Dynamic modeling of the advanced neutron source reactor

Conference · Fri Jun 01 00:00:00 EDT 1990 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6022074

March-Leuba, J ^[1]; Ibn-Khayat, M ^[2]

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1. Oak Ridge National Lab., TN (USA)
2. Univ. of Tennessee, Knoxville (USA)

The purpose of this paper is to provide a summary description and some applications of a computer model that has been developed to simulate the dynamic behavior of the advanced neutron source (ANS) reactor. The ANS dynamic model is coded in the advanced continuous simulation language (ACSL), and it represents the reactor core, vessel, primary cooling system, and secondary cooling systems. The use of a simple dynamic model in the early stages of the reactor design has proven very valuable not only in the development of the control and plant protection system but also of components such as pumps and heat exchangers that are usually sized based on steady-state calculations.

• OSTI ID: 6022074
• Report Number(s): CONF-900608-; CODEN: TANSA; TRN: 91-008346
• Journal Information: Transactions of the American Nuclear Society; (USA), Vol. 61; Conference: American Nuclear Society (ANS) annual meeting, Nashville, TN (USA), 10-14 Jun 1990; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
NEUTRON SOURCES
PLANNING
REACTOR KINETICS
A CODES
RESEARCH REACTORS
REACTOR SAFETY
AFTER-HEAT REMOVAL
BENCHMARKS
CONTAINMENT SYSTEMS
DYNAMICS
HEAT EXCHANGERS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
LOSS OF FLOW
PIPES
PRESSURIZERS
PRIMARY COOLANT CIRCUITS
PUMPS
REACTIVITY
REACTOR CHANNELS
REACTOR CONTROL SYSTEMS
REACTOR CORES
REACTOR PROTECTION SYSTEMS
REACTOR VESSELS
SCRAM
SECONDARY COOLANT CIRCUITS
ACCIDENTS
COMPUTER CODES
CONTAINERS
CONTAINMENT
CONTROL SYSTEMS
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
KINETICS
MECHANICS
PARTICLE SOURCES
RADIATION SOURCES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SHUTDOWN
REACTORS
REMOVAL
RESEARCH AND TEST REACTORS
SAFETY
SHUTDOWN
220900* - Nuclear Reactor Technology- Reactor Safety
220700 - Nuclear Reactor Technology- Plutonium & Isotope Production Reactors