kinetics formulation to model reactivity feedback and control and the ANS 5.1 decay-heat curve to model shutdown decay-heat production. A pump module models the behavior of thermoelectric-electromagnetic pumps, and a heat exchanger module models not only thermal effects in thermoelectric heat exchangers, but also predicts electrical power production for a given configuration. Finally, an accumulator module models coolant expansion/contraction accumulators

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
55
Series
Trans. Am. Nucl. Soc.
Journal Page Range
726-728
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
20003943
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
C CODES; HEAT TRANSFER; HYDRAULICS; PUMPS; REACTOR KINETICS; REACTOR SAFETY; SPACE POWER REACTORS; TRANSIENTS; VECTOR PROCESSING
Descriptors DEC
COMPUTER CODES; ENERGY TRANSFER; EQUIPMENT; KINETICS; MOBILE REACTORS; POWER REACTORS; PROGRAMMING; REACTORS; SAFETY

Optional Information

Secondary number(s)
CONF-8711195--.