Characteristics of Fuel Articles for Irradiation Testing in INL-TREAT and MIT-NRL

Gokul Vasudevamurthy; Nicholas R. Brown; Robert F. Kile; Danny P. Schappel; Kory D. Linton

doi:10.2172/1606752

Characteristics of Fuel Articles for Irradiation Testing in INL-TREAT and MIT-NRL

Gokul Vasudevamurthy, Nicholas R. Brown, Robert F. Kile, Danny P. Schappel, Kory D. Linton

Advanced Fuel Fabrication and Instrument

Research output: Book/Report › Commissioned report

Abstract

To obtain valuable data that will help in the design and commissioning of the Transformational Challenge Reactor, a series of graded, increasingly complex irradiation tests are planned that will demonstrate the feasibility of advanced manufactured reactor core components. In the first irradiation test, conventionally- fabricated uranium nitride tristructural isotropic (UN TRISO) fuel kernels will be embedded into compacts that are fabricated using advanced manufacturing methods. These compacts are to be irradiated at Massachusetts Institute of Technology’s Nuclear Reactor Laboratory and Idaho National Laboratory’s Transient Reactor Test Facility. This report presents the characteristics of the proposed samples and experiments.

Original language	English
Place of Publication	United States
DOIs	https://doi.org/10.2172/1606752
State	Published - 2019

Keywords

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

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10.2172/1606752

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abstract = "To obtain valuable data that will help in the design and commissioning of the Transformational Challenge Reactor, a series of graded, increasingly complex irradiation tests are planned that will demonstrate the feasibility of advanced manufactured reactor core components. In the first irradiation test, conventionally- fabricated uranium nitride tristructural isotropic (UN TRISO) fuel kernels will be embedded into compacts that are fabricated using advanced manufacturing methods. These compacts are to be irradiated at Massachusetts Institute of Technology{\textquoteright}s Nuclear Reactor Laboratory and Idaho National Laboratory{\textquoteright}s Transient Reactor Test Facility. This report presents the characteristics of the proposed samples and experiments.",

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AU - Vasudevamurthy, Gokul

AU - Brown, Nicholas R.

AU - Kile, Robert F.

AU - Schappel, Danny P.

AU - Linton, Kory D.

PY - 2019

Y1 - 2019

N2 - To obtain valuable data that will help in the design and commissioning of the Transformational Challenge Reactor, a series of graded, increasingly complex irradiation tests are planned that will demonstrate the feasibility of advanced manufactured reactor core components. In the first irradiation test, conventionally- fabricated uranium nitride tristructural isotropic (UN TRISO) fuel kernels will be embedded into compacts that are fabricated using advanced manufacturing methods. These compacts are to be irradiated at Massachusetts Institute of Technology’s Nuclear Reactor Laboratory and Idaho National Laboratory’s Transient Reactor Test Facility. This report presents the characteristics of the proposed samples and experiments.

AB - To obtain valuable data that will help in the design and commissioning of the Transformational Challenge Reactor, a series of graded, increasingly complex irradiation tests are planned that will demonstrate the feasibility of advanced manufactured reactor core components. In the first irradiation test, conventionally- fabricated uranium nitride tristructural isotropic (UN TRISO) fuel kernels will be embedded into compacts that are fabricated using advanced manufacturing methods. These compacts are to be irradiated at Massachusetts Institute of Technology’s Nuclear Reactor Laboratory and Idaho National Laboratory’s Transient Reactor Test Facility. This report presents the characteristics of the proposed samples and experiments.

KW - 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

U2 - 10.2172/1606752

DO - 10.2172/1606752

M3 - Commissioned report

BT - Characteristics of Fuel Articles for Irradiation Testing in INL-TREAT and MIT-NRL

CY - United States

ER -

Characteristics of Fuel Articles for Irradiation Testing in INL-TREAT and MIT-NRL

Abstract

Keywords

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