Published November 1989 | Version v1
Journal article

SASSYS-1 balance-of-plant component models for an integrated plant response

Creators

  • 1. Argonne National Laboratory, IL (USA)

Description

The balance-of-plant (BOP) system of a nuclear power plant is a complicated thermal-hydraulic network involving several types of components interacting with one another. A first-principles analysis of such a complex system would be a formidable computation task. Such an approach appears to be the one represented by the mathematical models and numerical techniques of codes like RETRAN and RELAP, which are capable of performing elaborate analyses on plant transients. The approach taken for the SASSYS-1 BOP component models was deliberately different. Hard-wired component-specific models were developed. The stand-alone coding for the various types of SASSYS-1 BOP components can be said to be based on models that rely on simple conservation balances and extensive component data in the form of correlations. This should ensure a reasonable and adequate simulation and should not take extensive time in terms of computation and user setup. A validation program will be implemented to verify the capability of the models to generate results within an acceptable accuracy range. Models of power plant heat transfer components and rotating machinery have been added to the BOP model in the SASSYS-1 liquid-metal reactor systems analysis code. The models described in this paper extend the scope of the BOP model to handle nonadiabatic conditions along flow paths. The heat source term is treated with full explicitness. The seven types of heaters and the turbine model are discussed in this paper

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
60
Series
Trans. Am. Nucl. Soc.
Journal Page Range
716-717
ISSN
0003-018X
CODEN
TANSA

Conference

Title
Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit.
Dates
26-30 Nov 1989.
Place
San Francisco, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
22085791
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCURACY; COMPUTERIZED SIMULATION; LIQUID METAL COOLED REACTORS; MATHEMATICAL MODELS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; S CODES; TRANSIENTS
Descriptors DEC
COMPUTER CODES; COOLING SYSTEMS; REACTORS; SIMULATION

Optional Information

Secondary number(s)
CONF-891103--.