Review of Design Requirements for the MHTGR Reactor Cavity Cooling System

Review of Design Requirements for the MHTGR Reactor Cavity Cooling System PDF Author: M. J. Driscoll
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 20

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Review of Design Requirements for the MHTGR Reactor Cavity Cooling System

Review of Design Requirements for the MHTGR Reactor Cavity Cooling System PDF Author: M. J. Driscoll
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 20

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Design and Construction of a Mock-up to Study MHTGR Reactor Cavity Cooling System Riser Performance

Design and Construction of a Mock-up to Study MHTGR Reactor Cavity Cooling System Riser Performance PDF Author: Von Buford Duran
Publisher:
ISBN:
Category :
Languages : en
Pages : 92

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Modeling & Performance of the MHTGR Reactor Cavity Cooling System

Modeling & Performance of the MHTGR Reactor Cavity Cooling System PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Modeling and Performance of the MHTGR (Modular High-Temperature Gas-Cooled Reactor) Reactor Cavity Cooling System

Modeling and Performance of the MHTGR (Modular High-Temperature Gas-Cooled Reactor) Reactor Cavity Cooling System PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 27

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The Reactor Cavity Cooling System (RCCS) of the Modular High- Temperature Gas-Cooled Reactor (MHTGR) proposed by the U.S. Department of Energy is designed to remove the nuclear afterheat passively in the event that neither the heat transport system nor the shutdown cooling circulator subsystem is available. A computer dynamic simulation for the physical and mathematical modeling of and RCCS is described here. Two conclusions can be made form computations performed under the assumption of a uniform reactor vessel temperature. First, the heat transferred across the annulus from the reactor vessel and then to ambient conditions is very dependent on the surface emissivities of the reactor vessel and RCCS panels. These emissivities should be periodically checked to ensure the safety function of the RCCS. Second, the heat transfer from the reactor vessel is reduced by a maximum of 10% by the presence of steam at 1 atm in the reactor cavity annulus for an assumed constant in the transmission of radiant energy across the annulus can be expected to result in an increase in the reactor vessel temperature for the MHTGR. Further investigation of participating radiation media, including small particles, in the reactor cavity annulus is warranted. 26 refs., 7 figs., 1 tab.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 486

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Thermal-Hydraulic Analysis of an Experimental Reactor Cavity Cooling System with Air. Part I

Thermal-Hydraulic Analysis of an Experimental Reactor Cavity Cooling System with Air. Part I PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 185

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This experimental study investigates the thermal hydraulic behavior and the heat removal performance for a scaled Reactor Cavity Cooling System (RCCS) with air. A quarter-scale RCCS facility was designed and built based on a full-scale General Atomics (GA) RCCS design concept for the Modular High Temperature Gas Reactor (MHTGR). The GA RCCS is a passive cooling system that draws in air to use as the cooling fluid to remove heat radiated from the reactor pressure vessel to the air-cooled riser tubes and discharged the heated air into the atmosphere. Scaling laws were used to preserve key aspects and to maintain similarity. The scaled air RCCS facility at UW-Madison is a quarter-scale reduced length experiment housing six riser ducts that represent a 9.5° sector slice of the full-scale GA air RCCS concept. Radiant heaters were used to simulate the heat radiation from the reactor pressure vessel. The maximum power that can be achieved with the radiant heaters is 40 kW with a peak heat flux of 25 kW per meter squared. The quarter-scale RCCS was run under different heat loading cases and operated successfully. Instabilities were observed in some experiments in which one of the two exhaust ducts experienced a flow reversal for a period of time. The data and analysis presented show that the RCCS has promising potential to be a decay heat removal system during an accident scenario.

