Thermal mixing characteristics of helium gas in high-temperature gas-cooled reactor. (1) Thermal mixing behavior of helium gas in HTTR
Creators
- 1. Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan)
- 2. Kyushu University, Department of Applied Quantum Physics and Nuclear Engineering, Fukuoka (Japan)
Description
The future high-temperature gas-cooled reactor (HTGR) is now designed in Japan Atomic Energy Agency. The reactor has many merging points of helium gas with different temperatures. It is needed to clear the thermal mixing characteristics of helium gas at the pipe in the HTGR from the viewpoint of structure integrity and temperature control. Previously, the reactor inlet coolant temperature was controlled lower than specific one in the high-temperature engineering test reactor (HTTR) due to lack of mixing of helium gas in the primary cooling system. Now, the control system is improved to use the calculated bulk temperature of reactor inlet helium gas. In this paper, thermal-hydraulic analysis on the primary cooling system of the HTTR was conducted to clarify the thermal mixing behavior of helium gas. As a result, it was confirmed that the thermal mixing behavior is mainly affected by the aspect ratio of annular flow path, and it is needed to consider the mixing characteristics of helium gas at the piping design of the HTGR. (author)
Availability note (English)
Available from http://dx.doi.org/10.1080/00223131.2015.1054910Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Nuclear Science and Technology (Tokyo)
- Journal Volume
- 53
- Journal Issue
- 3
- Journal Page Range
- p. 425-431
- ISSN
- 0022-3131
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 47104426
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ASPECT RATIO; COOLANT LOOPS; FLOW RATE; HEAT EXTRACTION; HELIUM; HTTR REACTOR; PIPES; PRIMARY COOLANT CIRCUITS; REACTOR CORES; REACTOR SAFETY; THERMAL HYDRAULICS
- Descriptors DEC
- COOLING SYSTEMS; DIMENSIONLESS NUMBERS; ELEMENTS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FLUID MECHANICS; FLUIDS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; HYDRAULICS; MECHANICS; NONMETALS; RARE GASES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; TUBES
Optional Information
- Notes
- 8 refs., 11 figs., 2 tabs.