HDG-1 Graphite Preirradiation Data Package Report

Rohrbaugh, David T; Windes, William E; Swank, W David

Title: HDG-1 Graphite Preirradiation Data Package Report

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Abstract

This report documents all pre-irradiation examination material-property measurement data for graphite specimens that are going to be used within the first high dose graphite (HDG) -1 irradiation capsule. The two new HDG capsules signify a major change to the AGC Experiment. HDG-1 and HDG-2 will replace the last two Advanced Graphite Creep (AGC) capsules (AGC-5 and AGC-6) which were designed to irradiate graphite at the extreme upper operational temperatures for a very-high-temperature reactor (VHTR) design, 1100°C. These very high temperature AGC-5 and AGC-6 capsules have been repurposed to re-irradiated specimens (from AGC-2, AGC-3, and AGC-4) at the lower temperatures of 600°C and 800°C. HDG-1 will be irradiated at 600°C and HDG-2 will be irradiated at 800°C. By re-irradiating the previous AGC specimens a total maximum neutron dose of around 15 dpa (displacements per atom) can be achieved for all major graphite grades at irradiation temperatures of 600°C and 800°C. Specimens in the HDG-1 capsule are made up of previously irradiated specimens from the AGC-2 capsule and unirradiated specimens prepared for the now discontinued AGC-5 capsule. Utilizing the irradiated specimens, a maximum neutron dose of around 15 dpa is anticipated. These new maximum dose levels will provide irradiated material property datamore »« less

Authors:

Rohrbaugh, David T ^[1];

^[1];

^[1]

Idaho National Laboratory

Publication Date:: 2020-08-05

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

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

OSTI Identifier:: 1668756

Report Number(s):: INL/EXT-20-59175-Rev000

DOE Contract Number:: DE-AC07-05ID14517

Resource Type:: Program Document

Country of Publication:: United States

Language:: English

Subject:: 11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Graphite Preirradiation; High Dose Graphite

Citation Formats


                    Rohrbaugh, David T, Windes, William E, and Swank, W David. HDG-1 Graphite Preirradiation Data Package Report.  United States: N. p., 2020. 
        Web.

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                    Rohrbaugh, David T, Windes, William E, & Swank, W David. HDG-1 Graphite Preirradiation Data Package Report.  United States.

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                    Rohrbaugh, David T, Windes, William E, and Swank, W David. 2020.  
        "HDG-1 Graphite Preirradiation Data Package Report".  United States.  https://www.osti.gov/servlets/purl/1668756.

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@article{osti_1668756,

  title        = {HDG-1 Graphite Preirradiation Data Package Report},

  author       = {Rohrbaugh, David T and Windes, William E and Swank, W David},

  abstractNote = {This report documents all pre-irradiation examination material-property measurement data for graphite specimens that are going to be used within the first high dose graphite (HDG) -1 irradiation capsule. The two new HDG capsules signify a major change to the AGC Experiment. HDG-1 and HDG-2 will replace the last two Advanced Graphite Creep (AGC) capsules (AGC-5 and AGC-6) which were designed to irradiate graphite at the extreme upper operational temperatures for a very-high-temperature reactor (VHTR) design, 1100°C. These very high temperature AGC-5 and AGC-6 capsules have been repurposed to re-irradiated specimens (from AGC-2, AGC-3, and AGC-4) at the lower temperatures of 600°C and 800°C. HDG-1 will be irradiated at 600°C and HDG-2 will be irradiated at 800°C. By re-irradiating the previous AGC specimens a total maximum neutron dose of around 15 dpa (displacements per atom) can be achieved for all major graphite grades at irradiation temperatures of 600°C and 800°C. Specimens in the HDG-1 capsule are made up of previously irradiated specimens from the AGC-2 capsule and unirradiated specimens prepared for the now discontinued AGC-5 capsule. Utilizing the irradiated specimens, a maximum neutron dose of around 15 dpa is anticipated. These new maximum dose levels will provide irradiated material property data over a total neutron dose range of 1-15 dpa at a temperature of 600°C when combined with the previous AGC-1 and AGC-2 irradiation data. This will provide quantitative data necessary for predicting the irradiation behavior and operating performance of new nuclear graphite grades for use within high temperature reactor designs. Similar to previous AGC test trains, HDG-1 includes the major graphite grades (IG-110, NBG-17, NBG-18, PCEA, and 2114) as well as adding the very fine-grain grade IG-430 which is of interest to the Molten Salt Reactor (MSR) designs. Also new to the HDG-1 capsule are 90 smaller geometry specimens designated as pencil specimens. These specimens take up only one third the space of a standard creep size specimen. This increased number of specimens will enhance property measurement statistics because they will provide 3 times the control specimen data at a position that would otherwise only have a single measurement.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/1668756},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {2020},

  month        = {8}

}

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