AGC 3 Irradiated Material Properties Analysis

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

Title: AGC 3 Irradiated Material Properties Analysis

Full Record
Other Related Research

Abstract

This report documents the analysis of the irradiated material property data from the Advanced Graphite Creep (AGC)-3 graphite specimens. This is the third in a series of six irradiation test trains planned as part of the AGC experiment to fully characterize the neutron irradiation effects and radiation creep behavior of current nuclear graphite grades. The AGC-3 capsule was irradiated in the Idaho National Laboratory Advanced Test Reactor at a nominal temperature of 800°C, beginning with irradiation Cycle 152B on November 28, 2012 and ending with Cycle 155B on April 12, 2014, with a total received dose range of 0.9–3.7 dpa. Larger creep and control specimens located more centrally in the capsule received a dose of 1.0 – 3.7 dpa. AGC-3 was designed to provide irradiation conditions similar to AGC-1 and AGC-2 capsules (similar graphite grades tested, specimen dimensions, mechanical loading conditions) but at a different nominal irradiation temperature of 800°C. AGC-3 was irradiated for a short duration to provide material property values at lower dose levels. AGC-4 will have a longer duration and provide material property values at higher dose levels. After irradiation, material property and dimensional strain measurements were conducted on all AGC-3 specimens (from 11 nuclear graphite grades)more »« less

Authors:

^[1]; Rohrbaugh, David T ^[1];

^[1]

Idaho National Laboratory

Publication Date:: 2020-04-29

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

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

OSTI Identifier:: 1774792

Report Number(s):: INL/EXT-20-58029-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; Advanced Graphite Creep; high temperature reactor

Citation Formats


                    Windes, William E, Rohrbaugh, David T, and Swank, W David. AGC 3 Irradiated Material Properties Analysis.  United States: N. p., 2020. 
        Web.

Copy to clipboard


                    Windes, William E, Rohrbaugh, David T, & Swank, W David. AGC 3 Irradiated Material Properties Analysis.  United States.

Copy to clipboard


                    Windes, William E, Rohrbaugh, David T, and Swank, W David. 2020.  
        "AGC 3 Irradiated Material Properties Analysis".  United States.  https://www.osti.gov/servlets/purl/1774792.

Copy to clipboard


                    
@article{osti_1774792,

  title        = {AGC 3 Irradiated Material Properties Analysis},

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

  abstractNote = {This report documents the analysis of the irradiated material property data from the Advanced Graphite Creep (AGC)-3 graphite specimens. This is the third in a series of six irradiation test trains planned as part of the AGC experiment to fully characterize the neutron irradiation effects and radiation creep behavior of current nuclear graphite grades. The AGC-3 capsule was irradiated in the Idaho National Laboratory Advanced Test Reactor at a nominal temperature of 800°C, beginning with irradiation Cycle 152B on November 28, 2012 and ending with Cycle 155B on April 12, 2014, with a total received dose range of 0.9–3.7 dpa. Larger creep and control specimens located more centrally in the capsule received a dose of 1.0 – 3.7 dpa. AGC-3 was designed to provide irradiation conditions similar to AGC-1 and AGC-2 capsules (similar graphite grades tested, specimen dimensions, mechanical loading conditions) but at a different nominal irradiation temperature of 800°C. AGC-3 was irradiated for a short duration to provide material property values at lower dose levels. AGC-4 will have a longer duration and provide material property values at higher dose levels. After irradiation, material property and dimensional strain measurements were conducted on all AGC-3 specimens (from 11 nuclear graphite grades) using the same equipment and approved standards as were conducted before irradiation. The specimen loading configuration for all graphite grades within AGC-3 followed a similar pattern as earlier AGC capsules to provide easy future comparison of all irradiated material property data.},

  doi          = {},

  url          = {https://www.osti.gov/biblio/1774792},
  journal      = {},
number       = ,

  volume       = ,

  place        = {United States},

  year         = {2020},

  month        = {4}

}

Copy to clipboard

Program Document:

View Program Document

Other availability

Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that may hold this item.

Save / Share:

Export Metadata

Save to My Library

Similar records in OSTI.GOV collections:

AGC-2 Specimen Post Irradiation Data Package Report

Technical Report Windes, William; Swank, W.; Rohrbaugh, David; ...

This report documents results of the post-irradiation examination material property testing of the creep, control, and piggyback specimens from the irradiation creep capsule Advanced Graphite Creep (AGC)-2 are reported. This is the second of a series of six irradiation test trains planned as part of the AGC experiment to fully characterize the neutron irradiation effects and radiation creep behavior of current nuclear graphite grades. The AGC-2 capsule was irradiated in the Idaho National Laboratory Advanced Test Reactor at a nominal temperature of 600°C and to a peak dose of 5 dpa (displacements per atom). One-half of the creep specimens weremore »« less
https://doi.org/10.2172/1260881

Full Text Available
AGC-3 Experiment Irradiation Monitoring Data Qualification Final Report

Technical Report Hull, Laurence

The Graphite Technology Development Program will run a series of six experiments to quantify the effects of irradiation on nuclear grade graphite. The third experiment, Advanced Graphite Creep 3 (AGC 3), began with Advanced Test Reactor (ATR) Cycle 152B on November 27, 2012, and ended with ATR Cycle 155B on April 23, 2014. This report documents qualification of AGC 3 experiment irradiation monitoring data for use by the Very High Temperature Reactor (VHTR) Technology Development Office (TDO) Program for research and development activities required to design and license the first VHTR nuclear plant. Qualified data meet the requirements for datamore »« less
https://doi.org/10.2172/1166045

Full Text Available
AGC-3 Specimen Load Calculations by Stack

Technical Report Rohrbaugh, David

This Engineering Calculations and aAnalysis Report (ECAR) documents the results of the threshold averaging on the load cell data taken during the third advanced graphite creep (AGC) test, AGC 3. Specimens were irradiated in the Advance Test Reactor (ATR) during Cycles 152B, 154B, 155A, and 155B (the AGC-3 capsule was not in ATR for Cycles 153A/B and 154A). During each cycle, the specimens located in the upper portions of the stacks were subjected to a compressive load. The applied load of each stack was monitored and load data were recorded in 1 minute intervals. Collecting data detailing the loads appliedmore »« less
https://doi.org/10.2172/1599858

Full Text Available
AGC-3 Graphite Preirradiation Data Analysis Report

Technical Report Windes, William; Swank, David; Rohrbaugh, David; ...

This report describes the specimen loading order and documents all pre-irradiation examination material property measurement data for the graphite specimens contained within the third Advanced Graphite Capsule (AGC-3) irradiation capsule. The AGC-3 capsule is third in six planned irradiation capsules comprising the Advanced Graphite Creep (AGC) test series. The AGC test series is used to irradiate graphite specimens allowing quantitative data necessary for predicting the irradiation behavior and operating performance of new nuclear graphite grades to be generated which will ascertain the in-service behavior of the graphite for pebble bed and prismatic Very High Temperature Reactor (VHTR) designs. The generalmore »« less
https://doi.org/10.2172/1111508

Full Text Available
HDG-1 Graphite Preirradiation Data Package Report

Program Document Rohrbaugh, David; Windes, William; Swank, W

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 ofmore »« less
Full Text Available

Similar Records