Published August 1, 2016 | Version v1
Report

Data Report on the Newest Batch of PCEA Graphite for the VHTR Baseline Graphite Characterization Program

Description

This report details a comparison of mechanical and physical properties from the first billet of extruded PCEA nuclear-grade graphite from the newest batch of PCEA procured from GrafTech. Testing has largely been completed on three of the billets from the original batch of PCEA, with data distributions for those billets exhibiting a much wider range of values when compared to the distributions of properties from other grades. A higher propensity for extremely low values or specimens that broke while machining or handling was also characteristic of the billets from the first batch, owing to unusually large fissures or disparate flaws in the billets in an as-manufactured state. Coordination with GrafTech prior to placing the order for a second batch of PCEA included discussions on these large disparate flaws and how to prevent them during the manufacturing process. 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. As the program moves forward, property distributions from these two tests will be based on specimen geometries that match specimen geometries being used in the irradiated Advanced Graphite Creep (AGC) program. This will allow a more thorough evaluation of both the utility of the test and expected variability in properties when using those approaches on the constrained geometries of specimens irradiated in the Advanced Test Reactor as part of the AGC experiment.

Availability note (English)

Available from https://inldigitallibrary.inl.gov/sites/sti/sti/7245714.pdf; PURL: http://www.osti.gov/servlets/purl/1364481/

Additional details

Publishing Information

Imprint Pagination
30 p.
Report number
INL/EXT--16-39604

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
48103810
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
COMPARATIVE EVALUATIONS; CREEP; GRAPHITE; PHYSICAL PROPERTIES; TENSILE PROPERTIES; TEST REACTORS
Descriptors DEC
CARBON; ELEMENTS; EVALUATION; MECHANICAL PROPERTIES; MINERALS; NONMETALS; REACTORS; RESEARCH AND TEST REACTORS; TEST FACILITIES

Optional Information

Contract/Grant/Project number
AC07-05ID14517
Funding organization
USDOE Office of Nuclear Energy - NE (United States)
Secondary number(s)
OSTIID--1364481