System seismic analysis of an innovative primary system for a large pool type LMFBR plant

Conference · Sun Jan 01 00:00:00 EST 1984

OSTI ID:6861514

Pan, Y C; Wu, T S; Cha, B K; Burelbach, J; Seidensticker, R

The system seismic analysis of an innovative primary system for a large pool type liquid metal fast breeder reactor (LMFBR) plant is presented. In this primary system, the reactor core is supported in a way which differs significantly from that used in previous designs. The analytical model developed for this study is a three-dimensional finite element model including one-half of the primary system cut along the plane of symmetry. The model includes the deck and deck mounted components,the reactor vessel, the core support structure, the core barrel, the radial neutron shield, the redan, and the conical support skirt. The sodium contained in the primary system is treated as a lumped mass appropriately distributed among various components. The significant seismic behavior as well as the advantages of this primary system design are discussed in detail.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6861514
• Report Number(s): CONF-840647-7; ON: DE84007272
• Resource Relation: Conference: ASME pressure vessel and piping conference, San Antonio, TX, USA, 17 Jun 1984; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LMFBR TYPE REACTORS
PRIMARY COOLANT CIRCUITS
SEISMIC EFFECTS
FINITE ELEMENT METHOD
MATHEMATICAL MODELS
STRESS ANALYSIS
THREE-DIMENSIONAL CALCULATIONS
BREEDER REACTORS
COOLING SYSTEMS
ENERGY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
LIQUID METAL COOLED REACTORS
NUMERICAL SOLUTION
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding