Published September 1, 2007 | Version v1
Report

Graphite Technology Development Plan

Description

This technology development plan is designed to provide a clear understanding of the research and development direction necessary for the qualification of nuclear grade graphite for use within the Next Generation Nuclear Plant (NGNP) reactor. The NGNP will be a helium gas cooled Very High Temperature Reactor (VHTR) with a large graphite core. Graphite physically contains the fuel and comprises the majority of the core volume. Considerable effort will be required to ensure that the graphite performance is not compromised during operation. Based upon the perceived requirements the major data needs are outlined and justified from the perspective of reactor design, reactor performance, or the reactor safety case. The path forward for technology development can then be easily determined for each data need. How the data will be obtained and the inter-relationships between the experimental and modeling activities will define the technology development for graphite R and D. Finally, the variables affecting this R and D program are discussed from a general perspective. Factors that can significantly affect the R and D program such as funding, schedules, available resources, multiple reactor designs, and graphite acquisition are analyzed.

Additional details

Publishing Information

Imprint Pagination
vp.
Report number
INL/EXT--07-13165

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
41025065
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
DESIGN; GRAPHITE; HELIUM; PERFORMANCE; REACTOR SAFETY; SCHEDULES; SIMULATION
Descriptors DEC
CARBON; ELEMENTS; FLUIDS; GASES; MINERALS; NONMETALS; RARE GASES; SAFETY

Optional Information

Contract/Grant/Project number
AC07-05ID14517
Notes
doi 10.2172/968671
Funding organization
DOE - NE (United States)