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1
Heat Transfer Measurements of Internally Heated Liquids in Cylindrical Convection Cells.
1978-01-01

In hypothetical reactor accidents, the thermohydraulic behaviour of core melts heated by the after-heat must be analyzed. For this purpose model experiments have been performed to study the stationary, natural convective heat transfer of internally heated...

National Technical Information Service (NTIS)

2
Fire and Thermal Effects of HD 1.3 Accidents: History ...
2010-07-01

... For a given accident progression, the potential for direct flame ... This may require performing heat transfer analysis for exposed structural members ...

DTIC Science & Technology

3
Heat Removal Characteristics of Volume-Heated Boiling Pools with Inclined Boundaries in Bubbly Flow Regime.
1979-01-01

The heat transfer characteristics of volume-heated boiling pools are of importance in the safety analysis of hypothetical core disruptive accidents in liquid metal fast breeder reactors. Investigations into the heat transfer and hydrodynamic behavior of s...

National Technical Information Service (NTIS)

4
Heat Transfer Effects in Severe Accident Integral Analyses.
1988-01-01

How much energy is removed from the core and where it is deposited are important considerations in severe accidents. The core heatup rate will affect the timing of the damage progression and the nature of the core debris. Heat transferred from the core to...

National Technical Information Service (NTIS)

5
SIMULATION OF A LIQUID METAL FAST BREEDER ...
1969-06-01

... NEUTRON FLUX, REACTOR REACTIVITY, REACTOR KINETICS, HEAT TRANSFER, REACTOR FUELS, ALGORITHMS, REACTOR ACCIDENTS ...

DTIC Science & Technology

6
Natural Convection Heat Transfer in Beds of Inductively Heated Particles.
1978-01-01

The estimation of heat-removal-capability from core debris that may be formed as a result of a hypothetical fuel disruptive accident in a LMFBR is of interest in the nuclear reactor safety analysis. After the accident, the fuel debris in the form of parti...

National Technical Information Service (NTIS)

7
Validation of RELAP5/KMRR for HANARO Accident Analyses.
1996-01-01

To carry out the accident analyses for the HANARO, RELAP5/MOD2 was modified. The heat transfer correlations and other thermal hydraulic models to account for the finned fuel elements and plate-type heat exchangers were modified to give RELAP5/KMRR, simula...

National Technical Information Service (NTIS)

8
Emergency heat removal system for a nuclear reactor
1976-01-01

A heat removal system for nuclear reactors serving as a supplement to an Emergency Core Cooling System (ECCS) during a Loss of Coolant Accident (LOCA) comprises a plurality of heat pipes having one end in heat transfer relationship with either the reactor pressure vessel, the core support grid ...

DOE Information Bridge

9
Emergency Heat Removal System for a Nuclear Reactor.
1976-01-01

A heat removal system for nuclear reactors serving as a supplement to an Emergency Core Cooling System (ECCS) during a Loss of Coolant Accident (LOCA) comprises a plurality of heat pipes having one end in heat transfer relationship with either the reactor...

National Technical Information Service (NTIS)

10
Falling Film Flow, Heat Transfer and Breakdown on Horizontal Tubes.
1980-01-01

Knowledge of falling film flow and heat transfer characteristics on horizontal tubes is required in the assessment of certain CANDU reactor accident sequences for those CANDU reactors which use moderator dump as one of the shut-down mechanisms. In these r...

National Technical Information Service (NTIS)

11
Workshop No. 5 - NASA

10 CFR 71.73 Fire Accident; Cask Performance; Finite Element (ANSYS�) Model ... ANSYS� Model Mesh. Heat Transfer Mechanisms; Initial Conditions ...

NASA Website

12
Network Model of Free Convection within Internally Heated Porous Media.
1978-01-01

A hypothetical core-disruptive accident in a liquid metal fast breeder reactor may result in the formation of an internally heated debris bed which is immersed in liquid sodium. A method is demonstrated for computing the heat transfer from such a bed to t...

National Technical Information Service (NTIS)

13
Heat transfer by natural convection in a volume heated particulate bed
1983-11-01

It is often postulated that following a severe accident in either a liquid metal fast breeder reactor or a light water reactor a particulate debris bed will be formed. An understanding of the physical processes occurring in the debris bed often proves to be paramount in considering its coolability and hence the mitigation of the accident. It is probable ...

Energy Citations Database

14
Droplet heat transfer and chemical reactions during direct containment heating
1986-01-01

A simplified model of heat transfer and chemical reaction has been adapted to evaluate the expected behavior of droplets containing unreacted Zircaloy and stainless steel moving through the containment atmosphere during postulated accidents involving direct containment heating. The model includes internal and ...

Energy Citations Database

15
Combined convection and radiation heat transfer under conditions simulating uncovered reactor fuel rods
1985-01-01

Limited information is available on the detailed heat transfer processes that occur in an undercooled core during a nuclear plant accident. This study determined the relative importance of conduction, convection, and radiation heat transfer in a PWR core with uncovered fuel rods. The resulting ...

Energy Citations Database

16
The modeling of heat transfer in a degraded BWR core
1983-01-01

This paper presents a degraded BWR core heat transfer model for the analysis of accidents leading to core meltdown. The model accounts for conduction, radiation and convection heat transfer, and evaluates such nodal quantities as the regional temperatures and/or melting rates of the fuel, clad, ...

