A Mechanism Explaining The Instability Of EBR-I, Mark III

Technical Report · Fri Sep 01 04:00:00 EDT 1961

DOI:https://doi.org/10.2172/4836022· OSTI ID:4836022

Smith, R. R. ^[1]; Matlock, R. G. ^[1]; McGinnis, F. D. ^[1]; Novick, M. ^[1]; Thalgott, F. W. ^[1]

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1. Argonne National Laboratory (ANL), Argonne, IL (United States)

Presented at the International Atomic Energy Agencysponsored Seminar on the Physics of Fast and Intermediate Reactors. Vienna, August 3-11, 196l. A feedback model, was developed to account for resonant instabilities in the Mark II core. In this model, the prompt positive power coefficient effect is ascribed to fuel rod bowing and the delayed negative power coefficient effect to thermally lnduced motions in the lower shield plate. Since this model is supported by observations, it is concluded that the instability of Mark II is chiefly due to lack of radial coupling between fuel rods. (D.L.C.)

• Research Organization: Argonne National Laboratory (ANL), Argonne, IL (United States)
• Sponsoring Organization: Univ. of Chicago, IL (United States); USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: W-31109-ENG-38
• NSA Number: NSA-16-001185
• OSTI ID: 4836022
• Report Number(s): ANL--6354
• Country of Publication: United States
• Language: English

Related Subjects

ANALOG SYSTEMS
CONFERENCE
CONFIGURATION
DEFORMATION
DELAYED NEUTRONS
EBR-1
FAILURES
FUEL ELEMENTS
HEAT TRANSFER
MEASURED VALUES
MECHANICAL STRUCTURES
MOTION
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
PLANNING
PLATES
POWER PLANTS
PROMPT NEUTRONS
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
RESONANCE
RODS
SHIELDING
STABILITY
TEMPERATURE
THERMAL STRESSES
TRANSFER FUNCTIONS
TRANSIENTS
VARIATIONS