44 Matching Results

Search Results

Advanced search parameters have been applied.

in creator/contributor: "Ginsberg, T."

open access

Direct heating containment vessel interactions code (DHCVIC) and prediction of SNL ''SURTSEY'' test DCH-1

High-pressure melt ejection from PWR vessels has been identified as a severe core accident scenario which could potentially lead to ''early'' containment failure. Melt ejection, followed by dispersal of the melt by high velocity steam in the cavity beneath the PWR vessel could, according to this scenario, lead to rapid transfer of energy from the melt droplets to the containment atmosphere. This paper describes DHCVIC, an integrated model of the thermal, chemical and hydrodynamic interactions w… more

Date: January 1, 1986

Creator: Ginsberg, T. & Tutu, N.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

BNL severe-accident sequence experiments and analysis program. [PWR; BWR]

In the analysis of degraded core accidents, the two major sources of pressure loading on light water reactor containments are: steam generation from core debris-water thermal interactions; and molten core-concrete interactions. Experiments are in progress at BNL in support of analytical model development related to aspects of the above containment loading mechanisms. The work supports development and evaluation of the CORCON (Muir, 1981) and MARCH (Wooton, 1980) computer codes. Progress in the … more

Date: January 1, 1983

Creator: Greene, G.A.; Ginsberg, T. & Tutu, N.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Evaluation of condensation-induced water hammer in preheat steam generators

A review of Westinghouse 1/8-scale water hammer tests and data analysis was carried out. BNL has concluded that water hammers occurred in the feedwater line during many of the 1/8-scale tests. These events were probably caused by steam bubble entrapment and collapse in the partially-filled feedwater line. Recorded vessel pressure pulse activity under two-phase operating conditions was rare and, in those cases where pulses were recorded, the pressure pulse amplitudes were small. Either void coll… more

Date: September 1, 1980

Creator: Saha, P.; Ginsberg, T.; Wu, B.J.C. & Jones, O.C. Jr.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Aspects of microwave-heating uniformity

Interest has been shown in the field of nuclear reactor safety in the use of microwave heating to simulate the nuclear heat source. The objective of the investigation reported here was to evaluate the usefulness of microwave dielectric heating as a simulator of the nuclear heat source in experiments which simulate the process of boiling of molten mixtures of nuclear fuel and steel. This paper summarizes the results of studies of several aspects of energy deposition in dielectric liquid samples … more

Date: January 1, 1983

Creator: Ginsberg, T. & Makowitz, H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Analysis of influence of steam superheating on packed bed quench phenomena

Experimental data suggest that steam produced within a particle bed which is being quenched by flow from an overlying pool of water has a strong potential for being superheated as a result of heat transfer from the unquenched particulate in the dry channels of the bed. A model is presented for the debris bed quench process which considers the effects of steam superheat on both the bed heat flux and on the quench front propagation characteristics. Calculations are presented which demonstrate the… more

Date: January 1, 1985

Creator: Ginsberg, T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Core-debris quenching-heat-transfer rates under top- and bottom-reflood conditions. [PWR; BWR]

This paper presents recent experimental data for the quench-heat-transfer characteristics of superheated packed beds of spheres which were cooled, in separate experiments, by top- and bottom-flooding modes. Experiments were carried out with beds of 3-mm steel spheres of 330-mm height. The initial bed temperature was 810 K. The observed heat-transfer rates are strongly dependent on the mode of water injection. The results suggest that top-flood bed quench heat transfer is limited by the rate at … more

Date: February 1, 1983

Creator: Ginsberg, T.; Tutu, N.; Klages, J.; Schwarz, C. E. & Sanborn, Y.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

BNL severe accident sequence experiments and analysis program

A major source of containment pressurization during severe accidents is the transfer of stored energy from the hot core material to available cooling water. One mode of thermal interaction involves the quench of superheated beds of debris which could be present in the reactor cavity following melt-through or failure of the reactor vessel. This work supports development of models of superheated bed quench phenomena which are to be incorporated into containment analysis computer codes such as MAR… more

Date: January 1, 1985

Creator: Greene, G.A.; Ginsberg, T. & Tutu, N.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

DHCVIM: A direct heating containment vessel interactions module: Applications to Sandia National Laboratory Surtsey experiments

