Turbocirculator for High Temperature Gas-Cooled Reactors

1970 ◽  
Author(s):  
J. Yampolsky ◽  
G. Melese D’Hospital ◽  
L. Cavallaro ◽  
V. J. Barbat
Keyword(s):  
High Temperature ◽  
Prestressed Concrete ◽  
Thermodynamic Cycle ◽  
Supply System ◽  
The Other ◽  
Pumping Power ◽  
Present Design ◽  
The Cost ◽  
Reactor Pressure ◽  
High Temperature Gas

The present design study was part of a program undertaken for the purpose of determining the feasibility, establishing the development requirements, and estimating the cost of a turbocirculator to provide the pumping power for a 1000-MWe High Temperature Gas Cooled Reactor (HTGR). Methods were developed for the optimization of the thermodynamic cycle and the design point of the turbocirculator components. A comparison of a turbocirculator to other ways of pumping helium in a HTGR is also shown in this paper. A design of the machine with its associated bearing and seal system and gas conduits was carried out. An important feature of this design is incorporation with the other components of the nuclear steam supply system within the prestressed concrete reactor pressure vessel.

Optimization of Active Magnetic Bearings’ Power Supply System for Main Helium Fan in High Temperature Gas-Cooled Reactor

2021 ◽  
Author(s):  
Huan Luo ◽  
Zhengang Shi ◽  
Yan Zhou ◽  
Ni Mo
Keyword(s):  
High Temperature ◽  
Power Supply ◽  
Power Supply System ◽  
Magnetic Bearing ◽  
Supply System ◽  
Buck Converter ◽  
Normal Operation ◽  
Rotating Equipment ◽  
Amb System ◽  
High Temperature Gas

Abstract High temperature gas-cooled reactor (HTR) is a kind of reactor with inherent safety developed by Institute of Nuclear Energy and New Energy Technology of Tsinghua University. In the first circuit, pure helium is used as coolant and the main helium fan is used to promote the coolant circulation. In order to meet the requirements of service environment and performance, the main helium fan adopts the non-lubricant active magnetic bearing (AMB) system as its support system. For the high-speed rotating equipment supported by AMBs, losing power would lead to bearing failure and cause serious damage to the equipment. In this paper, the power supply system of AMBs is optimized. The power supply of AMB system is connected with the DC-link of the motor converter through DC/DC converter. During normal operation, the AMB system is supplied by external power supply, and the DC/DC converter is used as the backup redundant power supply. In the event of a power failure accident, the DC/DC converter is put into operation, converting the remanet kinetic energy of the motor into stable power to maintain the normal operation of the AMB system. The DC/DC converter adopts two-stage topology structure of the former BUCK converter and the later LLC converter, and completes the voltage stabilization control of the latter LLC converter through the digital signal processor (DSP). Experimental results show that this scheme can realize the power loss protection function of the rotating equipment supported by AMBs.

Program of Human-Machine Interface Verification and Validation of HTR-PM in China

2016 ◽  
Author(s):  
Jia Qianqian ◽  
Chao Guo ◽  
Qu Ronghong ◽  
Zhang Liangju
Keyword(s):  
High Temperature ◽  
Steam Turbine ◽  
Modular Design ◽  
Supply System ◽  
Human Machine Interface ◽  
Verification And Validation ◽  
Task Support ◽  
Machine Interface ◽  
Under Construction ◽  
High Temperature Gas

The demonstration construction of the Chinese design of modular high temperature gas cooled reactor (MHTGR), named as high-temperature gas-cooled reactor-pebble bed module (HTR-PM) is now under construction. HTR-PM employs a layout of two nuclear steam supply system (NSSS) modules coupled to one steam turbine. The verification and validation (V&V) of HMIs is important for HTR-PM, as the first two-modular design. The V&V program of HMIs for HTR-PM is introduced in this paper. The V&V activities may include the static and dynamic verifications. The basic layout and static HMI usabilities will be verified on the static stage, and the task support based on operation procedures will be evaluated in the dynamic V&V phase. A verification platform is built to make verification and validation of the HMIs. The HMIs of HTR-PM will be improved according to the V&V result.

