THE DERIVATION OF REACTOR HEAT TRANSFER TRANSIENT EQUATIONS FOR GAS COOLED GRAPHITE MODERATED THERMAL REACTORS

Technical Report · Wed May 21 00:00:00 EDT 1958

OSTI ID:4283101

O'Neill, T J

In making transient studies on the behavior of gas-cooled graphite moderated thermal reactors, one of the sets of mathematical equations involved is that for reactor heat transfer. These equations have for inputs: reactor power, reactor gas flow and reactor inlet gas temperature; and produce as output: reactor outlet gas temperature, the uranium and graphite reactivity affecting variables, and the maximum fuel element temperatures. From the consideration of a unit length of one fuel element channel in the core, partial differential equations of the system are determined. These are integrated in space, to give the form required for analogue computer studies, i.e., simultaneous ordinary nonlinear diffential equations. The final equations are given for two variants in moderator design, viz: a solid block type of moderator, and a moderator involving in part a graphite fuel element supporting sleeve. Account is taken of heat transfer by conduction in the solids, and by convection and thermal radiation in and between the gas spaces.

• Research Organization: General Electric Co., Ltd., Erith, Kent, Eng.
• NSA Number: NSA-13-007197
• OSTI ID: 4283101
• Report Number(s): A/CONF.15/P/21
• Resource Relation: Conference: 2. United Nations International Conference on the Peaceful Uses of Atomic Energy, Geneva (Switzerland), 1958.; Other Information: Orig. Receipt Date: 31-DEC-59
• Country of Publication: United Kingdom
• Language: English

Related Subjects

REACTORS
ANALOG SYSTEMS
COMPUTERS
CONFIGURATION
CONVECTION
COOLANT LOOPS
DIFFERENTIAL EQUATIONS
DISTRIBUTION
EQUATIONS
FUEL ELEMENTS
GAS COOLANT
GAS FLOW
GRAPHITE
GRAPHITE MODERATOR
HEAT TRANSFER
HIGH TEMPERATURE
MATHEMATICS
MECHANICAL STRUCTURES
MODERATORS
NEUTRON FLUX
PLANNING
POWER PLANTS
PRESSURE
REACTIVITY
REACTOR CORE
TEMPERATURE
THERMAL CONDUCTIVITY
THERMAL NEUTRONS
THERMAL RADIATION
THERMODYNAMICS
TRANSIENTS
URANIUM
VARIATIONS
ZONES