NUCLEAR REACTOR HEAT TRANSFER

Technical Report · Fri Dec 01 04:00:00 EST 1961

OSTI ID:4812427

Lottes, P A

Text material for a graduate course in heat transfer applications to nuclear engineering is presented. Topics covered include fuel element heat transfer-steady state, fuel assembly calculations, maximum-to-average heat flux calculations, hot spot factors, power excursion equations, fuel element transients, shutdown cooling calculations, shield cooling calculations, boiling heat transfer-steady state, two-phase pressure drop with constant flow area, two- phase density and slip ratio, expansion losses with two-phase flow, contraction losses with two-phase flow, hydrodynamic analysis of a natural-circulation circuit, flow in parallel channels, calculation of boiling length, and calculation for a boiling reactor core. (M.C.G.)

• Research Organization: Argonne National Lab., Ill.
• DOE Contract Number: W-31109-ENG-38
• NSA Number: NSA-16-009617
• OSTI ID: 4812427
• Report Number(s): ANL-6469
• Country of Publication: United States
• Language: English

Related Subjects

BOILING
CONFIGURATION
CONVECTION
COOLANT LOOPS
COOLANTS
COOLING
DECAY
DENSITY
EQUATIONS
EVAPORATION
EXCURSIONS
EXPANSION
FLUID FLOW
GAS FLOW
HEAT TRANSFER
HIGH TEMPERATURE
NEUTRON FLUX
NUMERICALS
PERSONNEL
POWER PLANTS
PRESSURE
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
SHUTDOWN
STABILITY
STEAM
THERMAL CONDUCTIVITY
THERMODYNAMICS
TRANSIENTS
VARIATIONS
WATER