An integrated systems calculation of a steam generator tube rupture in a modular prismatic HTGR (high-temperature gas-cooled reactor) conceptual design using ATHENA (Advanced Thermal-Hydraulic Energy Network Analyzer)

Conference · Wed Nov 01 00:00:00 EST 1989 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5417415

Beelman, R J ^[1]

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1. Idaho National Engineering Laboratory, Idaho Falls (USA)

The capability to perform integrated systems calculations of modular high-temperature gas-cooled reactor (MHTGR) transients has been developed at the Idaho National Engineering Laboratory (INEL) using the Advanced Thermal-Hydraulic Energy Network Analyzer (ATHENA) computer code. A scoping calculation of a steam generator tube rupture (SGTR) water ingress event in a prismatic 2 {times} 350-MW(thermal) MHTGR conceptual design has been completed at INEL using ATHENA. The proposed MHTGR design incorporates dual, graphite-moderated, helium-cooled, 350-MW(thermal), annular prismatic core concept reactor plants, each configured with an individual helical once-through steam generator steaming a common 280-MW(electric) turbine generator set.

• OSTI ID: 5417415
• Report Number(s): CONF-891103-; CODEN: TANSA; TRN: 91-024669
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 60; Conference: Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit, San Francisco, CA (United States), 26-30 Nov 1989; 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
HTGR TYPE REACTORS
STEAM GENERATORS
LOSS OF COOLANT
A CODES
TUBES
RUPTURES
DESIGN
HELIUM
IDAHO NATIONAL ENGINEERING LABORATORY
MODULAR STRUCTURES
OXIDATION
PRIMARY COOLANT CIRCUITS
R CODES
REACTOR CORES
REACTOR KINETICS
REACTOR PHYSICS
SECONDARY COOLANT CIRCUITS
SYSTEMS ANALYSIS
TRANSIENTS
WATER
ACCIDENTS
BOILERS
CHEMICAL REACTIONS
COMPUTER CODES
COOLING SYSTEMS
ELEMENTS
ENERGY SYSTEMS
FAILURES
FLUIDS
GAS COOLED REACTORS
GASES
GRAPHITE MODERATED REACTORS
HYDROGEN COMPOUNDS
KINETICS
NATIONAL ORGANIZATIONS
NONMETALS
OXYGEN COMPOUNDS
PHYSICS
RARE GASES
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
US DOE
US ERDA
US ORGANIZATIONS
VAPOR GENERATORS
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
Graphite Moderated