Convective processes in spent nuclear fuel canisters

McCreery, Glenn E.; Condie, K. G.; Clarksean, Randy; McEligot, Donald M.

doi:10.1615/ihtc12.4380

Cited by 4 publications

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“…35. The World's largest Matched-Index-of-Refraction flow system using laser Doppler velocimetry to study fluid physics phenomena in an idealized SNF storage canister for an EM Science project [Stoots et al, 2001;McCreery et al, 2002] Glycol ret urn Durst, Keck and Kleine [1979] have suggested that the refractive index must be maintained within ± 0.0001 for high quality LDV measurements. For the mineral oil in the INEEL MIR system, this criterion translates to the requirement that the oil temperature must be held steady and uniform to within about 0.3 C; in general, we aim at a limit of about 0.1 C. Experience has shown that, after the initial transients, it is possible to maintain the test section temperature as close as about ± 0.02 C and the model temperature range to about ± 0.05 C, well within the desired limitations.…”

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confidence: 99%

“…Transition in boundary layers with the Lehrstuhl für Strömungsmechanik of Uni. Erlangen, Germany [Becker et al, 2002] Flow phenomena in SNF canisters for a DoE EM Science project [McCreery et al, 2002] Flow fields around buildings for assessment of Bechtel R&D computer simulations for fate and transport of biological agents [McCreery et al, 2001] Effects of realistic surface roughness on turbomachinery flows with U. Idaho for the Air Force Office of Scientific Research [Budwig et al, 2001] Complex flows relating to advanced gas-cooled nuclear reactors for the DoE NERI program [McCreery et al, 2003] Additional studies now include examination of complex flows relating to supercritical water reactors for the DoE US/Korea I-NERI program and synthetic jet actuators by U. Wyoming for the Air Force Office of Scientific Research.…”

Section: Not Matched Matchedmentioning

confidence: 99%

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Scaling studies and conceptual experiment designs for NGNP CFD assessment

McEligot¹,

McCreery²

2004

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Re Reynolds number, 4 m / D ; Re Dh , based on hydraulic diameter, G D h / Ri overall Richardson number, g (1-2) H / (1 V b 2) Ri wall Richardson number defined in terms of wall quantities (see text) Greek symbols volumetric coefficient of expansion,-(1/) (/ T) p dissipation of turbulence kinetic energy absolute viscosity kinematic viscosity, / density shear stress; w , wall shear stress Subscripts b evaluated at bulk or mixed-mean temperature (or enthalpy) D based on diameter DB Dittus-Boelter [1930] correlation Dh evaluated with hydraulic diameter f, fc forced convection i, in evaluated at inlet, entry j jet max maximum value p support post ref evaluated at reference conditions w, wall wall, evaluated at wall temperature Control Rod Drive Assembly Refueling Stand Pipe Control Rod Guide tubes

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Section: Not Matched Matchedmentioning

confidence: 99%

Section: Not Matched Matchedmentioning

confidence: 99%

Scaling studies and conceptual experiment designs for NGNP CFD assessment

McEligot¹,

McCreery²

2004

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“…28. The World's largest Matched-Index-of-Refraction flow system using laser Doppler velocimetry to study fluid physics phenomena in an idealized SNF storage canister for an EM Science project [Stoots et al, 2001;McCreery et al, 2002] This versatile facility [Stoots et al, 2001] has been used for fundamental and applied measurements in a variety of recent research programs:…”

Section: Not Matched Matchedmentioning

confidence: 99%

“…Transition in boundary layers with the Lehrstuhl für Strömungsmechanik of Uni. Erlangen, Germany [Becker et al, 2002] Flow phenomena in SNF canisters for a DoE EM Science project [McCreery et al, 2002] Flow fields around buildings for assessment of Bechtel R&D computer simulations for fate and transport of biological agents [McCreery et al, 2001] Effects of realistic surface roughness on turbomachinery flows with U. Idaho for the Air Force Office of Scientific Research [Budwig et al, 2001] Complex flows relating to advanced gas-cooled nuclear reactors for the DoE NERI program [McCreery et al, 2003] Additional studies now include examination of complex flows relating to supercritical water reactors for the DoE US/RoK I-NERI program and synthetic jet actuators by U. Wyoming for the Air Force Office of Scientific Research. Figure 29 demonstrates a conceptual design for an experimental model to be mounted in the test section of the MIR flow system.…”

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confidence: 99%

Initial Scaling Studies and Conceptual Thermal Fluids Experiments for the Prismatic NGNP Point Design