Review

Review PDF Author: Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 476

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Analysis of the Reactor Cavity Cooling System for Very High Temperature Gas-cooled Reactors Using Computational Fluid Dynamics Tools

Analysis of the Reactor Cavity Cooling System for Very High Temperature Gas-cooled Reactors Using Computational Fluid Dynamics Tools PDF Author: Angelo Frisani
Publisher:
ISBN:
Category :
Languages : en
Pages :

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The design of passive heat removal systems is one of the main concerns for the modular Very High Temperature Gas-Cooled Reactors (VHTR) vessel cavity. The Reactor Cavity Cooling System (RCCS) is an important heat removal system in case of accidents. The design and validation of the RCCS is necessary to demonstrate that VHTRs can survive to the postulated accidents. The commercial Computational Fluid Dynamics (CFD) STAR-CCM+/ V3.06.006 code was used for three-dimensional system modeling and analysis of the RCCS. Two models were developed to analyze heat exchange in the RCCS. Both models incorporate a 180 degree section resembling the VHTR RCCS bench table test facility performed at Texas A & M University. All the key features of the experimental facility were taken into account during the numerical simulations. Two cooling fluids (i.e., water and air) were considered to test the capability of maintaining the RCCS concrete walls temperature below design limits. Mesh convergence was achieved with an intensive parametric study of the two different cooling configurations and selected boundary conditions. To test the effect of turbulence modeling on the RCCS heat exchange, predictions using several different turbulence models and near-wall treatments were evaluated and compared. The models considered included the first-moment closure one equation Spalart-Allmaras model, the first-moment closure two-equation k-e and k-w models and the second-moment closure Reynolds Stress Transport (RST) model. For the near wall treatments, the low y+ and the all y+ wall treatments were considered. The two-layer model was also used to investigate the effect of near-wall treatment. The comparison of the experimental data with the simulations showed a satisfactory agreement for the temperature distribution inside the RCCS cavity medium and at the standpipes walls. The tested turbulence models demonstrated that the Realizable k-e model with two-layer all y+ wall treatment performs better than the other k-e models for such a complicated geometry and flow conditions. Results are in satisfactory agreement with the RST simulations and experimental data available. A scaling analysis was developed to address the distortion introduced by the experimental facility and CFD model in simulating the physics inside the RCCS system with respect to the real plant configuration. The scaling analysis demonstrated that both the experimental facility and CFD model give a satisfactory reproduction of the main flow characteristics inside the RCCS cavity region, with convection and radiation heat exchange phenomena being properly scaled from the real plant to the model analyzed.

Fiscal Year 1991 Department of Energy Authorization: Nuclear fission

Fiscal Year 1991 Department of Energy Authorization: Nuclear fission PDF Author: United States. Congress. House. Committee on Science, Space, and Technology. Subcommittee on Energy Research and Development
Publisher:
ISBN:
Category : Energy policy
Languages : en
Pages : 228

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Use of a Temperature-initiated Passive Cooling System (TIPACS) for the Modular High-temperature Gas-cooled Reactor Cavity Cooling System (RCCS).

Use of a Temperature-initiated Passive Cooling System (TIPACS) for the Modular High-temperature Gas-cooled Reactor Cavity Cooling System (RCCS). PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 110

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A new type of passive cooling system has been invented (Forsberg 1993): the Temperature-Initiated Passive Cooling System (TIPACS). The characteristics of the TIPACS potentially match requirements for an improved reactor-cavity-cooling system (RCCS) for the modular high-temperature gas-cooled reactor (MHTGR). This report is an initial evaluation of the TIPACS for the MHTGR with a Rankines (steam) power conversion cycle. Limited evaluations were made of applying the TIPACS to MHTGRs with reactor pressure vessel temperatures up to 450 C. These temperatures may occur in designs of Brayton cycle (gas turbine) and process heat MHTGRs. The report is structured as follows. Section 2 describes the containment cooling issues associated with the MHTGR and the requirements for such a cooling system. Section 3 describes TIPACS in nonmathematical terms. Section 4 describes TIPACS's heat-removal capabilities. Section 5 analyzes the operation of the temperature-control mechanism that determines under what conditions the TIPACS rejects heat to the environment. Section 6 addresses other design and operational issues. Section 7 identifies uncertainties, and Section 8 provides conclusions. The appendixes provide the detailed data and models used in the analysis.