Developing Capability for Hydride Moderator Manufacturing to Facilitate Thermal Spectrum Design Options

Hu, Xunxiang; Silva, Chinthaka; Terrani, Kurt A.

doi:10.2172/1885405

Title: Developing Capability for Hydride Moderator Manufacturing to Facilitate Thermal Spectrum Design Options

Full Record
Other Related Research

Abstract

This report provides a summary of efforts to develop the capability to fabricate massive crack-free yttrium hydride samples to support thermal spectrum design options for the Transformational Challenge Reactor (TCR) in FY2019. The challenges to fabricating massive, crack-free single-phase yttrium hydride are discussed. By using a modified static hydriding system, we have successfully demonstrated the fabrication of crack-free yttrium hydride, guided by the well-established thermodynamics of the binary yttriumhydrogen system. The presence of α-phase yttrium in the fabricated yttrium hydride necessitates employing temperature-pressure isochore cooling at the end of the hydriding process. Thus, a fully programmable hydriding system with continuous hydrogen partial pressure and flow control coordinated with precise temperature control has been designed to facilitate processing of massive, crack-free metal hydrides with the desired H/Y atom ratio. The new system is capable of fabricating yttrium hydride samples that will be used to establish a complete database of yttrium hydride to support the application of yttrium hydride as a high-performance moderator material in the TCR and other nuclear systems.

Authors:

^[1];

^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Publication Date:: 2019-09-27

Research Org.:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1885405

Report Number(s):: ORNL/SPR-2019/1340

DOE Contract Number:: AC05-00OR22725

Resource Type:: Technical Report

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE

Citation Formats


                    Hu, Xunxiang, Silva, Chinthaka, and Terrani, Kurt A. Developing Capability for Hydride Moderator Manufacturing to Facilitate Thermal Spectrum Design Options.  United States: N. p., 2019. 
        Web.  doi:10.2172/1885405.

Copy to clipboard


                    Hu, Xunxiang, Silva, Chinthaka, & Terrani, Kurt A. Developing Capability for Hydride Moderator Manufacturing to Facilitate Thermal Spectrum Design Options.  United States.  https://doi.org/10.2172/1885405

Copy to clipboard


                    Hu, Xunxiang, Silva, Chinthaka, and Terrani, Kurt A. 2019.  
        "Developing Capability for Hydride Moderator Manufacturing to Facilitate Thermal Spectrum Design Options".  United States.  https://doi.org/10.2172/1885405.  https://www.osti.gov/servlets/purl/1885405.

Copy to clipboard


                    
@article{osti_1885405,

  title        = {Developing Capability for Hydride Moderator Manufacturing to Facilitate Thermal Spectrum Design Options},

  author       = {Hu, Xunxiang and Silva, Chinthaka and Terrani, Kurt A.},

  abstractNote = {This report provides a summary of efforts to develop the capability to fabricate massive crack-free yttrium hydride samples to support thermal spectrum design options for the Transformational Challenge Reactor (TCR) in FY2019. The challenges to fabricating massive, crack-free single-phase yttrium hydride are discussed. By using a modified static hydriding system, we have successfully demonstrated the fabrication of crack-free yttrium hydride, guided by the well-established thermodynamics of the binary yttriumhydrogen system. The presence of α-phase yttrium in the fabricated yttrium hydride necessitates employing temperature-pressure isochore cooling at the end of the hydriding process. Thus, a fully programmable hydriding system with continuous hydrogen partial pressure and flow control coordinated with precise temperature control has been designed to facilitate processing of massive, crack-free metal hydrides with the desired H/Y atom ratio. The new system is capable of fabricating yttrium hydride samples that will be used to establish a complete database of yttrium hydride to support the application of yttrium hydride as a high-performance moderator material in the TCR and other nuclear systems.},

  doi          = {10.2172/1885405},

  url          = {https://www.osti.gov/biblio/1885405},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {2019},

  month        = {9}

}

Copy to clipboard

Technical Report:

View Technical Report

https://doi.org/10.2172/1885405

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

Fabrication of yttrium hydride for high-temperature moderator application

Journal Article Hu, Xunxiang; Schappel, Danny; Silva, Chinthaka; ... - Journal of Nuclear Materials

