HTGR Knowledge Base

Subject Index to Technical Documents

HTR Conferences

Conference on High Temperature Reactors (HTR-2004)
Proceedings of the Conference on High Temperature Reactors, Beijing, China, September, 22-24, 2004
Conference on High Temperature Reactors (HTR-2002)
Proceedings of the Conference on High Temperature Reactors, Petten, NL, April 22-24, 2002
Organized by HTR-TN in cooperation with the European Nucler Society (ENS) and the IAEA

Reactor Design and General Technology

Evaluation of high temperature gas cooled reactor performance: Benchmark analysis related to initial testing of the HTTR and HTR-10 (IAEA-TECDOC--1382)
Current status and future development of modular high temperature gas cooled reactor technology (IAEA-TECDOC--1198)
Overview of HTGR technology development as of 2001
High temperature gas cooled reactor technology development. (IAEA-TECDOC--988)
Technical committee meeting on high temperature gas cooled reactor technology development. Johannesburg (South Africa). 13-15 Nov 1996.
Design and development of gas cooled reactors with closed cycle gas turbines. (IAEA-TECDOC--899)
Technical committee meeting on design and development of gas cooled reactors with closed cycle gas turbines. Beijing (China). 30 Oct - 2 Nov 1995.
Gas-cooled fast reactors. (IAEA-TECDOC--154)
Proceedings of the IAEA study group meeting sponsored by the USSR State Committee on the Utilization of Atomic Energy, held at the Institute of Nuclear Energy of the Byelorussian Academy of Sciences Minsk, 24-28 July 1972.

Component Technology

Critical experiments and reactor physics calculations for low-enriched HTGRs (IAEA-TECDOC--1249)
Results of an IAEA Co-ordinated Research Project in support of validation of reactor physics codes for modular HTGRs conducted 1990-1996
Gas turbine power conversion systems for modular HTGRs (IAEA-TECDOC--1238)
IAEA Technical Committee Meeting on “Gas Turbine Power Conversion Systems for Modular HTGRs”, held from 14-16 November 2000 in Palo Alto, California
Uncertainties in physics calculations for gas cooled reactor cores. (IWGGCR--24)
Uncertainties in physics calculations for gas cooled reactor cores. Proceedings of a specialist's meeting held in Villigen, Switzerland, 9-11 May 1990
Seismic behaviour of gas cooled reactor components. (IWGGCR--22)
Seismic behaviour of gas cooled reactor components. Proceedings of a specialists' meeting held in Gif-sur-Yvette, France, 14-16 November 1989
Gas-cooled reactor coolant circulator and blower technology (IWGGCR--17)
Specialists' meeting on gas-cooled reactor coolant circulator and blower technology. San Diego, CA (USA). 30 Nov - 2 Dec 1987
Technology of steam generators for gas-cooled reactors (IWGGCR--15)
Specialists' meeting on technology of steam generators for gas-cooled reactors Winterthur (Switzerland) 9-12 Mar 1987
Graphite component structural design (IWGGCR--11)
Specialists' meeting on graphite component structural design, JAERI Tokai (Japan), September 8-11, 1986
Heat exchanging components of gas-cooled reactors (IWGGCR--9)
Specialists' meeting on heat exchanging components of gas-cooled reactors Duesseldorf (Germany) 16-19 Apr 1984
Gas-cooled reactor fuel development and spent fuel treatment (IWGGCR--8)
Specialists' meeting on gas-cooled reactor fuel development and spent fuel treatment Moscow (Russian Federation) 18-21 Oct 1983

Materials Technology

Irradiation damage in graphite due to fast neutrons in fission and fusion systems (IAEA-TECDOC--1154)
Summary of graphite irradiation experience and implications with regard to design of graphite components in future fission and fusion systems
Nuclear Graphite Waste Management (TCM-Manchester99)
IAEA Technical Committee Meeting on "Nuclear Graphite Waste Management", held from 18-20 October 1999 in Manchester, United Kingdom
Graphite moderator lifecycle behaviour. (IAEA-TECDOC--901)
Specialists meeting on graphite moderator lifecycle behaviour. Bath (United Kingdom). 24-27 Sep 1995.
The status of graphite development for gas cooled reactors. (IAEA-TECDOC--690)
Specialists' meeting on the status of graphite development for gas cooled reactors. Tokai, Ibaraki (Japan). 9-12 Sep 1991
Design requirements, operation and maintenance of gas-cooled reactors (IWGGCR--19)
Technical committee meeting on design requirements, operation and maintenance of gas-cooled reactors. San Diego, CA (USA). 21-23 Sep 1988
High temperature metallic materials for gas-cooled reactors (IWGGCR--18)
High temperature metallic materials for gas-cooled reactors. Proceedings of a specialists meeting held in Cracow, 20-23 June 1988
High temperature metallic materials for application in gas-cooled reactors (IWGGCR--4)
Specialists Meeting on high temperature materials for applications in gas-cooled reactors held in Vienna, 4-6 May 1981
Mechanical behaviour of graphite for HTRs (IWGHTR--3)
Specialists meeting on mechanical behaviour of graphite for HTRs, Gif-sur-Yvette, France, 11-13 June 1979.

