Continue the same-rod-number and same-height comparison from part(a), and assume unchanged pump speed, similar inlet conditions and single-phase forced flow for the normal-operation hydraulic argument.
Core power density increases. The active core volume decreases while total thermal power stays fixed. The fuel's own average volumetric power and the mean fuel linear heat rate do not increase merely from bringing the same rods closer together: fuel volume and rod count are unchanged.
Coolant mass flow rate normally decreases. Tighter passages reduce flow area and hydraulic diameter, increasing the core's hydraulic resistance. The unchanged centrifugal pumps do not enforce constant flow. The pump operating point moves to the intersection of the same pump curve with the steeper system-resistance curve, normally giving smaller flow at greater pump head.[ref]
Thermodynamics, Heat Transfer, and Fluid Flow, Volume 3 by the United States Department of Energy. Module HT-03, pp.51–53, System Characteristic Curve and System Operating Point, Figure10
The core pressure drop normally increases for the usual pump curve. Its resistance at any given flow is higher. At the new, smaller flow, unchanged external piping and component losses are smaller, whereas a conventional falling pump head-versus-flow curve gives greater available head. The core takes the difference. This conclusion uses the stated pump-curve assumptions; holding flow fixed or holding pump head fixed would be different models. The exact new flow and pressure drop need both system and pump characteristics.
Fuel temperature would normally tend to rise, especially downstream, if the loss of flow increases coolant heating without a compensating improvement in film heat transfer. At fixed inlet state,shows that smaller total mass flow rate raises the bulk coolant temperature rise. At unchanged local fuel linear heat rate, the fuel-to-surface conductive contribution is approximately unchanged if material properties and gap conditions are held fixed. Its boundary temperature and the coolant film drop can nevertheless change.
The local coolant mass flux is . Both total flow and flow area decrease, so the sign of the change in , the heat transfer coefficient and the fuel temperature cannot be deduced from total flow alone. Changes in power peaking and inlet conditions add further qualifications to the usual hotter-fuel tendency.
The minimum departure from nucleate boiling ratio would commonly decrease, implying reduced boiling margin, but its sign is conditional. The defining local ratio isThe numerator is the critical heat flux for the local conditions, and the denominator is actual rod-surface heat flux.[ref]
Reactor glossary by the United States Nuclear Regulatory Commission. Departure from nucleate boiling ratio entry
The mean surface heat loading remains approximately unchanged for the same rods and total power. Greater coolant enthalpy rise tends to reduce margin, while changes in , geometry, pressure and local power determine the actual critical heat flux. A geometry-appropriate correlation or experiment is needed for a definite MDNBR change; unchanged hardware does not supply it. Pump Created 2026-10-20 Updated 2026-11-05
A pump supplies mechanical energy to a fluid so that it can flow against resistance or gain elevation. For a steady incompressible stream, a rise in pressure at similar inlet and outlet heights and speeds represents useful fluid power , where is the volumetric flow rate. Differences in kinetic energy and gravitational potential energy must be included when those conditions do not hold.
A real installation chooses its flow through the interaction between the pump's pressure-flow response and the connected passages. More resistance generally shifts the pump operating point, so the nameplate or rotational speed alone does not determine mass flow rate. Measuring inlet/outlet pressures, flow and supplied mechanical power separates useful fluid output from dissipative losses. A centrifugal pump uses a rotating impeller; a displacement device instead moves a defined volume during a cycle, with leakage and compressibility affecting the actual delivery.
Thermodynamics, Heat Transfer, and Fluid Flow, Volume 3 by the United States Department of Energy 2026-10-20
Module HT-03 covers fluid mechanics, hydraulic losses and centrifugal pumps. Printed pp.51–53 explain the system characteristic curve and pump operating point. The date in the current hosting path does not change the handbook's original publication year.