Analysis of the Limiting Safety System Settings of a Fluoride Salt–Cooled High-Temperature Test Reactor

2014 ◽  
Vol 187 (3) ◽  
pp. 221-234 ◽  
Author(s):  
Yao Xiao ◽  
Lin-Wen Hu ◽  
Charles Forsberg ◽  
Suizheng Qiu ◽  
Guanghui Su ◽  
...  
Keyword(s):  
High Temperature ◽  
Safety System ◽  
Fluoride Salt ◽  
Test Reactor ◽  
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 a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor

2015 ◽  
Vol 1 (1) ◽  
Author(s):  
Yao Xiao ◽  
Lin-Wen Hu ◽  
Suizheng Qiu ◽  
Dalin Zhang ◽  
Su Guanghui ◽  
...  
Keyword(s):  
High Temperature ◽  
Computer Code ◽  
The United States ◽  
Coolant Temperature ◽  
Transfer Model ◽  
Fluoride Salt ◽  
Pebble Bed ◽  
Reference Case ◽  
Test Reactor ◽  
Temperature Test

The fluoride-salt-cooled high-temperature reactor (FHR) is an advanced reactor concept that uses high-temperature tristructural isotropic (TRISO) fuel with a low-pressure liquid salt coolant. Design of the fluoride-salt-cooled high-temperature test reactor (FHTR) is a key step in the development of the FHR technology and is currently in progress both in China and the United States. An FHTR based on pebble-bed core design with a coolant temperature of 600–700°C is being planned for construction by the Chinese Academy of Sciences’ (CAS) Thorium Molten Salt Reactor (TMSR) Research Center, Shanghai Institute of Applied Physics (SINAP). This paper provides preliminary thermal-hydraulic transient analyses of an FHTR using SINAP’s pebble-bed core design as a reference case. A point kinetic model is implemented using computer code by coupling with a simplified porous medium heat transfer model in the core. The founded models and developed code are applied to analyze the safety characteristics of the FHTR by simulating several transient conditions including the unprotected loss of flow, unprotected overcooling, and unprotected transient overpower accidents. The results show that SINAP’s pebble-bed core is a very safe reactor design.

Licensing Considerations of a Fluoride Salt Cooled High Temperature Test Reactor

2013 ◽  
Author(s):  
Yao Xiao ◽  
Lin-wen Hu ◽  
Charles Forsberg ◽  
Suizheng Qiu ◽  
Guanghui Su
Keyword(s):  
High Temperature ◽  
Coolant Temperature ◽  
Outlet Temperature ◽  
Fluoride Salt ◽  
Applied Physics ◽  
Reference Case ◽  
Triso Fuel ◽  
Regulatory Guidelines ◽  
Test Reactor ◽  
Temperature Test

The Fluoride salt cooled High temperature Reactor (FHR) is an innovative reactor concept that uses high temperature TRISO fuel with a low-pressure liquid salt coolant. Design of Fluoride salt cooled High temperature Test Reactor (FHTR) is a key step in the development of the FHR technology and is currently in progress both in China and United States. An FHTR based on pebble bed core design with coolant temperature 600–700 °C is being planned for construction by the Shanghai Institute of Applied Physics (SINAP). This paper provides a preliminary thermal hydraulic licensing analysis of an FHTR using SINAP’s pebble core design as a reference case. The operation limits based on criteria outlined in U.S. regulatory guidelines are evaluated. Limiting Safety System Settings (LSSS) considering uncertainties for forced convection operation are obtained. The LSSS power and coolant outlet temperature are 24.6 MW and 720 °C, respectively.

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

Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a FHTR

2014 ◽  
Author(s):  
Yao Xiao ◽  
Lin-wen Hu ◽  
Suizheng Qiu ◽  
Dalin Zhang ◽  
Guanghui Su ◽  
...  
Keyword(s):  
High Temperature ◽  
The United States ◽  
Coolant Temperature ◽  
Transfer Model ◽  
Fluoride Salt ◽  
Applied Physics ◽  
Reference Case ◽  
Triso Fuel ◽  
Test Reactor ◽  
Thorium Molten Salt Reactor

The Fluoride-salt-cooled High-temperature Reactor (FHR) is an advanced reactor concept that uses high temperature TRISO fuel with a low-pressure liquid salt coolant. Design of Fluoride-salt-cooled High-temperature Test Reactor (FHTR) is a key step in the development of the FHR technology and is currently in progress both in China and the United States. An FHTR based on pebble bed core design with coolant temperature 600–700 °C is being planned for construction by the Chinese Academy of Sciences (CAS)’s Thorium Molten Salt Reactor (TMSR) Research Center, Shanghai Institute of Applied Physics (SINAP). This paper provides preliminary thermal hydraulic transient analyses of an FHTR using SINAP’s pebble core design as a reference case. A point kinetic model is calculated by developing a microcomputer code coupling with a simplified porous medium heat transfer model in the core. The founded models and developed code are applied to analyze the safety characteristics of the FHTR by simulating basic transient conditions including the unprotected loss of flow, unprotected overcooling, and unprotected transient overpower accidents. The results show that the SINAP’s pebble core design is an inherently safe reactor design.

scholarly journals Homogenous (Th,Pu)O2 Fuel Utilization on High Temperature Test Reactor 30MWt

2019 ◽  
Vol 1204 ◽  
pp. 012133
Author(s):  
Anni Nuril Hidayati ◽  
Abdul Waris ◽  
Dwi Irwanto ◽  
Asril Pramutadi
Keyword(s):  
High Temperature ◽  
Fuel Utilization ◽  
Test Reactor ◽  
Temperature Test
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