Neutron moderation modules

Miao, Yinbin; Stauff, Nicolas E.; Bhattacharya, Sumit; Yacout, Abdellatif M.; Kim, Taek K.

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Title: Neutron moderation modules

Abstract

Provided herein is a neutron moderation module and a thermal-neutron nuclear micro-reactor.

Inventors:: Miao, Yinbin; Stauff, Nicolas E.; Bhattacharya, Sumit; Yacout, Abdellatif M.; Kim, Taek K.

Issue Date:: 2022-09-13

Research Org.:: Argonne National Laboratory (ANL), Argonne, IL (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1925107

Patent Number(s):: 11443858

Application Number:: 16/926,132

Assignee:: UChicago Argonne, LLC (Chicago, IL)

Patent Classifications (CPCs):: G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS

G - PHYSICS G21 - NUCLEAR PHYSICS G21D - NUCLEAR POWER PLANT

Show more

G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
G21C15/08 - from moderating material
G21C3/07 - characterised by their material, e.g. alloys
G21C3/326 - comprising fuel elements of different composition
G21C5/12 - characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator {

G - PHYSICS G21 - NUCLEAR PHYSICS G21D - NUCLEAR POWER PLANT
G21D5/02 - Reactor and engine structurally combined, e.g. portable

Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
Y02E30/00 - Energy generation of nuclear origin

Show less

DOE Contract Number:: AC02-06CH11357

Resource Type:: Patent

Resource Relation:: Patent File Date: 07/10/2020

Country of Publication:: United States

Language:: English

Subject:: 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS

Citation Formats


                    Miao, Yinbin, Stauff, Nicolas E., Bhattacharya, Sumit, Yacout, Abdellatif M., and Kim, Taek K. Neutron moderation modules.  United States: N. p., 2022. 
        Web.

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                    Miao, Yinbin, Stauff, Nicolas E., Bhattacharya, Sumit, Yacout, Abdellatif M., & Kim, Taek K. Neutron moderation modules.  United States.

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                    Miao, Yinbin, Stauff, Nicolas E., Bhattacharya, Sumit, Yacout, Abdellatif M., and Kim, Taek K. Tue .  
        "Neutron moderation modules".  United States.  https://www.osti.gov/servlets/purl/1925107.

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@article{osti_1925107,

  title        = {Neutron moderation modules},

  author       = {Miao, Yinbin and Stauff, Nicolas E. and Bhattacharya, Sumit and Yacout, Abdellatif M. and Kim, Taek K.},

  abstractNote = {Provided herein is a neutron moderation module and a thermal-neutron nuclear micro-reactor.},

  doi          = {},

  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {2022},

  month        = {9}

}

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Similar Records

Title: Neutron moderation modules

Abstract

Citation Formats

Ultra-thin Al2O3 films grown by atomic layer deposition for corrosion protection of copper journal, January 2014

Interlaboratory round robin study on axial tensile properties of SiC-SiC CMC tubular test specimens journal, May 2018

Tritium/hydrogen barrier development journal, March 1995

Handbook of SiC properties for fuel performance modeling journal, September 2007

Hydrides as neutron moderator and reflector materials journal, February 1971

High Temperature Ceramic Composition for Hydrogen Retention patent, January 1974

ECRIX-H experiment: Synthesis of post-irradiation examinations and simulations journal, August 2011

Thermophysical property correlations for the niobium-1% zirconium alloy journal, October 1990

Innovative SiC/SiC Composite for Nuclear Applications journal, January 2013

A brief review of atomic layer deposition: from fundamentals to applications journal, June 2014

Uranium–zirconium hydride fuel properties journal, August 2009

Lattice and Grain Boundary Diffusion in Polycrystals journal, January 1961

Nb-Base FS-85 Alloy as a Candidate Structural Material for Space Reactor Applications: Effects of Thermal Aging journal, February 2009

Summary Report of htre no. 3 Nuclear Excursion report, January 1965

Coating of Nuclear Fuel Cladding Materials, Method for Coating Nuclear Fuel Cladding Materials patent-application, March 2015

Moderator-fuel element patent, September 1967

Transport property correlations for the niobium-1% zirconium alloy journal, October 1990

Characterization of less common nitrides as potential permeation barriers journal, February 2019

Pressure-Temperature-Composition Relationships of the Yttrium-Hydrogen System journal, January 1962

Hydrogen gas permeation through amorphous and partially crystallized Fe40Ni38Mo4B18 journal, August 2012

Hydrogen Permeation Measurements on Alumina: Hydrogen Permeation Measurements on Alumina journal, December 2004

Permeation barrier layer patent, February 2014

Research on High-Temperature Aerospace Materials at NASA Glenn Research Center journal, April 2013

Void Swelling in Electron Irradiated Hastelloy-X journal, April 1978

The formation of hydrogen permeation barriers on steels by aluminising journal, May 1991