Direct containment heating is the mechanism of severe nuclear reactor accident containment loading which results from transfer of thermal and chemical energy from high temperature, finely divided, molten core material to the containment atmosphere. The Direct Heating Containment Vessel Interactions Module, DHCVIM, has been developed at BNL to mechanistically model the mechanisms of containment loading resulting from the direct heating accident sequence. The calculational procedure is being used… more

Date: January 1, 1987

Creator: Ginsberg, T. & Tutu, N.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Transient quenching of superheated debris beds during bottom reflood

The experimental data suggest that for small liquid supply rate and low initial particle temperature, the bed quench process is a one-dimensional frontal phenomenon. The bed heat flux is constant during most of the duration of the quench period. The range of conditions which display one-dimensional frontal cooling characteristics is identified as the deep bed regime of bed quenching, and a limiting mathematical model was developed to describe the observed behavior. For large liquid supply rate … more

Date: January 1, 1984

Creator: Tutu, N. K.; Ginsberg, T.; Klein, J.; Schwarz, C. E. & Klages, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Contain direct containment heating calculations for the Zion plant: A preliminary study

No Description Available.

Date: January 1, 1988

Creator: Tutu, N.; Park, C.; Grimshaw, C. & Ginsberg, T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Quench cooling of superheated debris beds in containment during LWR core meltdown accidents

Light water reactor core meltdown accident sequence studies suggest that superheated debris beds may settle on the concrete floor beneath the reactor vessel. A model for the heat transfer processes during quench of superheated debris beds cooled by an overlying pool of water has been presented in a prior paper. This paper discusses the coolability of decay-heated debris beds from the standpoint of their transient quench characteristics. It is shown that even though a debris bed configuration ma… more

Date: January 1, 1984

Creator: Ginsberg, T. & Chen, J. C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Model for superheated debris-bed quench for severe-accident containment calculations. [PWR; BWR]. CONF-831047--85

Core meltdown accidents are being analyzed to develop an understanding of the risk associated with such postulated accidents and to evaluate the impact of possible mitigating engineering safety equipment. An integral feature of these analyses is the determination of containment building pressurization as a result of loadings imposed by the energy stored in the molten core debris. A major source of containment pressurization would result from the ex-vessel thermal interaction between molten core… more

Date: August 1, 1983

Creator: Ginsberg, T. & Chen, J. C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Preliminary reactor cavity melt dispersal model for direct containment heating scenarios

This paper presents the results of a series of experiments performed to study the effect of initial pressure vessel conditions on the extent of melt dispersal from scaled reactor cavities and describes progress in development of a mathematical model which is designed to predict the melt mass dispersed from reactor cavities as a function of reactor vessel initial conditions and on the vessel breach area. The model, which is being developed to also characterize the heat transfer and chemical reac… more

Date: January 1, 1989

Creator: Ginsberg, T. & Tutu, N.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Condensation induced water hammer in steam generators

The case of condensation induced water hammer in nuclear steam generators is summarized, including both feed ring-type and economizer-type geometries. A slug impact model is described and used to demonstrate the parametric dependence of the impact pressures on heat transfer rates, initial pressures, and relative initial slug and void lengths. The results of the parametric study are related also to the economizer geometry and a suggested alternative model is presented. The importance of concerns… more

Date: June 1, 1979

Creator: Jones, O.C. Jr.; Saha, P.; Wu, B.J.C. & Ginsberg, T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Potential for entrainment of sodium into expanding multiphase HCDA bubbles by Rayleigh-Taylor instability

The ''termination phase'' of an energetic hypothetical core disruptive accident (HCDA) in liquid-metal fast breeder reactors is characterized by expansion of a high-pressure, high-temperature multiphase bubble against the overlying pool of sodium. A number of entrainment mechanisms have been proposed to explain the entrainment rates observed in various experiments. (JDB)

Date: January 1, 1981

Creator: Ginsberg, T. & Moszynski, J.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

One-dimensional model for transient boilup of volume-heated pools for LMFBR transition phase analysis

An analytical model is presented which describes the transient dispersion characteristics of fuel-steel boiling pool systems under decay heating conditions, with boundary heat losses. The spatial distribution of steel vapor (void fraction) and molten fluid is computed, together with the pressure--temperature histories of boiling pool systems. Local heat losses and sensible heating are included in the model for the vapor generation rate in the material balance equations. Model calculations are p… more

