Effect of partial blockages in simulated LMFBR fuel assemblies

Fontana, Mario; Gnadt, P.A.; Kress, T.S.; MacPherson, R.E.; Parsly, L.F.; Wantland, J.L.

doi:10.2172/4357059

Cited by 11 publications

(4 citation statements)

References 12 publications

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“…The effect of partial blockages in simulated Liquid Metal Fast Breeder Reactor (LMFBR) fuel assemblies at the Thermal Hydraulic Out-of-Reactor Safety (THORS) facility was modeled using Pronghorn-SC (subchannel) under the NEAMS Thermal Fluids Technical Area. Information on the THORS facility and experiments can be found in [29,30,31].…”

Section: Status: Availablementioning

confidence: 99%

NEAMS Model Contributions in 2023 to the National Reactor Innovation Center Virtual Test Bed for Use by Industry and Other Stakeholders

Shemon,

Fang,

Hua

et al. 2023

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The U.S. Department of Energy (DOE) Office of Nuclear Energy's Advanced Modeling and Simulation (NEAMS) Program develops models of advanced reactor phenomena to demonstrate code applicability to challenging physics problems, drive code development through user assessment, and perform code verification and validation. Meanwhile, the U.S. DOE's National Reactor Innovation Center (NRIC) hosts an open-source website and associated GitHub repository called the Virtual Test Bed (VTB) on which computational models for advanced reactors are documented and shared with the reactor community.This work documents NEAMS efforts to support industry adoption of advanced modeling tools through contribution of 10 NEAMS models to the NRIC Virtual Test Bed including models for the High Temperature Test Facility (HTTF), TRISO fuel failure in a microreactor, and multiphysics models of a molten chloride fast reactor, among others. The open sharing of these models benefits the reactor community by providing "best practice" examples using NEAMS tools for advanced reactor physics problems. In particular, the HTTF model is being used for code validation and benchmarking activities. The microreactor and molten chloride fast reactor models are representative of analysis that may be useful for current candidates of DOME and LOTUS, NRIC's physical testbeds. This report summarizes and provides links to these new models and highlights their importance in developing and demonstrating advanced nuclear reactor systems.

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Section: Status: Availablementioning

confidence: 99%

NEAMS Model Contributions in 2023 to the National Reactor Innovation Center Virtual Test Bed for Use by Industry and Other Stakeholders

Shemon,

Fang,

Hua

et al. 2023

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show abstract

“…The wirewraps wound around the rods were started at the radial position, which was rotated counterclockwise by 60 degrees azimuthally on the bundle bottom plane. The angle is related with a radial Table 1 THORS bundle 2B test conditions (Fontana et al, 1973 distribution of the flow and temperature over the sub-channels, because the inter-mixing among sub-channels is largely influenced by the appearance of the wire-wrap spacers inside a sub-channel. The sub-channels were divided axially into 36 equally sized nodes (1-in./node) in the MATRA-LMR-FB input.…”

Section: Matra-lmr-fb Input Modelingmentioning

confidence: 99%

“…The qualification effort for such a case should be enlarged. In this respect, the 'THORS bundle 2B' test with a 19-rod bundle (Fontana et al, 1973;Han, 1977) was selected to assess the MATRA-LMR-FB for the inlet blockage case. The test results, however, could not provide enough detailed information on the flow and temperature distributions established over the sub-channels to assess the MATRA-LMR-FB prediction capability.…”

Section: Introductionmentioning

confidence: 99%

MATRA-LMR-FB assessment with THORS bundle 2B experiments

Chang

Jin

Choi

et al. 2015

Nuclear Engineering and Design

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“…Loss of electric power to the sodium pumps causes a relatively slow flow coastdown (~10-s) for the entire core. 22 Blockage of a subassembly inlet or an element flow channel can cause local loss of coolant 71 in ~1 s or less. A third postulated loss of coolant accident, blanketing of an element by fis"ion gas released from a cladding failure in an adjacent element, ' 2 can occur in milliseconds.…”

Section: Loss Of Coolantmentioning

confidence: 99%

Experience related to the safety of advanced LMFBR fuel elements

Kerrisk¹

1975

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Effect of partial blockages in simulated LMFBR fuel assemblies

Cited by 11 publications

References 12 publications

NEAMS Model Contributions in 2023 to the National Reactor Innovation Center Virtual Test Bed for Use by Industry and Other Stakeholders

NEAMS Model Contributions in 2023 to the National Reactor Innovation Center Virtual Test Bed for Use by Industry and Other Stakeholders

MATRA-LMR-FB assessment with THORS bundle 2B experiments

Experience related to the safety of advanced LMFBR fuel elements

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