Energy Citations Database

17
Making Core Melt Accidents Impossible in a Large 2400-MW(t) Reactor Charles W. Forsberg

Heat Exchanger Hot Molten Salt Cooling Water Helium Generator Recuperator Gas Compressor Hot Air Out. During operation, the molten salt coolant exit temperatures exceed 750EC. Heat is transferred to a multi transfer through the argon gas from the reactor vessel. Radiation heat ...

E-print Network

18
CFD modeling of the HTR reactor cavity cooling system.
1996-01-01

This report describes the heat transport under accident conditions from the reactor vessel wall of the INCOGEN installation to the environment. For this purpose, the heat transfer mechanisms as well as the flow patterns inside the cavity and the Reactor C...

National Technical Information Service (NTIS)

19
Cooling of safety rods in the Savannah River K Reactor during the gamma heating phase of a postulated loss-of-coolant accident.
1992-01-01

This paper documents the heat-transfer analysis for the safety rod placed in a perforated guide tube during the gamma heating phase of a large-break loss of coolant accident in Savannah River K-reactor. The cooling mechanisms are natural convection to air...

National Technical Information Service (NTIS)

20
Heat transfer of molten metal layers in severe accidents
1997-12-01

In some scenarios of severe accidents of light water reactors, a layer of molten metal from internal structural components of the pressure vessel is predicted to occur on top of a ceramic core debris in the lower head. The layer transfers the heat generated in the ceramic pool to the side wall of the vessel, causing the latter to melt. ...

Energy Citations Database

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21
Natural convection phenomena in a nuclear power plant during a postulated TMLB' accident
1987-01-01

After the TMI (Three Mile Island) accident, there has been significant interest in analyzing and understanding the phenomena that may occur in a PWR (Pressurized Water Reactor) accident which may lead to partial or total core meltdown and degradation. Natural convection is one of the important phenomena. In the present paper the results of two numerical ...

Energy Citations Database

22
Heat Transfer Calculations for a Fixed CST Bed Column
2001-03-28

In support of the crystalline silicotitanate (CST) ion exchange project of High-Level Waste (HLW) Process Engineering, a transient two-dimensional heat transfer model that includes the conduction process neglecting the convection cooling mechanism inside the CST column has been constructed and heat transfer ...

Energy Citations Database

23
HEAT TRANSFER,
1967-08-01

... HEAT TRANSFER), CONVECTION(HEAT TRANSFER), VAPORIZATION, CONDENSATION, HEAT OF VAPORIZATION, THERMAL RADIATION ...

DTIC Science & Technology

24
Heat Transfer.
1967-01-01

Contents: The fundamentals of the theory of transfers; Heat conduction and heat transfer in bodies; Convection heat transfer; Radiative heat exchange.

National Technical Information Service (NTIS)

25
Multi-Phase flow and heat transfer III. Part A: Fundamentals
1984-01-01

This two-volume set presents the papers given at a conference concerning the fundamentals and applications of two-phase flow and heat transfer. Topics considered at the conference included equations, gas-liquid flow, hydrodynamics, pressure drop, steam separation, pressure wave propagation, flashing, boiling, condensation, reactor ...

Energy Citations Database

26
A Heat Transfer Model for a Heated Helium Airship
1987-03-01

... THESIS A HEAT TRANSFER MODEL FOR A HEATED HELIUM AIRSHIP by ... A HEAT TRANSFER MODEL OF A HEATED HELIUM AIRSHIP ...

DTIC Science & Technology

27
Instability of flow of liquid film over a heated surface
1994-08-01

Fundamental concepts and basic equations of a flowing thin liquid film cooling a heated surfaced by its vaporization and the effect of dry patches were treated. Stable film flow prior to the appearance of dry patches on the heated surface is maintained by a balance of various forces due to surface tension, shear stress, heat and mass ...

Energy Citations Database

28
The effect of gamma-ray transport on afterheat calculations for accident analysis
2000-05-01

Radioactive afterheat is an important source term for the release of radionuclides in fusion systems under accident conditions. Heat transfer calculations are used to determine time-temperature histories in regions of interest, but the true source term needs to be the effective afterheat, which considers the transport of penetrating ...

Energy Citations Database

29
Clinch River breeder reactor sodium fire protection system design and development
1984-04-13

To assure the protection of the public and plant equipment, improbable accidents were hypothesized to form the basis for the design of safety systems. One such accident is the postulated failure of the Intermediate Heat Transfer System (IHTS) piping within the Steam Generator Building (SGB), resulting in a ...

DOE Information Bridge

30
Heat transfer processes during intermediate and large break loss-of-coolant accidents (LOCAs)
1986-09-01

The general purpose of this project was the investigation of the heat transfer regimes during the high pressure portion of blowdown. The main attention has been focussed on the evaluation of those phenomena which are most important in reactor safety, such as maximum and minimum critical heat flux and forced convection film boiling ...

Energy Citations Database

31
Safety evaluation of core components exposed to air during an LBLOCA
1993-01-01

An analysis was performed to determine the peak heat structure temperature of internal reactor components during the gamma-heating phase of a large-break loss-of-coolant accident (LBLOCA) in a heavy-water reactor. During this phase, the reactor is scrammed, the coolant in the moderator tank is replaced by air, and fuel and control rod ...

Energy Citations Database

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