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
Keyword(s):  
High Temperature ◽  
Benchmark Data ◽  
Temperature Lattice ◽  
Test Reactor ◽  
High Temperature Gas

scholarly journals COMPUTER PROGRAMS FOR OPERATION OF THE HIGH TEMPERATURE LATTICE TEST REACTOR (HTLTR).

1967 ◽  
Author(s):  
L.D. Coffin ◽  
S.J. Simmons ◽  
J.R. Kosorok ◽  
C.E. Haines ◽  
W.C. Roberts
Keyword(s):  
High Temperature ◽  
Computer Programs ◽  
Temperature Lattice ◽  
Test Reactor

scholarly journals DESIGN CRITERIA FOR HIGH TEMPERATURE LATTICE TEST REACTOR PROJECT CAH-100

1963 ◽  
Author(s):  
D L Ballard ◽  
W W Brown ◽  
C W Harrison ◽  
R E Heineman ◽  
H L Henry ◽  
...  
Keyword(s):  
High Temperature ◽  
Design Criteria ◽  
Temperature Lattice ◽  
Test Reactor

Characteristic Tests on Transition Core of HTR-10

2018 ◽  
Author(s):  
Liqiang Wei ◽  
Dongmei Ding ◽  
Ling Liu ◽  
Yucheng Wang ◽  
Xiaoming Chen ◽  
...  
Keyword(s):  
High Temperature ◽  
Control Rod ◽  
Safety Requirements ◽  
Operation Characteristic ◽  
Power Operation ◽  
Test Reactor ◽  
High Temperature Gas

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.

Summary of Tritium Source Term Study in 10 MW High Temperature Gas-Cooled Test Reactor

2020 ◽  
Vol 76 (4) ◽  
pp. 513-525
Author(s):  
X. Liu ◽  
W. Peng ◽  
F. Xie ◽  
J. Cao ◽  
Y. Dong ◽  
...  
Keyword(s):  
High Temperature ◽  
Source Term ◽  
Term Study ◽  
Test Reactor ◽  
High Temperature Gas

Study on Simulation, Control and Online Assistance Integrated System of 10MW High Temperature Gas-Cooled Test Reactor

2004 ◽  
Author(s):  
Shaojie Luo ◽  
Lei Shi ◽  
Shutang Zhu
Keyword(s):  
Control System ◽  
High Temperature ◽  
System Design ◽  
Reactor Core ◽  
Control Flow ◽  
Integrated System ◽  
Control System Design ◽  
Simulation Control ◽  
Test Reactor ◽  
High Temperature Gas

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.

Development of the Prediction Technology of Cable Disconnection of In-Core Neutron Detector for the Future High-Temperature Gas-Cooled Reactors

2016 ◽  
Vol 2 (4) ◽  
Author(s):  
Yosuke Shimazaki ◽  
Hiroaki Sawahata ◽  
Taiki Kawamoto ◽  
Hisashi Suzuki ◽  
Masanori Shinohara ◽  
...  
Keyword(s):  
High Temperature ◽  
Neutron Detector ◽  
Time Domain Reflectometry ◽  
Technical Issue ◽  
Electrical Method ◽  
Inspection Method ◽  
Wide Range ◽  
Test Reactor ◽  
The Time Domain ◽  
High Temperature Gas

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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