Published August 2017 | Version v1
Report Restricted

Design database of helium gas turbine for HTTR-GT/H2 test plant (Revised version)

Creators

  • 1. Japan Atomic Energy Agency, Sector of Nuclear Science Research, HTGR Hydrogen and Heat Application Research Center, Oarai, Ibaraki (Japan)

Description

High Temperature Gas-cooled Reactor (HTGR) is expected to extend the use of nuclear heat to a wider spectrum of industrial applications because of the high temperature heat supply capability and inherently safe characteristics. Japan Atomic Energy Agency has been conducting research and development for remaining topics in need of further development of high efficient HTGR gas turbine power generation system which is recommended by a task force established under the Nuclear Science Committee of Ministry of Education, Culture, Sports, Science and Technology (MEXT). We are developing a plan for a nuclear cogeneration demonstration utilizing of the High Temperature engineering Test Reactor (HTTR), the first HTGR in Japan. In addition, we are developing turbine blade alloy for reduction of fission product plate-out. This report is the revised version of the report titled "Design Database of Helium Gas Turbine for High Temperature Gas-cooled Reactor, JAEA-Data/Code 2016-007" reflecting component design and experimental data analysis results for fission product isotope diffusion through the turbine blade alloy conducted in Fiscal Year 2016. (author)

Availability note (English)

Available from JAEA; DOI: https://doi.org/10.11484/jaea-data-code-2017-011

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Additional details

Identifiers

DOI
10.11484/jaea-data-code-2017-011;

Publishing Information

Imprint Pagination
43 p.
Report number
JAEA-Data/Code--2017-011

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
49047208
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COATED FUEL PARTICLES; COGENERATION; FISSION PRODUCTS; GAS COMPRESSORS; GAS TURBINES; HEAT TRANSFER; HELIUM; HTTR REACTOR; HYDROGEN PRODUCTION; IN-VESSEL HEAT EXCHANGERS; RADIOISOTOPES; REACTOR SAFETY; REACTOR VESSELS; TUBES; TURBINE BLADES
Descriptors DEC
COMPRESSORS; CONTAINERS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; EXPERIMENTAL REACTORS; FLUIDS; FUEL PARTICLES; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; HEAT EXCHANGERS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; ISOTOPES; MACHINERY; MATERIALS; NONMETALS; POWER GENERATION; RADIOACTIVE MATERIALS; RARE GASES; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; STEAM GENERATION; TURBINES; TURBOMACHINERY

Optional Information

Notes
3 refs., 15 figs., 12 tabs.