Safety Aspects

Considerations in the development of safety requirements for innovative reactors: Application to modular high temperature gas cooled reactors (IAEA-TECDOC--1366)
Safety related design and economic aspects of HTGR (IAEA-TECDOC--1210)
Proceedings of a Technical Committee Meeting held in Beijing, People's Republic of China, 2-4 November 1998
Heat transport and afterheat removal for gas cooled reactors under accident conditions (IAEA-TECDOC--1163)
Results of an IAEA Co-ordinated Research Project in support of validation of thermal hydraulics codes for modular HTGRs, conducted 1992-1998
Fuel performance and fission product behaviour in gas cooled reactors (IAEA-TECDOC--978)
Results of an IAEA Co-ordinated Research Project on coated particle fuel retention of radionuclides and transport of fission products in modular HTGRs, conducted 1992-1996
Response of fuel, fuel elements and gas cooled reactor cores under accidental air or water ingress conditions. (IAEA-TECDOC--784)
Technical committee meeting on response of fuel, fuel elements and gas cooled reactor cores under accidental air or water ingress conditions. Beijing (China). 25-27 Oct 1993
Decay heat removal and heat transfer under normal and accident conditions in gas cooled reactors. (IAEA-TECDOC--757)
Specialists meeting on decay heat removal and heat transfer under normal and accident conditions in gas cooled reactors. Juelich (Germany). 6-8 Jul 1992
Gas-cooled reactor technology safety and siting (IAEA-TC--389.26)
Technical committee meeting on gas-cooled reactor technology safety and siting Dimitrovgrad (Russian Federation) 21-23 Jun 1989
Gas-cooled reactor safety and accident analysis. (IAEA-TECDOC--358)
Specialists' meeting on safety and accident analysis for gas-cooled reactors. Oak Ridge, TN (USA). 13-15 May 1985
Behaviour of gas cooled reactor fuel under accident conditions. (IWGGCR--25)
Behaviour of gas cooled reactor fuel under accident conditions. Proceedings of a specialists meeting held in Oak Ridge, 5-8 November 1990
Fission product release and transport in gas-cooled reactors (IWGGCR--13)
Specialists' meeting on fission product release and transport in gas-cooled reactors Berkeley (United Kingdom) 22-25 Oct 1985
Gas-cooled reactor seismic design problems and solutions (IWGGCR--6)
IAEA IWGGCR specialists' meeting on gas-cooled reactor seismic design problems and solutions. San Diego, CA (USA). 30 Aug - 1 Sep 1982
Gas-cooled reactor safety and licensing aspects (IWGGCR--1)
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors. Specialists meeting on gas-cooled reactor safety and licensing aspects, Lausanne, Switzerland, 1-3 September 1980. Summary report. Jan 1981

Operational Aspects

Technologies for gas cooled reactor decommissioning, fuel storage and waste disposal. (IAEA-TECDOC--1043)
Technical committee meeting on technologies for gas cooled reactor decommissioning, fuel storage and waste disposal. Juelich (Germany) 8-10 Sep 1997
Coolant chemistry, plate-out and decontamination in gas-cooled reactors. (IWGGCR--2)
Specialists meeting on coolant chemistry, plate-out and decontamination in gas-cooled reactors Juelich, Federal Republic of Germany 2-4 December 1980

Nuclear Heat Applications

Design and evaluation of heat utilization systems for the high temperature engineering test reactor (IAEA-TECDOC--1236)
Results of an IAEA Co-ordinated Research Project on high temperature process heat applications with potential for demonstration using the High Temperature Engineering Test Reactor (HTTR) in Japan, conducted 1993-1999
Hydrogen as an energy carrier and its production by nuclear power (IAEA-TECDOC--1085)
An overview of past technology development and future prospects of processes for nuclear production by nuclear power
Nuclear heat applications: design aspects and operating experience. (IAEA-TECDOC--1056)
Advisory group meeting and consultancy on experience with nuclear heat applications: district heating, process heat and desalination, 13-15 December 1995 and 7-9 February 1996.
Advisory group meeting on technology, design and safety aspects of non-electrical application of nuclear energy, 20-24 October 1997.
Advisory group meeting on operational modes of nuclear desalination plants, 3-5 November 1997.
Advisory group meeting on materials and equipment for the coupling interfaces of nuclear reactors with desalination and district heating plants, 21-23 April 1998.
Non-electric applications of nuclear energy. (IAEA-TECDOC--923)
Advisory group meeting on non-electric applications of nuclear energy. Jakarta (Indonesia). 21-23 Nov 1995
High temperature applications of nuclear energy. (IAEA-TECDOC--761)
Technical committee meeting on high temperature applications of nuclear energy. Oarai (Japan). 19-20 Oct 1992
Process heat applications technology (IWGHTR--6)
Specialists' meeting on process heat applications technology. Juelich, Germany, F.R. 27 - 29 Nov 1979