Power Reactivity Decrement Components of a Homogeneous UPu10Zr-Fueled 900-MW(Thermal) Liquid Metal Reactor

Conference · Sun Jun 04 04:00:00 EDT 1989 · Transactions of the American Nuclear Society

OSTI ID:6923487

Linear and Doppler feedback components of the power reactivity decrement (PRD) for a 900-MW(thermal) homogeneous UPu10Zr-fueled sodium-cooled reactor have been calculated. (The PRD is the negative of the reactivity required to bring the reactor from a zero-power hot-critical condition to a given power level.) The components are further separated into power-dependent and power-to-flow-dependent parts. These delineations enhance understanding of the contributions of the components to the feedback process. The delineation also enables the PRDs for other values of coolant flows to be estimated. The linear and Doppler components of the PRD are obtained using the EBRPOCO code, which calculates detailed axially delineated contributions of the components for every subassembly of a loading configuration. Separation of the components into power and power-to-flow parts is made by calculations of the components, assuming infinite thermal conductivities to obtain the power-to-flow values. Subtractions of these from the corresponding PRD quantities give the power-dependent parts. The values of the various feedback components are compared with corresponding quantities reported for an analogous U10Zr-fueled case.

• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 6923487
• Report Number(s): CONF-890604--
• Conference Information: Journal Name: Transactions of the American Nuclear Society Journal Volume: 59
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
97 MATHEMATICS AND COMPUTING
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
ACTINIDES
ALLOYS
CRITICALITY
DOPPLER EFFECT
EBRPOCO Code
ELEMENTS
ENERGY TRANSFER
FLOW RATE
FLUID MECHANICS
HEAT TRANSFER
HOMOGENEOUS REACTORS
HYDRAULICS
IRON ALLOYS
IRON BASE ALLOYS
KINETICS
LIQUID METAL COOLED REACTORS
Linear and Doppler Feedback Components
MECHANICS
METALS
Nuclear Criticality Safety Program (NCSP)
PLUTONIUM
POWER DENSITY
Power Reactivity Decrement (PRD)
REACTIVITY
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
SODIUM COOLED REACTORS
STEELS
TRANSITION ELEMENTS
TRANSURANIUM ELEMENTS
UPu10Zr-Fueled Sodium-Cooled Reactor
URANIUM
ZIRCONIUM