Fabrication, inspection, and test plan for the Advanced Test Reactor (ATR) Mixed-Oxide (MOX) fuel irradiation project

Wachs, G W

doi:10.2172/565642

Title: Fabrication, inspection, and test plan for the Advanced Test Reactor (ATR) Mixed-Oxide (MOX) fuel irradiation project

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Abstract

The Department of Energy (DOE) Fissile Materials Disposition Materials Disposition Program (FMDP) has announced that reactor irradiation of MOX fuel is one of the preferred alternatives for disposal of surplus weapons-usable plutonium (Pu). MOX fuel has been utilized domestically in test reactors and on an experimental basis in a number of Commercial Light Water Reactors (CLWRs). Most of this experience has been with Pu derived from spent low enriched uranium (LEU) fuel, known as reactor grade (RG) Pu. The MOX fuel test will be irradiated in the ATR to provide preliminary data to demonstrate that the unique properties of surplus weapons-derived or weapons-grade (WG) plutonium (Pu) do not compromise the applicability of this MOX experience base. In addition, the test will contribute experience with irradiation of gallium-containing fuel to the data base required for resolution of generic CLWR fuel design issues (ORNL/MD/LTR-76). This Fabrication, Inspection, and Test Plan (FITP) is a level 2 document as defined in the FMDP LWR MOX Fuel Irradiation Test Project Plan (ORNL/MD/LTR-78).

Authors:: Wachs, G W

Publication Date:: Sat Nov 01 00:00:00 EST 1997

Research Org.:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE, Washington, DC (United States)

OSTI Identifier:: 565642

Report Number(s):: INEEL/EXT-97-01066
ON: DE98050619; TRN: 98:002560

DOE Contract Number:: AC07-94ID13223

Resource Type:: Technical Report

Resource Relation:: Other Information: PBD: Nov 1997

Country of Publication:: United States

Language:: English

Subject:: 22 NUCLEAR REACTOR TECHNOLOGY; ATR REACTOR; MIXED OXIDE FUELS; PLUTONIUM; FABRICATION; INSPECTION; EXPERIMENT PLANNING; IRRADIATION

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                    Wachs, G W. Fabrication, inspection, and test plan for the Advanced Test Reactor (ATR) Mixed-Oxide (MOX) fuel irradiation project.  United States: N. p., 1997. 
        Web.  doi:10.2172/565642.

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                    Wachs, G W. Fabrication, inspection, and test plan for the Advanced Test Reactor (ATR) Mixed-Oxide (MOX) fuel irradiation project.  United States.  https://doi.org/10.2172/565642

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                    Wachs, G W. 1997.  
        "Fabrication, inspection, and test plan for the Advanced Test Reactor (ATR) Mixed-Oxide (MOX) fuel irradiation project".  United States.  https://doi.org/10.2172/565642.  https://www.osti.gov/servlets/purl/565642.

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@article{osti_565642,

  title        = {Fabrication, inspection, and test plan for the Advanced Test Reactor (ATR) Mixed-Oxide (MOX) fuel irradiation project},

  author       = {Wachs, G W},

  abstractNote = {The Department of Energy (DOE) Fissile Materials Disposition Materials Disposition Program (FMDP) has announced that reactor irradiation of MOX fuel is one of the preferred alternatives for disposal of surplus weapons-usable plutonium (Pu). MOX fuel has been utilized domestically in test reactors and on an experimental basis in a number of Commercial Light Water Reactors (CLWRs). Most of this experience has been with Pu derived from spent low enriched uranium (LEU) fuel, known as reactor grade (RG) Pu. The MOX fuel test will be irradiated in the ATR to provide preliminary data to demonstrate that the unique properties of surplus weapons-derived or weapons-grade (WG) plutonium (Pu) do not compromise the applicability of this MOX experience base. In addition, the test will contribute experience with irradiation of gallium-containing fuel to the data base required for resolution of generic CLWR fuel design issues (ORNL/MD/LTR-76). This Fabrication, Inspection, and Test Plan (FITP) is a level 2 document as defined in the FMDP LWR MOX Fuel Irradiation Test Project Plan (ORNL/MD/LTR-78).},

  doi          = {10.2172/565642},

  url          = {https://www.osti.gov/biblio/565642},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {Sat Nov 01 00:00:00 EST 1997},

  month        = {Sat Nov 01 00:00:00 EST 1997}

}

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