Published August 1, 2010 | Version v1
Report Metadata-only

AGC-2 Graphite Pre-irradiation Data Package

Creators

Description

The NGNP Graphite R and D program is currently establishing the safe operating envelope of graphite core components for a Very High Temperature Reactor (VHTR) design. The program is generating quantitative data necessary for predicting the behavior and operating performance of the new nuclear graphite grades. To determine the in-service behavior of the graphite for pebble bed and prismatic designs, the Advanced Graphite Creep (AGC) experiment is underway. This experiment is examining the properties and behavior of nuclear grade graphite over a large spectrum of temperatures, neutron fluences and compressive loads. Each experiment consists of over 400 graphite specimens that are characterized prior to irradiation and following irradiation. Six experiments are planned with the first, AGC-1, currently being irradiated in the Advanced Test Reactor (ATR) and pre-irradiation characterization of the second, AGC-2, completed. This data package establishes the readiness of 512 specimens for assembly into the AGC-2 capsule.

Additional details

Identifiers

URL
https://www.osti.gov/servlets/purl/991897-BbEhtW/;
DOI
10.2172/991897;

Publishing Information

Imprint Pagination
vp.
Report number
INL/EXT--10-19588

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
42006133
Subject category
S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
CREEP; DESIGN; GRAPHITE; IRRADIATION; NEUTRON FLUENCE; PERFORMANCE; TEST REACTORS
Descriptors DEC
CARBON; ELEMENTS; MECHANICAL PROPERTIES; MINERALS; NONMETALS; REACTORS; RESEARCH AND TEST REACTORS; TEST FACILITIES

Optional Information

Contract/Grant/Project number
AC07-05ID14517
Notes
doi 10.2172/991897
Funding organization
DOE - NE (United States)