scholarly journals THR-TH: a high-temperature gas-cooled nuclear reactor core thermal hydraulics code

1984 ◽  
Author(s):  
D.R. Vondy
Keyword(s):  
High Temperature ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Thermal Hydraulics ◽  
Nuclear Reactor Core ◽  
High Temperature Gas

A Nodal Dynamic Model for Control System Simulation of the HTR-PM Reactor Core

2010 ◽  
Author(s):  
Zhe Dong ◽  
Xiaojin Huang ◽  
Liangju Zhang
Keyword(s):  
Control System ◽  
High Temperature ◽  
Power Distribution ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Pebble Bed ◽  
Nodal Model ◽  
High Temperature Gas

The modular high-temperature gas-cooled nuclear reactor (MHTGR) is seen as one of the best candidates for the next generation of nuclear power plants. China began to research the MHTGR technology at the end of the 1970s, and a 10 MWth pebble-bed high temperature reactor HTR-10 has been built. On the basis of the design and operation of the HTR-10, the high temperature gas-cooled reactor pebble-bed module (HTR-PM) project is proposed. One of the main differences between the HTR-PM and HTR-10 is that the ratio of height to diameter corresponding to the core of the HTR-PM is much larger than that of the HTR-10. Therefore it is not proper to use the point kinetics based model for control system design and verification. Motivated by this, a nodal neutron kinetics model for the HTR-PM is derived, and the corresponding nodal thermal-hydraulic model is also established. This newly developed nodal model can reflect not only the total or average information but also the distribution information such as the power distribution as well. Numerical simulation results show that the static precision of the new core model is satisfactory, and the trend of the transient responses is consistent with physical rules.

Aerosols released at high temperature oxidation of a nuclear reactor core model II

2000 ◽  
Vol 31 ◽  
pp. 47-48 ◽  
Author(s):  
A. Pintér Csordás ◽  
L. Matus ◽  
Z. Hózer ◽  
A. Czitrovsky ◽  
P. Jani
Keyword(s):  
High Temperature ◽  
High Temperature Oxidation ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Core Model ◽  
Temperature Oxidation ◽  
Nuclear Reactor Core

Investigation of aerosols released at high temperature from nuclear reactor core models

2000 ◽  
Vol 282 (2-3) ◽  
pp. 205-215 ◽  
Author(s):  
A Pintér Csordás ◽  
L Matus ◽  
A Czitrovszky ◽  
P Jani ◽  
L Maróti ◽  
...  
Keyword(s):  
High Temperature ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Nuclear Reactor Core

scholarly journals Double Heterogeneity Neutronic Simulation of HTR-10 for First Criticality and Full Power Initial Core with TORT-TD code

2021 ◽  
Vol 927 (1) ◽  
pp. 012037
Author(s):  
Daddy Setyawan
Keyword(s):  
High Temperature ◽  
Cross Section ◽  
Power Distribution ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Pebble Bed ◽  
The Core ◽  
Full Power ◽  
Double Heterogeneity ◽  
High Temperature Gas

Abstract In order to support the verification and validation of computational methods and codes for the safety assessment of pebble bed High-Temperature Gas-cooled Reactors (HTGRs), the calculation of first criticality and full power initial core of the high-temperature pebble bed reactor 10 MWt (HTR-10) has been defined as one of the problems specified for both code-to-code and code-to-experiment benchmarking with a focus on neutronics. HTR-10 Experimental facility serves as the source of information for the currently designed high-temperature gas-cooled nuclear reactor. It is also desired to verify the existing codes against the data obtained in the facility. In HTR-10, the core is filled with thousands of graphite and fuel pebbles. Fuel pebbles in the reactor consist of TRISO particles, which are embedded in the graphite matrix stochastically. The reactor core is also stochastically filled with pebbles. These two stochastic geometries comprise the so-called double heterogeneity of this type of reactor. In this paper, the first criticality and the power distribution in full power initial core calculations of HTR-10 are used to demonstrate treatment of this double heterogeneity using TORT-TD and Serpent for cross-section generation. HTR-10 has unique characteristics in terms of the randomness in geometry, as in all pebble bed reactors. In this technique, the core structure is modeled by TORT-TD, and Serpent is used to provide the cross-section in a double heterogeneity approach. Results obtained by TORT-TD calculations are compared with available data. It is observed that TORT-TD calculation yield sufficiently accurate results in terms of initial criticality and power distribution in full power initial core of the HTR-10 reactor.

Aerosols released at high temperature oxidation of a nuclear reactor core model

1999 ◽  
Vol 30 ◽  
pp. S105-S106
Author(s):  
A. Pinte´r Csorda´s ◽  
L. Matus ◽  
L. Maro´ti ◽  
A. Czitrovszky ◽  
P. Jani
Keyword(s):  
High Temperature ◽  
High Temperature Oxidation ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Core Model ◽  
Temperature Oxidation ◽  
Nuclear Reactor Core

Full Implicit Integrate Solution to the Coupled Neutronics/Thermal-Hydraulics Problems

2013 ◽  
Author(s):  
Han Zhang ◽  
Fu Li
Keyword(s):  
Nuclear Reactor ◽  
Reactor Core ◽  
Thermal Hydraulics ◽  
Field Equations ◽  
Krylov Method ◽  
Tightly Coupled ◽  
Physical Insight ◽  
Second Order Convergence ◽  
The Individual ◽  
Integrate Solution

The traditional solution of the coupled neutronics/ thermal-hydraulics problems has typically been performed by solving the individual field separately and then transferring information between each other. In this paper, full implicit integrate solution to the coupled neutronics/ thermal-hydraulic problem is investigated. There are two advantages compared with the traditional method, which are high temporal accuracy and stability. The five equations of single-phase flow, the solid heat conduction and the neutronics are employed as a simplified model of a nuclear reactor core. All these field equations are solved together in a tightly coupled, nonlinear fashion. Firstly, Newton-based method is employed to solve nonlinear systems due to its local second-order convergence rate. And then the Krylov iterative method is used to solve the linear systems which are from the Newton linearization. The two procedures above are the so-called Newton-Krylov method. Furthermore, in order to improve the performance of the Krylov method, physics-based preconditioner is employed, which is constructed by the physical insight. Finally, several Newton-Krylov solution approaches are carried out to compare the performance of the coupled neutronics / thermal-hydraulic equations.

Identification of a nuclear reactor core (VVER) using recurrent neural networks

2002 ◽  
Vol 29 (10) ◽  
pp. 1225-1240 ◽  
Author(s):  
Mehrdad Boroushaki ◽  
Mohammad B. Ghofrani ◽  
Caro Lucas
Keyword(s):  
Neural Networks ◽  
Recurrent Neural Networks ◽  
Nuclear Reactor ◽  
Reactor Core ◽  
Nuclear Reactor Core
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