McEligot¹,

McCreery²

2004

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Table of contents iii Nomenclature iv Heated flow experiments Vertical tube Lower plenum Fluid dynamics experiments for lower plenum Concluding remarks References cited Bo* Jackson buoyancy parameter, Gr* / (Re Dh 3.425 Pr 0.8) d + wire diameter, d u / f, f friction factor, 2 b g c w / G 2 Gr* Grashof number based on heat flux, g q" wall D h 4 / (k 2) K v acceleration parameter, (b / V b 2) (dV b / dx) v Nu Nusselt number, h D h / k b Pr Prandtl number, c p /k q + heat flux, q" wall / (G c p) Re Reynolds number, 4 m / D ; Re Dh , based on hydraulic diameter, G D h / Ri overall Richardson number, g (1-2) H / (1 V b 2) Greek symbols volumetric coefficient of expansion,-(1/) (/ T) p dissipation of turbulence kinetic energy absolute viscosity kinematic viscosity, / density shear stress; w , wall shear stress Subscripts b evaluated at bulk or mixed-mean temperature (or enthalpy) D based on diameter DB Dittus-Boelter [1930] correlation Dh evaluated with hydraulic diameter f, fc forced convection i, in evaluated at inlet, entry j jet max maximum value p support post ref evaluated at reference conditions w, wall wall, evaluated at wall temperature Control Rod Drive Assembly Refueling Stand Pipe Control Rod Guide tubes

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Next Generation Nuclear Plant Research and Development Program Plan

MacDonald¹

2005

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The U.S Department of Energy (DOE) is conducting research and development (R&D) on the Very High Temperature Reactor (VHTR) design concept for the Next Generation Nuclear Plant (NGNP) Project. The reactor design will be a graphite moderated, thermal neutron spectrum reactor that will produce electricity and hydrogen in a highly efficient manner. The NGNP reactor core could be either a prismatic graphite block type core or a pebble bed core. Use of a liquid salt coolant is also being evaluated. The NGNP will use very high-burnup, low-enriched uranium, TRISO-coated fuel, and have a projected plant design service life of 60 years.The VHTR concept is considered to be the nearest-term reactor design that has the capability to efficiently produce hydrogen. The plant size, reactor thermal power, and core configuration will ensure passive decay heat removal without fuel damage or radioactive material releases during accidents.The objectives of the NGNP Project are to:Demonstrate a full-scale prototype VHTR that is commercially licensed by the U.S. Nuclear Regulatory Commission Demonstrate safe and economical nuclearassisted production of hydrogen and electricity.The DOE laboratories, led by the INL, will perform R&D that will be critical to the success of the NGNP, primarily in the areas of: High temperature gas reactor fuels behavior High temperature materials qualification Design methods development and validation Hydrogen production technologiesEnergy conversion.The current R&D work is addressing fundamental issues that are relevant to a variety of possible NGNP designs. This document describes the NGNP R&D planned and currently underway in the first three topic areas listed above. The NGNP Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is presented in Section 2, the NGNP Materials R&D Program Plan is presented in Section 3, and the NGNP Design Methods Development and Validation R&D Program is presented in Section 4. The DOE-funded hydrogen production [DOE 2004] and energy conversion technologies programs are described elsewhere.Sketch of how the NGNP might be configured to produce both electricity and hydrogen. iv Fuel Development and QualificationDevelopment and qualification of TRISO-coated low-enriched uranium fuel is a key R&D activity associated with the NGNP Program. The work is being conducted in accordance with the Technical Program Plan for the Advanced Gas Reactor Fuel Development and Qualification Program [Bell et al. 2003]. The AGR Program includes work on improving the kernel fabrication, coating, and compacting technologies, irradiation and accident testing of fuel specimens, and fuel performance and fission product transport modeling. The primary goal of these activities is to successfully demonstrate that TRISOcoated fuel can be fabricated to withstand the high temperatures, burnup, and power density requirements of a prismatic block type NGNP with an acceptable failure fraction. It is assumed that TRISO fuel that is successful in a block reactor will also be successful in pe...

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Convective processes in spent nuclear fuel canisters

Cited by 4 publications

References 0 publications

Scaling studies and conceptual experiment designs for NGNP CFD assessment

Scaling studies and conceptual experiment designs for NGNP CFD assessment

Initial Scaling Studies and Conceptual Thermal Fluids Experiments for the Prismatic NGNP Point Design

Next Generation Nuclear Plant Research and Development Program Plan

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