scholarly journals Use and Storage of Test and Operations Data from the High Temperature Test Reactor Acquired by the US Government from the Japan Atomic Energy Agency

2010 ◽  
Author(s):  
Hans Gougar
Keyword(s):  
High Temperature ◽  
Atomic Energy ◽  
Japan Atomic Energy Agency ◽  
Energy Agency ◽  
The Us ◽  
Us Government ◽  
Test Reactor ◽  
And Storage ◽  
Temperature Test

Thermal Hydraulic Studies of a Fluoride Salt Cooled High Temperature Test Reactor With Different CFD Methods

2014 ◽  
Author(s):  
Chenglong Wang ◽  
Yao Xiao ◽  
Jianjun Zhou ◽  
Dalin Zhang ◽  
Suizheng Qiu ◽  
...  
Keyword(s):  
High Temperature ◽  
Channel Model ◽  
Single Channel ◽  
Fluoride Salt ◽  
Applied Physics ◽  
Local Flow ◽  
Single Channel Analysis ◽  
Test Reactor ◽  
Safety Operation ◽  
Temperature Test

The Fluoride-salt-cooled High temperature Reactor (FHR) is new reactor concept-about a decade old which is mainly on going in China and U.S. The preliminary thermal-hydraulic studies of the Fluoride salt cooled High temperature Test Reactor (FHTR) is necessary for the development of the FHR technology. In this paper, the thermal-hydraulics of FHTR (also called TMSR-SF) designed by Shanghai Instituted of Applied Physics (SINAP) is studied in different power modes. The temperature distributions of the coolant and the fuel pebble are obtained using a steady-state thermal-hydraulic analysis code for FHR. The comprehensive local flow and heat transfer are investigated by computational fluid dynamics (CFD) for the locations where may have the maximum pebble temperature based on the results from single channel analysis. The profiles of temperature, velocity, pressure and Nu of the coolant on the surface of the pebble as well as the temperature distribution of a fuel pebble are obtained and analyzed. Numerical results showed that the results of 3-D simulation are in reasonable agreement with that of single channel model and also illustrated safety operation of the preliminary designed TMSR-SF in different power mode.

Development of High Temperature Gas-Cooled Reactor Fuel for Extended Burnup

2010 ◽  
Author(s):  
Shohei Ueta ◽  
Jun Aihara ◽  
Masaki Honda ◽  
Noboru Furihata ◽  
Kazuhiro Sawa
Keyword(s):  
High Temperature ◽  
Coating Layer ◽  
Fission Products ◽  
Pyrolytic Carbon ◽  
Principal Function ◽  
Energy Agency ◽  
Triso Fuel ◽  
Coating Layers ◽  
Test Reactor ◽  
Fuel Particles

Current HTGRs such as the High Temperature Engineering Test Reactor (HTTR) of Japan Atomic Energy Agency (JAEA) use Tri-Isotropic (TRISO)-coated fuel particles with diameter of around 1 mm. TRISO fuel consists of a micro spherical kernel of oxide or oxycarbide fuel and coating layers of porous pyrolytic carbon (buffer), inner dense pyrolytic carbon (IPyC), silicon carbide (SiC) and outer dense pyrolytic carbon (OPyC). The principal function of these coating layers is to retain fission products within the particle. Particularly, the SiC coating layer acts as a barrier against the diffusive release of metallic fission products and provides mechanical strength for the particle [1].

Investigation on Iodine Release Behavior During the Operation of High Temperature Engineering Test Reactor (HTTR)

2013 ◽  
Author(s):  
Shohei Ueta ◽  
Hiroyuki Inoi ◽  
Yoshitaka Mizutani ◽  
Hirofumi Ohashi ◽  
Jin Iwatsuki ◽  
...  
Keyword(s):  
High Temperature ◽  
Local Area ◽  
Release Behavior ◽  
Primary Coolant ◽  
Energy Agency ◽  
Xenon Isotopes ◽  
Test Reactor ◽  
Forced Cooling ◽  
Iodine Release ◽  
Testing Plan

Japan Atomic Energy Agency (JAEA) has planned to investigate on iodine release behavior from fuel through the testing operation of High Temperature Engineering Test Reactor (HTTR) in order to contribute to the reasonable estimation of the radiation exposure necessary for the realization of HTGR in the future. In this test, the fractional release of iodine will be measured and evaluated by measuring xenon isotopes, the daughter nuclides of iodine isotopes, in the primary coolant sampling under the loss-of-forced cooling (LOFC) test by which the primary coolant circulator is shut down and/or the manual scram test of HTTR. In parallel, the local area of primary coolant circuit where iodine is plated-out will be evaluated. This paper describes the testing plan and the preliminary analytical study on the release behavior of iodine and xenon isotopes through the operation of HTTR.

scholarly journals Recent activity of neutron diffractometers for biological crystallography at Japan Atomic Energy Agency

2010 ◽  
Vol 66 (a1) ◽  
pp. s121-s121
Author(s):  
Taro Tamada ◽  
Kazuo Kurihara ◽  
Takashi Ohhara ◽  
Nobuo Okazaki ◽  
Ryota Kuroki
Keyword(s):  
Atomic Energy ◽  
Japan Atomic Energy Agency ◽  
Energy Agency ◽  
Recent Activity

scholarly journals Deterministic Modeling of the High Temperature Test Reactor

2010 ◽  
Author(s):  
J. Ortensi ◽  
J. J. Cogliati ◽  
M. A. Pope ◽  
R. M. Ferrer ◽  
A. M. Ougouag
Keyword(s):  
High Temperature ◽  
Deterministic Modeling ◽  
Test Reactor ◽  
Temperature Test
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