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Abstract
Baseline Characterization Database Verification Report - 2114 Billet A20570.pdfBaseline Characterization Database Verification Report - 2114 Billet A20570ECAR-4322

The purpose of this engineering calculations and analysis report (ECAR) is to present data--baseline properties of nuclear-grade graphite with regard to individual grade, billet, and position within individual billets--collected in the Baseline Graphite Characterization Program. The physical- and mechanical-property information being collected will be transferred to the Nuclear Data Management and Analysis System (NDMAS), and that database will help populate the handbook of property data available to member nations of the Generation-IV International Forum. Transfer of these data from the applicable technical lead to the dissemination databases available to other end users requires a full review of the test procedures and data-collection efforts through an analysis of the multiple summary spreadsheets and values being collected. This report represents the analysis for 2114 Billet A20570 and facilitates release of associated data to the NDMAS custodians.​

Baseline Characterization Database Verification Report - PCEA Billet 02S8-7.pdfBaseline Characterization Database Verification Report - PCEA Billet 02S8-7ECAR-3725

The purpose of this engineering calculations and analysis report (ECAR) is to present data--baseline properties of nuclear-grade graphite with regard to individual grade, billet, and position within individual billets--collected in the Baseline Graphite Characterization Program. The physical and mechanical property information being collected will be transferred to the Nuclear Data Management and Analysis System (NDMAS), and that database will help populate the handbook of property data available to member nations of the Generation IV International Forum. Transfer of these data from the applicable technical lead to the dissemination databases available to other end users requires a full review of the test procedures and data collection efforts through an analysis of the multiple summary spreadsheets and values being collected. This report represents the analysis for PCEA billet 02S8 7 and facilitates release of associated data to the NDMAS custodians.​

Baseline Graphite Characterization First Billet.pdfBaseline Graphite Characterization First BilletINL-EXT-10-19910

This report covers the development of the Baseline Graphite Characterization program from a testing and data collection standpoint through the completion of characterization on the first billet of nuclear-grade graphite. The Baseline Graphite Characterization program provide data characterizing the inherent property variability in nuclear-grade graphite without the testing constraints of the Advanced Graphite Creep program. This variability will be quantified not only within a single billet of as-produced graphite, but also from billets within a single lot, billets from different lots of the same grade, and across different billets of the numerous grades of nuclear graphite that are presently available. The thorough understanding of this variability will provide added detail to the irradiated property data, and provide a more thorough understanding of the behavior of graphite that will be used in reactor design and licensing. ​

Baseline Graphite Initial Mechanical Test Report.pdfBaseline Graphite Initial Mechanical Test ReportINL-EXT-09-16868

The Next Generation Nuclear Plant (NGNP) Project is tasked with selecting a high temperature gas reactor technology that will be capable of generating electricity and supplying large amounts of process heat. The NGNP is presently being designed as a helium-cooled high temperature gas reactor (HTGR) with a large graphite core. The graphite baseline characterization project is conducting the research and development (R&D) activities deemed necessary to fully qualify nuclear-grade graphite for use in the NGNP reactor. One of the major fundamental objectives of the project is establishing nonirradiated thermomechanical and thermophysical properties by characterizing lot-to-lot and billet-to-billet variations (for probabilistic baseline data needs) through extensive data collection and statistical analysis. This report is confirmation that the test procedures are in place and approved, and that mechanical testing of graphite under the Baseline Graphite Characterization program has commenced.​

Baseline Test Specimen Machining Report.pdfBaseline Test Specimen Machining ReportINL-EXT-09-16709

The Next Generation Nuclear Plant (NGNP) Project is tasked with selecting a high temperature gas reactor technology that will be capable of generating electricity and supplying large amounts of process heat. The NGNP is presently being designed as a helium-cooled high temperature gas reactor (HTGR) with a large graphite core. The graphite baseline characterization project is conducting the research and development (R&D) activities deemed necessary to fully qualify nuclear-grade graphite for use in the NGNP reactor. One of the key components in the evaluation of these graphite types will be mechanical testing on specimens drawn from carefully controlled sections of each billet. This report discusses the machining of the first set of test specimens that were evaluated in this program through tensile, compressive, and flexural testing. Validation that the test specimens have been produced to the tolerances required by the applicable ASTM standards, and to the quality control levels required by this program, will demonstrate the viability of sending graphite to selected suppliers that will provide valuable and certifiable data to future data sets that are integral to the NGNP program and beyond.​

Data Report on the Newest Batch of PCEA Graphite for the VHTR Baseline Graphite Characterization Program.pdfData Report on the Newest Batch of PCEA Graphite for the VHTR Baseline Graphite Characterization ProgramINL-EXT-16-39604

This report provides a comparison of the observed data distributions from properties measured in the first billet from the new batch of PCEA with those observed in the original batch, in order that an evaluation of tighter control of the manufacturing process and the outcome of these controls on final properties can be ascertained. Additionally, this billet of PCEA is the first billet to formally include measurements from two alternate test techniques that will become part of the Baseline Graphite Characterization database – the three-point bend test on sub-sized cylinders and the Brazilian disc splitting tensile strength test. ​

Grade 2114 Flexure Strength and Elastic Properties.pdfGrade 2114 Flexure Strength and Elastic PropertiesORNL-TM-2019-1256

This document reports flexural strength, bulk density, and elastic constants data (the last determined by two separate methods) for Mersen grade 2114, billet 116310. These data are needed to support the design of graphite core components. This technical memorandum is responsive to work package AT-19OR03050405, “Graphite Materials Properties—ORNL."​

Initial Comparison of Baseline Physical and Mechanical Properties for the VHTR Candidate Graphite Grades.pdfInitial Comparison of Baseline Physical and Mechanical Properties for the VHTR Candidate Graphite GradesINL-EXT-14-33120

This report is a preliminary comparison between each of the grades of graphite that are considered “candidate" grades from four major international graphite producers. These particular grades (NBG-18, NBG-17, PCEA, IG-110, and 2114) are the major focus of the evaluations presently underway on irradiated graphite properties through the series of Advanced Graphite Creep (AGC) experiments. The comparison between each of these grades will include the differences in fundamental and statistically-significant individual strength levels and the differences in overall variability in properties within each of the grades. ​

Statistical Comparison of the Baseline Mechanical Properties of NBG-18 and PCEA Graphite.pdfStatistical Comparison of the Baseline Mechanical Properties of NBG-18 and PCEA GraphiteINL-EXT-13-30011

This report is a preliminary comparison between the two grades of graphite that were initially favored in the two main Very High Temperature Reactor (VHTR) designs. NBG-18, a medium-grain pitch coke graphite from SGL formed via vibration molding, was the favored structural material in the pebble-bed configuration, while PCEA, a smaller grain, petroleum coke, extruded graphite from GrafTech was favored for the prismatic configuration. A comparison between these two grades included differences in fundamental and statistically-significant individual strength levels and differences in variability in properties within each of the grades. ​

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