Published April 2009 | Version v1
Report Metadata-only

Overview of the DOE advanced gas reactor fuel development and qualification program and gas reactor R and D

Creators

  • 1. U.S. Department of Energy, Washington, D.C. (United States)

Description

Overview of the Generation IV very high temperature gas cooled reactor (VHTR) - next generation nuclear plant (NGNP) development and the details about the US Department of Energy's advanced gas reactor fuel development and qualification program supporting the deployment of tri-isotropic (TRISO) fuel. This project will also demonstrate the economic feasibility of producing hydrogen for alternate energy applications. The details of the fuels program's approach to developing improved gas reactor TRISO ceramic fuel technology and its irradiation and safety performance testing activities are described. Additional fuel development and irradiation testing will be required to demonstrate that TRISO fuel can be used for the higher operating temperatures envisioned for the VHTR design and meet safety margin requirements. The program will provide the necessary fundamental scientific understanding of fuel performance and seek to improve TRISO fuel manufacturing process. (author)

Part of:
Status and prospects for gas cooled reactor fuels. Proceedings of two IAEA meetings held in June 2004 and June 2005

Additional details

Identifiers

URL
http://www-pub.iaea.org/MTCD/publications/PDF/TE_1614_CD/start.pdf; http://www-pub.iaea.org/MTCD/publications/publications.asp;

Publishing Information

ISBN
978-92-0-152809-4
Imprint Title
Status and prospects for gas cooled reactor fuels. Proceedings of two IAEA meetings held in June 2004 and June 2005
Imprint Pagination
274 p.
Journal Page Range
p. 15-28
ISSN
1684-2073
Report number
IAEA-TECDOC-CD--1614

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
41072555
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CERAMICS; DESIGN; FUEL CANS; HYDROGEN; IRRADIATION; MANUFACTURING; NUCLEAR FUELS; NUCLEAR POWER PLANTS; PERFORMANCE; PERFORMANCE TESTING; REACTOR FUELING; SAFETY; SAFETY MARGINS; VHTR REACTOR
Descriptors DEC
ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; MATERIALS; NONMETALS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; TESTING; THERMAL POWER PLANTS; THERMAL REACTORS

Optional Information

Notes
5 refs, 9 figs, 2 tabs