HTGR Knowledge Base

IAEA-TECDOC--1236: Design and evaluation of heat utilization systems for the high temperature engineering test reactor

International Atomic Energy Agency, Vienna (Austria)

Abstract

The IAEA has co-ordinated an extensive programme addressing the technical development of advanced gas cooled reactor technology. This CRP on the application of high temperature nuclear heat complements other recent CRPs which focused on research on the safety of the HTGR. The technical areas within these CRPs included determining the ability of advanced HTGR designs to dissipate decay heat by natural transport mechanisms, the neutron physics behaviour of the core and on the ability of ceramic coated fuel paritcles to retain fission products under accident conditions.

view the full text of this report (format: PDF, size= 10776kB, 208 pages)

see also:

Chapters

Introduction
(format: PDF, size= 101kB, 2 pages) )
HTGR Heat source and utilisation
(format: PDF, size= 416kB, 8 pages) )
High temperature engineering test reactor
(format: PDF, size= 757kB, 15 pages) )
Heat utilisation systems for coupling to the HTTR
(format: PDF, size= 818kB, 17 pages) )
Candidate heat utilisation systems to be connected to the HTTR
(format: PDF, size= 5740kB, 103 pages) )
Achievements of other high temperature endothermic technologies & supporting activities
(format: PDF, size= 2167kB, 34 pages) )
Summary and conclusions
(format: PDF, size= 261kB, 5 pages) )
Appendix A: Research & development needs for the future
(format: PDF, size= 70kB, 2 pages) )
Appendix B: Frequently used abbreviations
(format: PDF, size= 99kB, 5 pages) )
Research co-ordination meetings
(format: PDF, size= 13kB, 1 page) )
Participants & contributors to drafting and review
(format: PDF, size= 25kB, 2 pages) )
Reference:
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1236