HTGR Knowledge Base

Conference Article: Developmental assessment of the Fort St. Vrain version of the composite HTGR analysis program (CHAP-2)

Stroh, K.R. (Los Alamos Scientific Lab., NM (USA))

Abstract

The Composite HTGR Analysis Program (CHAP) consists of a model-independent systems analysis mainframe named LASAN and model-dependent linked code modules, each representing a component, subsystem, or phenomenon of an HTGR plant. The Fort St. Vrain version (CHAP-2) includes 21 coded modules that model the neutron kinetics and thermal response of the core. The thermal-hydraulics of the reactor primary coolant system, secondary steam supply system, and balance-of-plant. The actions of the control system and plant protection system. The response of the reactor building. And the relative hazard resulting from fuel particle failure. FSV steady-state and transient plant data are being used to partially verify the component modeling and dynamic simulation techniques used to predict plant response to postulated accident sequences. Results of these preliminary validation efforts are presented showing good agreement between code output and plant data for the portions of the code that have been tested. Plans for further development and assessment as well as application of the validated code are discussed.

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key words: buildings; c codes; computerized simulation; primary coolant circuits; radiation hazards; reactor control systems; reactor cores; reactor kinetics; reactor protection systems; reactor safety; secondary coolant circuits; transients; vrain reactor; computer codes; control systems; cooling systems; enriched uranium reactors; gas cooled reactors; graphite moderated reactors; hazards; health hazards; htgr type reactors; kinetics; power reactors; reactor components; reactor cooling systems; reactors; safety; simulation
Reference:
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors. Specialists meeting on gas-cooled reactor safety and licensing aspects, Lausanne, Switzerland, 1-3 September 1980. Summary report. Jan 1981
International Atomic Energy Agency, Vienna (Austria). International Working Group on High-Temperature Reactors.
IWGGCR--1, pp:63-67