A5050671951- Nuclear reactor physics and engineering
- Nuclear Engineering Thermal-Hydraulics
- Nuclear Materials and Properties
- Graphite, nuclear technology, radiation studies
- Nuclear and radioactivity studies
- Particle Detector Development and Performance
- Spacecraft and Cryogenic Technologies
- Fault Detection and Control Systems
- Muon and positron interactions and applications
- Superconducting Materials and Applications
- Quantum, superfluid, helium dynamics
- Radiation Detection and Scintillator Technologies
- Non-Destructive Testing Techniques
- Wind and Air Flow Studies
- Nuclear Physics and Applications
- Engineering Applied Research
- Heat transfer and supercritical fluids
- Electron and X-Ray Spectroscopy Techniques
- Adsorption and Cooling Systems
- Marine and Coastal Research
- Solar Energy Systems and Technologies
- Advanced Power Generation Technologies
- Heat Transfer and Boiling Studies
- Heat Transfer and Numerical Methods
- Particle physics theoretical and experimental studies
Japan Atomic Energy Agency
2012-2023
Kyushu University
1997-2005
Advanced Science Research Center
2003
In a safety demonstration test involving the loss of both reactor reactivity control and core cooling, high-temperature engineering (HTTR) demonstrates spontaneous stabilization power. The analytical results tripping one or two out three gas circulators without scram have already been reported. Moreover, pre-analytical result all has presented. On other hand, are shown in this paper. About experiments, at an initial power 30% (9 MW), when were tripped to reduce coolant flow rate zero, fuel...
A high-temperature gas-cooled reactor (HTGR) is a graphite-moderated and helium reactor. It particularly attractive due to its capability of producing gas, passive inherent safety features. To enable nuclear energy application wide range heat process industries, Japan Atomic Energy Agency (JAEA) has continued extensive effort for the development HTGR using engineering test (HTTR), which first in with thermal power 30 MW, operates it at site JAEA's Oarai Research Development Center. The HTTR...
The Gas Turbine High Temperature Reactor 300 (GTHTR300) composed of an inherent safe 600MWt reactor and a closed gas turbine power conversion system is high efficient economically competitive HTGR to be deployed in 2010s. To analyze the plant dynamics thermal hydraulics GTHTR300, new analytical code (Conan-GTHTR) based on 'RELAP5/MOD3' has been developed applied heat transfer calculations Engineering Test (HTTR) for its verification. results proved that was available transient simulations...
The HTTR (High Temperature Engineering Test Reactor), which has thermal output of 30MW, coolant inlet temperature 395°C and outlet 850°C/950°C, is a first high gas-cooled reactor (HTGR) in Japan. HTGR inherent safety potential to accident. Safety demonstration tests using the are underway order demonstrate such excellent features HTGR. reactivity insertion test demonstrates that rapid increase power during withdrawal control rod restrained by only negative feedback effect without operation...
A HTTR (High Temperature Engineering Test Reactor), which has a thermal output of 30 MW, coolant inlet temperature 395°C and outlet 850°C/950°C, is first high-temperature gas-cooled reactor (HTGR) in Japan. The HTGR high inherent safety potential to accidents. demonstration tests such as the reactivity insertion flow reduction using are underway order demonstrate excellent features HTGRs. These that rapid increase or decrease power restrained by only negative feedback effect without an...
Adoption of SiC-matrix fuel elements in future pin-in-block type HTGR designs will enhance oxidation resistance the element event air ingress accident, one most worrisome accidents HTGRs. This would eliminate need for graphite sleeves used current and enable high power density core with sleeveless directly coolable structure. Such a concept itself has been suggested past. However, feasibility design not evaluated yet. The present work is intended to demonstrate new upgraded from an existing...
The High-Temperature Engineering Test Reactor (HTTR) is the first Gas-cooled (HTGR) with a thermal power of 30 MW and maximum reactor outlet coolant temperature 950 °C; it was built at Oarai Research Development Center JAEA. At present, test studies are being conducted using HTTR to improve HTGR technologies in collaboration domestic industries that also contribute foreign projects for acceleration development worldwide. To technologies, advanced analysis techniques currently under data...
The HTTR (High Temperature Engineering Test Reactor), which has thermal output of 30MW, coolant inlet temperature 395°C and outlet 850°C/950°C is the first high gas-cooled reactor (HTGR) in Japan. HTGRs have inherent safety potential to accident condition. Safety demonstration tests using are underway order demonstrate such excellent features HTGRs. reactivity insertion rapid increase power by withdrawing control rod without operating system. experimental results show negative feedback...
Safety demonstration tests using the High Temperature Engineering Test Reactor (HTTR) are in progress to verify its inherent safety features and improve technology design methodology for High-temperature Gas-cooled Reactors (HTGRs). The reactivity insertion test is one of HTTR. This simulates rapid increase reactor power by withdrawing control rod without operating system. In addition, loss coolant flow has been conducted simulate decrease tripping one, two or all out three gas circulators....
Recently, we have been proposing a sleeveless SiC matrix fuel compact design to increase the core power density and enhance safety for High Temperature Gas-cooled Reactor (HTGR). For that application, oxidation behavior of Reaction-Sintered Silicon Carbide (RS-SiC) under conditions air ingress accident needs be investigated. However, few study focused on RS-SiC oxidation, especially interest HTGR. The detailed kinetics passive-to-active transition remain unclear. In this work, aiming at...
Nuclear kinetic calculations based on point model have been generally applied as the standard method for neutronics codes. As central control rod (C-CR) withdrawal test has demonstrated in a prismatic core type high-temperature gas-cooled reactor (HTGR) named High Temperature Engineering Test Reactor (HTTR), transient calculation of parameter, reactivity, and neutron fluxes, requires new to shorten calculation-process time. Development neural network was necessity real-time that could work...