Thermal-hydraulic analysis techniques for axisymmetric pebble bed nuclear reactor cores. [PEBBLE code]

Stroh, K.R.

doi:10.2172/6169433

Cited by 3 publications

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“…For a pebble bed core, the localized Nusselt number, and hence the heat transfer coefficient, can be derived from empirical correlations using the average velocity of the coolant in the core (Stroh, 1979).…”

Section: Thermal Hydraulic Analysis Modelingmentioning

confidence: 99%

“…Empirical correlations for the Nusselt number (Stroh, 1979) and pressure drop for a packed bed (Bird, Stewart, and Lightfoot, 1960) or column can be used to find the heat transfer coefficient and pumping power for the UHTGR concept. Equations 2 to 4 can be used to determine the temperature difference across the fuel pebble.…”

Section: Uhtgr Fuel Pebble Element -Helium Coolantmentioning

confidence: 99%

“…The same calculation was performed except that the thermal conductivity for a pebble-bed core (Stroh, 1979) with 6-cm diameter pebbles was used. A maximum core temperature of 1580°C is reached at ~21 hours after shutdown.…”

Section: Vhtgr -Passive Heat Removal Analysismentioning

confidence: 99%

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Very High Efficiency Reactor (VHER) Concepts for Electrical Power Generation and Hydrogen Production

Parma¹,

Pickard²,

Suo-Anttila³

2003

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The goal of the Very High Efficiency Reactor study was to develop and analyze concepts for the next generation of nuclear power reactors. The next generation power reactor should be cost effective compared to current power generation plant, passively safe, and proliferation-resistant. High-temperature reactor systems allow higher electrical generating efficiencies and hightemperature process heat applications, such as thermo-chemical hydrogen production. The study focused on three concepts; one using molten salt coolant with a prismatic fuel-element geometry, the other two using high-pressure helium coolant with a prismatic fuel-element geometry and a fuel-pebble element design. Peak operating temperatures, passive-safety, decay heat removal, criticality, burnup, reactivity coefficients, and material issues were analyzed to determine the technical feasibility of each concept.4

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Section: Thermal Hydraulic Analysis Modelingmentioning

confidence: 99%

Section: Uhtgr Fuel Pebble Element -Helium Coolantmentioning

confidence: 99%

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Very High Efficiency Reactor (VHER) Concepts for Electrical Power Generation and Hydrogen Production

Parma¹,

Pickard²,

Suo-Anttila³

2003

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Forced-Convection Cooling of a Linear Array of Blocks in Open and Porous Matrix Channels

Rizk

Kleinstreuer

1991

Heat Transfer Engineering

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PEBBLE: a two-dimensional steady-state pebble bed reactor thermal hydraulics code

Vondy¹

1981

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Thermal-hydraulic analysis techniques for axisymmetric pebble bed nuclear reactor cores. [PEBBLE code]

Abstract: I. INTRODUCTION 1 A. Pebble Bed Nuclear Reactor Concept 1 B. Motivation of the Study 3 II.

Cited by 3 publications

References 0 publications

Very High Efficiency Reactor (VHER) Concepts for Electrical Power Generation and Hydrogen Production

Very High Efficiency Reactor (VHER) Concepts for Electrical Power Generation and Hydrogen Production

Forced-Convection Cooling of a Linear Array of Blocks in Open and Porous Matrix Channels

PEBBLE: a two-dimensional steady-state pebble bed reactor thermal hydraulics code

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