Development of Neutron Absorbers to Support Disposal of DOE SNF

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The National Spent Nuclear Fuel Program, located at the Idaho National Engineering and Environmental Laboratory, coordinates and integrates national efforts in management and disposal of U.S. Department of Energy (DOE)- owned . These management functions include using the DOE standardized canister for packaging, storage, treatment, transport, and long-term disposal. Nuclear criticality control measures are needed in these canisters because of the enrichment and total quantity of fissile material in some types of the DOE spent nuclear fuel. This paper will report the test results of one alloy heat from a metallurgical development program that is developing nickelchromium- molybdenum-gadolinium alloys for ... continued below

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Hurt, William Lon; Mizia, Ronald Eugene; Lister, T. E.; Pinhero, P. J.; Robino, C. V. & Dupont, J. N. March 1, 2003.

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Description

The National Spent Nuclear Fuel Program, located at the Idaho National Engineering and Environmental Laboratory, coordinates and integrates national efforts in management and disposal of U.S. Department of Energy (DOE)- owned . These management functions include using the DOE standardized canister for packaging, storage, treatment, transport, and long-term disposal. Nuclear criticality control measures are needed in these canisters because of the enrichment and total quantity of fissile material in some types of the DOE spent nuclear fuel. This paper will report the test results of one alloy heat from a metallurgical development program that is developing nickelchromium- molybdenum-gadolinium alloys for nuclear criticality control in the DOE standardized canister. Gadolinium has been chosen as the neutron absorption alloying element due to its high thermal neutron absorption cross section. The microstructure, mechanical properties, and corrosion resistance of various alloys will be presented. These corrosion resistant, structural alloys can be used to fabricate components of spent nuclear fuel storage racks, storage canisters and internal structural baskets, and transportation cask internals. The focus of this work is to qualify these materials for American Society of Mechanical Engineers code qualification and acceptance in the Yucca Mountain Repository.

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  • 2003 International High-Level Radioactive Waste Management Conference,Las Vegas, NV,03/30/2003,04/03/2003

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  • Report No.: INEEL/CON-02-01201
  • Grant Number: DE-AC07-99ID-13727
  • Office of Scientific & Technical Information Report Number: 910769
  • Archival Resource Key: ark:/67531/metadc879111

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  • March 1, 2003

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  • Sept. 22, 2016, 2:13 a.m.

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  • Nov. 7, 2016, 7:37 p.m.

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Hurt, William Lon; Mizia, Ronald Eugene; Lister, T. E.; Pinhero, P. J.; Robino, C. V. & Dupont, J. N. Development of Neutron Absorbers to Support Disposal of DOE SNF, article, March 1, 2003; [Idaho Falls, Idaho]. (digital.library.unt.edu/ark:/67531/metadc879111/: accessed August 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.