scholarly journals Summary of HTGR (high-temperature gas-cooled reactor) benchmark data from the high temperature lattice test reactor

1989 ◽  
Author(s):  
D.F. Newman
1967 ◽  
Author(s):  
L.D. Coffin ◽  
S.J. Simmons ◽  
J.R. Kosorok ◽  
C.E. Haines ◽  
W.C. Roberts

1963 ◽  
Author(s):  
D L Ballard ◽  
W W Brown ◽  
C W Harrison ◽  
R E Heineman ◽  
H L Henry ◽  
...  

Author(s):  
Liqiang Wei ◽  
Dongmei Ding ◽  
Ling Liu ◽  
Yucheng Wang ◽  
Xiaoming Chen ◽  
...  

After a long-term shutdown, the 10MW high temperature gas-cooled test reactor (HTR-10) was restarted, and the operation & safety characteristics of the HTR-10 transition core are tested and verified. A series of the characteristic tests have been implemented, such as the value calibrating test of the control rod and boron absorber ball, the disturbance characteristic of helium circulator, the start-stop characteristic and the stable power operation characteristic, which indicated the characteristics of the reactor transition core meet the design and safety requirements.


2020 ◽  
Vol 76 (4) ◽  
pp. 513-525
Author(s):  
X. Liu ◽  
W. Peng ◽  
F. Xie ◽  
J. Cao ◽  
Y. Dong ◽  
...  

Author(s):  
Shaojie Luo ◽  
Lei Shi ◽  
Shutang Zhu

In order to provide a convenient tool for engineering designed, safety analysis, operator training and control system design of the high temperature gas-cooled test reactor (HTR), an integrated system for simulation, control and online assistance of the HTR-10 has been designed and is still under development by the Institute of Nuclear Energy Technology (INET) of Tsinghua University in China. The whole system is based on a network environment and includes three subsystems: the simulation subsystem (SIMUSUB), the visualized control designed subsystem (VCDSUB) and the online assistance subsystem (OASUB). The SIMUSUB consists of four parts: the simulation calculating server (SCS), the main control client (MCC), the data disposal client (DDC) and the results graphic display client (RGDC), all of which can communicate each other via network. The SIMUSUB is intended to analyze and calculate the physical processes of the reactor core, the main loop system and the stream generator, etc., as well as to simulate the normal operation and transient accidents, and the result data can be graphically displayed through the RGDC dynamically. The VCDSUB provides a platform for control system modeling where the control flow systems can be automatically generated and graphically simulated. Based on the data from the field bus, the OASUB provides some of the reactor core parameter, which are difficult to measure. This whole system can be used as an educational tool to understand the design and operational characteristics of the HTR-10, and can also provide online supports for operators in the main control room, or as a convenient powerful tool for the control system design.


2016 ◽  
Vol 2 (4) ◽  
Author(s):  
Yosuke Shimazaki ◽  
Hiroaki Sawahata ◽  
Taiki Kawamoto ◽  
Hisashi Suzuki ◽  
Masanori Shinohara ◽  
...  

Maintenance technologies for the reactor system have been developed by using the High Temperature engineering Test Reactor (HTTR). One of the important purposes of development is to accumulate the experiences and data to satisfy the availability of operation up to 90% by shortening the duration of the periodical maintenance for future high-temperature gas-cooled reactors (HTGRs) by shifting from time-based maintenance to condition-based maintenance. The technical issue of the maintenance of the in-core neutron detector, wide range monitor (WRM), is to predict the malfunction caused by cable disconnection to plan the replacement schedule. This is because it is difficult to observe directly inside the WRM in detail. The electrical inspection method was proposed to detect and predict the cable disconnection of the WRM by remote monitoring from outside the reactor using the time-domain reflectometry (TDR). The disconnection position, which was specified by the electrical method, was identified by nondestructive and destructive inspection. The accumulated data are expected to be contributed for advanced maintenance of future HTGRs.


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