Observation and possible mechanism of irradiation induced creep in ceramics journal, March 2013

Gamma Titanium Aluminide Alloys book, January 2011

Hydrogen permeation resistance of plasma-sprayed Al2O3 and Al2O3–13wt.% TiO2 ceramic coatings on austenitic stainless steel journal, May 2003

Technical challenges and future direction for high-efficiency metal hydride thermal energy storage systems journal, March 2016

Voids in vanadium, niobium and molybdenum by fast neutron irradiation at high temperatures journal, May 1971

Hydrogen Permeation Characteristics of TiN-Coated Stainless Steels journal, June 2015

Method for Cladding Yttrium Hydride and Yttrium Base Alloy Hydrides patent, October 1966

Method of making ZrH fuel element patent, January 1978

Reducing Irradiation Damage in a Long-Life Fast Reactor with Spectral Softening journal, June 2018

Hydrogen transport and solubility in 316L and 1.4914 steels for fusion reactor applications journal, December 1988

A review of refractory metal alloys and mechanically alloyed-oxide dispersion strengthened steels for space nuclear power systems journal, April 2005

Tritium permeation barriers for fusion technology journal, March 1995

The UZrHx alloy: Its properties and use in TRIGA fuel journal, April 1981

Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding journal, November 2015

Ultra-thin Al₂O₃ films grown by atomic layer deposition for corrosion protection of copper
journal, January 2014

Interlaboratory round robin study on axial tensile properties of SiC-SiC CMC tubular test specimens
journal, May 2018

Tritium/hydrogen barrier development
journal, March 1995

Handbook of SiC properties for fuel performance modeling
journal, September 2007

Hydrides as neutron moderator and reflector materials
journal, February 1971

High Temperature Ceramic Composition for Hydrogen Retention
patent, January 1974

ECRIX-H experiment: Synthesis of post-irradiation examinations and simulations
journal, August 2011

Thermophysical property correlations for the niobium-1% zirconium alloy
journal, October 1990

Innovative SiC/SiC Composite for Nuclear Applications
journal, January 2013

A brief review of atomic layer deposition: from fundamentals to applications
journal, June 2014

Uranium–zirconium hydride fuel properties
journal, August 2009

Lattice and Grain Boundary Diffusion in Polycrystals
journal, January 1961

Nb-Base FS-85 Alloy as a Candidate Structural Material for Space Reactor Applications: Effects of Thermal Aging
journal, February 2009

Summary Report of htre no. 3 Nuclear Excursion
report, January 1965

Coating of Nuclear Fuel Cladding Materials, Method for Coating Nuclear Fuel Cladding Materials
patent-application, March 2015

Moderator-fuel element
patent, September 1967

Transport property correlations for the niobium-1% zirconium alloy
journal, October 1990

Characterization of less common nitrides as potential permeation barriers
journal, February 2019

Pressure-Temperature-Composition Relationships of the Yttrium-Hydrogen System
journal, January 1962

Hydrogen gas permeation through amorphous and partially crystallized Fe40Ni38Mo4B18
journal, August 2012

Hydrogen Permeation Measurements on Alumina: Hydrogen Permeation Measurements on Alumina
journal, December 2004

Permeation barrier layer
patent, February 2014

Research on High-Temperature Aerospace Materials at NASA Glenn Research Center
journal, April 2013

Void Swelling in Electron Irradiated Hastelloy-X
journal, April 1978

The formation of hydrogen permeation barriers on steels by aluminising
journal, May 1991

Observation and possible mechanism of irradiation induced creep in ceramics
journal, March 2013

Gamma Titanium Aluminide Alloys
book, January 2011

Hydrogen permeation resistance of plasma-sprayed Al2O3 and Al2O3–13wt.% TiO2 ceramic coatings on austenitic stainless steel
journal, May 2003

Technical challenges and future direction for high-efficiency metal hydride thermal energy storage systems
journal, March 2016

Voids in vanadium, niobium and molybdenum by fast neutron irradiation at high temperatures
journal, May 1971

Hydrogen Permeation Characteristics of TiN-Coated Stainless Steels
journal, June 2015

Method for Cladding Yttrium Hydride and Yttrium Base Alloy Hydrides
patent, October 1966

Method of making ZrH fuel element
patent, January 1978

Reducing Irradiation Damage in a Long-Life Fast Reactor with Spectral Softening
journal, June 2018

Hydrogen transport and solubility in 316L and 1.4914 steels for fusion reactor applications
journal, December 1988

A review of refractory metal alloys and mechanically alloyed-oxide dispersion strengthened steels for space nuclear power systems
journal, April 2005

Tritium permeation barriers for fusion technology
journal, March 1995

The UZrHx alloy: Its properties and use in TRIGA fuel
journal, April 1981

Stress analysis and probabilistic assessment of multi-layer SiC-based accident tolerant nuclear fuel cladding
journal, November 2015