AGC-2 Specimen Post Irradiation Data Package Report

Windes, William Enoch¹  Swank, W. David¹  Rohrbaugh, David T.¹  Cottle, David L.¹ 

[1]Idaho National Lab. (INL), Idaho Falls, ID (United States)

关键词: GRAPHITE;    HTGR TYPE REACTORS;    THERMODYNAMIC PROPERTIES;    POST-IRRADIATION EXAMINATION;    TEMPERATURE RANGE 0400-1000 K;    CREEP;    MODERATORS;    PERFORMANCE;    PHYSICAL PROPERTIES;    NEUTRONS;    PHYSICAL RADIATION EFFECTS;    STRESSES;    PRESSURE RANGE MEGA PA 10-100;    YOUNG MODULUS;    POISSON RATIO;    SHEAR PROPERTIES;    ELECTRIC CONDUCTIVITY;    THERMAL DIFFUSIVITY Advanced Reactor Technologies;    Advanced Test Reactor;    AGC-2;    Carbon Characterization Laboratory;    interquartile range;    thermocouple;    very high temperature reactor;   

DOI  :  10.2172/1260881
RP-ID  :  INL/EXT--15-36244
PID  :  OSTI ID: 1260881
Others  :  TRN: US1601561

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来源: SciTech Connect

【 摘 要 】

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 were subjected to mechanical stresses (an applied stress of either 13.8, 17.2, or 20.7 MPa) to induce irradiation creep. All post-irradiation testing and measurement results are reported with the exception of the irradiation mechanical strength testing, which is the last destructive testing stage of the irradiation testing program. Material property tests were conducted on specimens from 15 nuclear graphite grades using a similar loading configuration as the first AGC capsule (AGC-1) to provide easy comparison between the two capsules. However, AGC-2 contained an increased number of specimens (i.e., 487 total specimens irradiated) and replaced specimens of the minor grade 2020 with the newer grade 2114. The data reported include specimen dimensions for both stressed and unstressed specimens to establish the irradiation creep rates, mass and volume data necessary to derive density, elastic constants (Young???s modulus, shear modulus, and Poisson???s ratio) from ultrasonic time-of-flight velocity measurements, Young???s modulus from the fundamental frequency of vibration, electrical resistivity, and thermal diffusivity and thermal expansion data from 100???500?��C. No data outliers were determined after all measurements were completed. A brief statistical analysis was performed on the irradiated data and a limited comparison between pre- and post-irradiation properties is presented. A more complete evaluation of trends in the material property changes, as well as irradiation-induced creep due to irradiation, temperature, and applied load on specimens will be discussed in later AGC-2 post-irradiation examination analysis reports.