Conceptual reactor design study of very high temperature reactor (VHTR) with prismatic-type core
- 1. Fuji Electric Advanced Technology Co., Ltd., Kawasaki, Kanagawa (Japan)
Description
The preliminary conceptual design study of prismatic-type Very High Temperature Reactor (VHTR) has been performed with 950degC outlet coolant temperature for higher efficient hydrogen and electricity production. First, the core internals that enable higher outlet temperature are considered in the viewpoint of reduction of core bypass flow. Three-dimensional thermal and hydraulic analyses are carried out and show that the 950degC outlet temperature requires approximately 90% fuel flow fraction and it can be achieved with the installation of the seals in bottom blocks, the coolant tubes in the permanent side reflectors and the core restraint devices. Next, the core and fission product (FP) release analyses are performed. The analysis methods that have been developed for the pin-in-block fuel, one type of prismatic VHTR cores, can be applied to multi-hole fuel, another type of the cores, with some adjustments of the analytical models. (author)
Additional details
Identifiers
- DOI
- 10.1299/jpes.2.768;
Publishing Information
- Journal Title
- Journal of Power and Energy Systems
- Journal Volume
- 2
- Journal Issue
- 2
- Journal Page Range
- p. 768-774
- ISSN
- 1881-3062
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39106766
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BYPASSES; DESIGN; FISSION PRODUCT RELEASE; FUEL CHANNELS; HTGR TYPE REACTORS; PRISMATIC CONFIGURATION; REACTOR COMPONENTS; REACTOR CORE RESTRAINTS; REACTOR CORES; SEALS; VHTR REACTOR
- Descriptors DEC
- CONFIGURATION; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; POWER REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESTRAINTS; THERMAL REACTORS
Optional Information
- Notes
- Available from doi: http://dx.doi.org/10.1299/jpes.2.768; 6 refs., 14 figs.