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

Conference · Sun Jun 04 00:00:00 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-; CODEN: TANSA; TRN: 90-023488
• Journal Information: Transactions of the American Nuclear Society, Vol. 59; Conference: Annual Meeting of the American Nuclear Society , Atlanta, GA (United States), 4-8 Jun 1989; ISSN 0003-018X
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

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