We report given the superior thermal stability and highly attainable hydrogen density, yttrium hydride is an excellent high-temperature moderator material in advanced thermal neutron spectrum reactors that require small core volumes. Large-scale, crack-free, bulk yttrium hydride is in high demand; however, fabrication of yttrium hydride is challenging and has not been demonstrated for nearly half century. The associated challenges are discussed herein. In response to these challenges, a hydriding system was designed and constructed at Oak Ridge National Laboratory and was used to successfully fabricate crack-free yttrium hydride in complex geometries at large scales. This was accomplished by precisely controllingmore »« less
Cited by 19
https://doi.org/10.1016/j.jnucmat.2020.152335

Full Text Available
Physical and Thermomechanical Properties of Yttrium Hydride from Large Scale Bulk Metal Hydriding Furnace

Technical Report Hu, Xunxiang; Schappel, Danny; Trofimov, Artem; ...

Given the superior thermal stability and highly attainable hydrogen density, yttrium hydride is an excellent high-temperature moderator material in advanced thermal neutron spectrum reactors that require small core volumes. Yttrium hydride has been selected as the moderator material for the Transformational Challenge Reactor, which was launched at Oak Ridge National Laboratory (ORNL) in 2019. However, fabrication of large-scale crack-free yttrium hydride is challenging and very limited efforts have been committed to the characterization of bulk yttrium hydride in response to the need to establish a complete database of the thermomechanical properties of YHx. In this report, the challenges associated withmore »« less
https://doi.org/10.2172/1866716

Full Text Available
Technology Enabling Zero-EPZ Micro Modular Reactors: Fabrication of Zirconium Hydride with Controlled Hydrogen Loading

Technical Report Hu, Xunxiang; Mouche, Peter; Schappel, Danny; ...

This report completes Milestone M2.2.2 - ZrH pellet fabricated with controlled hydride loading: ZrH1.5±0.1 single phase pellets fabricated with controlled and thermally stable hydride loading. Hydrogen content to be quantified and single-phase confirmed by X-ray diffraction. In this milestone, we report the successful fabrication of delta-phase zirconium hydride pellets using the ORNL bulk metal hydriding system. The successful deployment of zirconium hydride moderator in advanced reactors requires development of a consistent and affordable production pathway along with implementation of a hydrogen retention solution throughout the reactor life. Fabrication of delta-phase zirconium hydride is challenging since the absorption of a largemore »« less
https://doi.org/10.2172/1879976

Full Text Available
Air oxidation of yttrium hydride as a high temperature moderator for thermal neutron spectrum fission reactors

Journal Article Kane, Kenneth; Hu, Xunxiang; Stack, Padraig; ... - Journal of Nuclear Materials

Yttrium hydride (YH_x) is an attractive moderator material for thermal neutron spectrum fission reactors requiring a small reactor core volume and has been selected as the neutron moderator for the Transformational Challenge Reactor (TCR), an advanced gas-cooled microreactor. Before YH_x can be used in this application, it is important to understand the material response to off-normal conditions. In the present study, 550–650 °C isothermal dry air oxidation was performed to simulate a depressurized loss of force circulation (DLOFC) event. The oxidation was performed using thermogravimetric analysis (TGA) on bulk crack-free YHx coupons. Oxidation studies were also performed on Y couponsmore »« less
https://doi.org/10.1016/j.jnucmat.2021.153166

Full Text Available
Transformational challenge reactor analysis to inform preconceptual core design decisions: Sensitivity study of transient analysis in a hydride-moderated microreactor

Journal Article Kile, Robert; Wysocki, Aaron; Betzler, Benjamin; ... - Nuclear Engineering and Design

The Transformational Challenge Reactor (TCR) program aims to demonstrate a revolutionary design approach enabled by advanced manufacturing and data analytics in the design of nuclear reactors. This article discusses scoping analyses of preconceptual designs to inform TCR design decisions and the evaluation of sensitivities and uncertainties on postulated transient scenarios. The applicability of the systems codes TRACE and RELAP5-3D to TCR transient analysis are examined, and RELAP5-3D models are used to examine the transient response of two candidate core designs at multiple power levels. Then, the uncertainty quantification code RAVEN is used to quantify the effect of several design parametersmore »« less
https://doi.org/10.1016/j.nucengdes.2021.111122

Full Text Available

Similar Records