Steam-Turbine-Driven Circulators for High-Temperature Gas-Cooled Reactors—Part II: Development

1974 ◽  
Vol 96 (2) ◽  
pp. 102-108
Author(s):  
V. J. Barbat ◽  
D. Kapich ◽  
F. C. Dahms ◽  
J. Yampolsky
Keyword(s):  
High Temperature ◽  
Steam Turbine ◽  
Prestressed Concrete ◽  
Axial Compressor ◽  
Development Program ◽  
Single Stage ◽  
Coolant Fluid ◽  
Primary Coolant ◽  
Experimental Development ◽  
High Temperature Gas

The High-Temperature Gas-Cooled reactor is characterized by integration of the primary coolant circuit and components within a Prestressed Concrete Pressure Vessel. This concept requires particular features and assurance in the circulators that are used to circulate the primary coolant fluid. Each circulator employs a single-stage axial compressor driven by a single-stage steam turbine which is in series with the main steam turbo-generator. The circulator is lubricated by water and is capable of variable speed operation. The conception and design of the circulator were discussed in the first part of this paper. The present part describes the experimental development program of the series steam-turbine-driven helium circulator, which verified and supported the design methods and demonstrated the operational capability of the circulator in all the possible modes that could occur in plant operation.

Steam Turbine Driven Circulators for High-Temperature Gas-Cooled Reactors—Part I: Design

1974 ◽  
Vol 96 (2) ◽  
pp. 95-101 ◽  
Author(s):  
J. Yampolsky ◽  
L. Cavallaro ◽  
G. C. Thurston ◽  
M. K. Nichols
Keyword(s):  
High Temperature ◽  
Steam Turbine ◽  
Prestressed Concrete ◽  
Axial Compressor ◽  
Development Program ◽  
Single Stage ◽  
Coolant Fluid ◽  
Primary Coolant ◽  
Experimental Development ◽  
High Temperature Gas

The High-Temperature Gas-Cooled reactor is characterized by integration of the primary coolant circuit and components within a Prestressed Concrete Pressure Vessel. This concept requires particular features and assurance in the circulators that are used to circulate the primary coolant fluid. Each circulator employs a single-stage axial compressor driven by a single-stage turbine which is in series with the main steam turbogenerator. The circulator is lubricated by water and is capable of variable speed operation. An extensive design and development program was carried out to provide a family of circulators for a range of reactor sizes. This paper considers the design features of the series steam turbine driven helium circulator and the basis for the adopted design solutions. Part II of this paper considers the experimental development program.

Design Approach for Mitigation of Air Ingress in High Temperature Gas-Cooled Reactor

2016 ◽  
Author(s):  
Hiroyuki Sato ◽  
Hirofumi Ohashi ◽  
Shigeaki Nakagawa
Keyword(s):  
High Temperature ◽  
Natural Circulation ◽  
Reactor Core ◽  
Lumped Element ◽  
Safety Design ◽  
Preliminary Study ◽  
Air Ingress ◽  
Core Cooling ◽  
Reactor Pressure ◽  
High Temperature Gas

One important safety design consideration for high temperature gas-cooled reactor (HTGR) is air ingress following a rupture of the reactor pressure boundary such as primary piping. The air intrusion to the reactor core held at high temperature through the break will results in significant oxidation of graphite components and fuels. Such oxidation may leads to the weakening of core support structures as well as fuel element damage and subsequent fission product release. This paper intends to propose a practical solution to protect the reactor from severe oxidation against air ingress accidents without reliance on subsystems. Firstly, a change is made to the center reflector structure to minimize temperature difference during the accident condition in order to reduce buoyancy-driven natural circulation in the reactor. Secondly, a modified structure of the upper reflector is suggested to prevent massive air ingress against a rupture in standpipes. As a preliminary study, a numerical analysis is performed for a typical prismatic-type HTGR to study the effectiveness of the proposed design concept using simplified lumped element models. The analysis considers internal decay heat generation and transient conduction from inner to outer regions at the reactor core, cooling of vessel outer surface by radiation and natural convection, and natural circulation flow in reactor. The results showed that amount of air ingress into the reactor can be significantly reduced with practical changes to local structure in the reactor.

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