Date: January 1, 1979

Creator: Ginsberg, T. & Chen, J. C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Aerosol generation from sparging of molten pools of corium by gases released from core-concrete interactions. [PWR; BWR]

A model for calculation of the aerosol generation rate resulting from surface bubble rupture during molten core-concrete interactions is discussed. One aspect of the model, based upon previous work in the literature, considers that film rupture occurs due to growth of film oscillation disturbances in the surface liquid film. Calculations are presented for molten pools with liquid properties in the range of prototypic interest.

Date: February 1, 1983

Creator: Ginsberg, T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Microwave heating simulations of fission energy generation in volume-boiling pool systems

The transition phase of the (hypothetical) loss-of-flow accident in LMFBR's may be characterized by the temporary entrapment of boiling pools of molten fuel and steel within the original core boundaries. Experiments to investigate the multiphase flow and heat transfer characteristics of such systems have been performed and are planned in which simulant fluids are volume-heated by microwave electromagnetic radiation. It has been assumed that the microwave radiation provides a spatially uniform e… more

Date: January 1, 1979

Creator: Makowitz, H. & Ginsberg, T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Observations on hydrogen generation in vicinity of the reactor cavity during the Direct Containment Heating scenario

No Description Available.

Date: January 1, 1987

Creator: Ginsberg, T. & Tutu, N.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

BNL program in support of LWR degraded-core accident analysis

Two major sources of loading on dry watr reactor containments are steam generatin from core debris water thermal interactions and molten core-concrete interactions. Experiments are in progress at BNL in support of analytical model development related to aspects of the above containment loading mechanisms. The work supports development and evaluation of the CORCON (Muir, 1981) and MARCH (Wooton, 1980) computer codes. Progress in the two programs is described in this paper. 8 figures.

Date: January 1, 1982

Creator: Ginsberg, T. & Greene, G.A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Progress in understanding of direct containment heating phenomena in pressurized light water reactors

Progress is described in development of a mechanistic understanding of direct containment heating phemonena arising during high-pressure melt ejection accidents in pressurized water reactor systems. The experimental data base is discussed which forms the basis for current assessments of containment pressure response using current lumped-parameter containment analysis methods. The deficiencies in available methods and supporting data base required to describe major phenomena occurring in the rea… more

Date: January 1, 1988

Creator: Ginsberg, T. & Tutu, N.K.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Quench cooling of superheated debris beds in containment during LWR core meltdown accidents

Light water reactor core meltdown accident sequence studies suggest that superheated debris beds may settle on the concrete floor beneath the reactor vessel. A model for the heat transfer processes during quench (removal of stored energy from initial temperature to saturation temperature) of superheated debris beds cooled by an overlying pool of water has been presented in a prior paper. This paper discusses the coolability of decay-heated debris beds from the standpoint of their transient quen… more

Date: January 1, 1984

Creator: Ginsberg, T. & Chen, J. C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Transient core-debris bed heat-removal experiments and analysis. [PWR; BWR]

An experimental investigation is reported of the thermal interaction between superheated core debris and water during postulated light-water reactor degraded core accidents. Data are presented for the heat transfer characteristics of packed beds of 3 mm spheres which are cooled by overlying pools of water. Results of transient bed temperature and steam flow rate measurements are presented for bed heights in the range 218 mm-433 mm and initial particle bed temperatures between 530K and 972K. Res… more

Date: August 1, 1982

Creator: Ginsberg, T.; Klein, J.; Klages, J.; Schwarz, C. E. & Chen, J. C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Liquid jet breakup characterization with application to melt-water mixing

Severe accidents in light-water reactors could lead to the flow of molten core material from the initial core region of the reactor vessel to the lower plenum. Steam explosions have been predicted to occur as a result of the contact of the melt with water available in the plenum. It is presently judged by many workers, that the magnitude of the energy released during such an in-vessel explosion would be insufficient to lead to failure of the containment building (SERG, 1985). A major contributi… more

Date: January 1, 1986

Creator: Ginsberg, T.

Item Type: Article

Partner: UNT Libraries Government Documents Department