The Fort St. Vrain high temperature gas-cooled reactor: VII. Prestressed concrete reactor vessel (PCRV) performance

1982 ◽  
Vol 72 (2) ◽  
pp. 111-123 ◽  
Author(s):  
H.G. Olson ◽  
H.L. Brey ◽  
F.E. Swart
Keyword(s):  
High Temperature ◽  
Prestressed Concrete ◽  
Reactor Vessel ◽  
High Temperature Gas

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.

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.

Simulation of the Operation in Passive Mode of Reactor Cavity Cooling System of High-Temperature Gas-Cooled Reactor

2008 ◽  
Author(s):  
Alex Matev
Keyword(s):  
High Temperature ◽  
Cooling System ◽  
Fission Products ◽  
Computer Code ◽  
Reactor Vessel ◽  
Passive Mode ◽  
Axial Distribution ◽  
Air Ingress ◽  
Cavity Cooling ◽  
High Temperature Gas

The Reactor Cavity Cooling System (RCCS) of a High-Temperature Gas-Cooled Reactor (HTGR) may be required to operate in a “passive” mode when heat is removed from the reactor cavity by letting RCCS water inventory to boil off to atmosphere. Overheating of the reactor cavity concrete walls may lead to a failure of the reactor vessel support structures and its shift off the design position. Dislocation of the massive reactor vessel may cause multiple ruptures of pipes, connected to both the upper and lower vessel heads. Such breaks of the reactor pressure boundary will enable air ingress into the core, fuel oxidation and overheating, and possible release of fission products into the environment. The computer code TINTE [3] was used to simulate a “Depressurized Loss Of Flow Circulation (DLOFC) Without Reactor Scram” accident and determine from its results the magnitude, axial distribution, and time dependence of the heat flux on the RCCS cooling panels. The computer code RELAP [4] was used to model the operation in “passive” mode of one RCCS train, consisting of a tank and four standpipes. This paper describes the application of both RELAP and TINTE for the simulation of RCCS operation in passive mode. The main conclusion from this analysis is that the proposed way of using both codes is suitable to perform scoping studies and design evaluation of RCCS of a pebble-bed HTGR.

Transient Analysis of a Permeable Thermal Barrier System

1978 ◽  
Vol 100 (1) ◽  
pp. 127-131 ◽  
Author(s):  
L. C. Cheng ◽  
J. M. Bowyer
Keyword(s):  
High Temperature ◽  
Prestressed Concrete ◽  
Rational Design ◽  
Working Fluid ◽  
System Response ◽  
Thermal Barrier ◽  
Transient Model ◽  
One Dimensional ◽  
Qualitative And Quantitative ◽  
High Temperature Gas

A permeable thermal barrier system lines the walls of certain enclosures and pipes within the High Temperature Gas-Cooled Reactor (HTGR). This system protects the Prestressed Concrete Reactor Vessel (PCRV) from the otherwise damaging effects of heat transfer from the high-temperature helium working fluid. A one-dimensional transient model of this system has been developed to study the response of this system and its associated supporting structure when it is subjected to a rapid depressurization. The analytical model is normalized, and the dimensionless parameters which characterize the system response are extensively studied. The results of this study will provide both the qualitative and quantitative knowledge required for a rational design of thermal barrier system in the High Temperature Gas-Cooled Reactors.

An Environmental Wet Cell For High Voltage Electron Microscopy

1973 ◽  
Vol 31 ◽  
pp. 18-19
Author(s):  
N.J. Tighe ◽  
H.M. Flower ◽  
P.R. Swann
Keyword(s):  
Electron Microscopy ◽  
High Temperature ◽  
Image Quality ◽  
Inelastic Scattering ◽  
High Voltage ◽  
High Voltage Electron Microscopy ◽  
Voltage Electron ◽  
Environmental Cell ◽  
Water Saturated ◽  
High Temperature Gas

A differentially pumped environmental cell has been developed for use in the AEI EM7 million volt microscope. In the initial version the column of gas traversed by the beam was 5.5mm. This permited inclusion of a tilting hot stage in the cell for investigating high temperature gas-specimen reactions. In order to examine specimens in the wet state it was found that a pressure of approximately 400 torr of water saturated helium was needed around the specimen to prevent dehydration. Inelastic scattering by the water resulted in a sharp loss of image quality. Therefore a modified cell with an ‘airgap’ of only 1.5mm has been constructed. The shorter electron path through the gas permits examination of specimens at the necessary pressure of moist helium; the specimen can still be tilted about the side entry rod axis by ±7°C to obtain stereopairs.

DISPERSED PHASE VELOCITY IN A HIGH-TEMPERATURE GAS FLOW

2019 ◽  
Vol 23 (4) ◽  
pp. 319-328
Author(s):  
Dmitry V. Nesterovich ◽  
Oleg G. Penyazkov ◽  
Yu. A. Stankevich ◽  
M. S. Tretyak ◽  
Vladimir V. Chuprasov ◽  
...  
Keyword(s):  
High Temperature ◽  
Phase Velocity ◽  
Gas Flow ◽  
Dispersed Phase ◽  
High Temperature Gas
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