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Reactor safety. Quarterly technical progress report, October--December 1977. [LMFBR]

Description: The objectives of the program are to conduct tests that will characterize the behavior of sodium oxide, fuel, fission product, and other aerosols as they might be generated by various postulated LMFBR accidents; determine by analysis and confirm by experiment the generation and transport of these aerosols with respect to source (location, type, and configuration), for the entire course of events associated with real and hypothetical accident conditions; and conduct tests that will determine the… more
Date: March 21, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

First in-core molten fuel pool experiment. [LMFBR]

Description: If during a LMFBR accident a fuel debris bed is not adequately cooled by overlying sodium and dryout occurs, then the fuel would heat up and melt. Molten fuel pools are of concern due to their potential for ablation of the supporting structure and possible penetration of the reactor vessel. The major goal of the molten fuel pool program has been to develop a versatile experiment in which heat flux and structural ablation could be studied using real materials under typical temperature and heatin… more
Date: January 1, 1977
Creator: Plein, H.G. & Carlson, G.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Growth of molten core debris pools in concrete. Part II. A. Pool growth in composite beds; B. Effect of overlaying steel layers. Final report, March 1, 1978-September 30, 1979. [LMFBR]

Description: The heat and mass transfer processes taking place in molten core debris/concrete systems have been experimentally investigated. Two types of experiments have been conducted. The first experiment simulates the growth of a molten debris pool in a composite sacrificial bed. This experiment models debris pool growth in an inner, low-melting point, sacrificial material zone followed by a melting attack on the concrete bed. The purpose of the inner zone is to quickly melt and dilute the debris pool s… more
Date: December 26, 1979
Creator: Abdel-Khalik, S I
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Exploratory study of molten core material/concrete interactions, July 1975--March 1977. [BWR; PWR]

Description: An experimental study of the interaction between high-temperature molten materials and structural concrete is described. The experimental efforts focused on the interaction of melts of reactor core materials weighing 12 to 200 kg at temperatures 1700 to 2800/sup 0/C with calcareous and basaltic concrete representative of that found in existing light-water nuclear reactors. Observations concerning the rate and mode of melt penetration into concrete, the nature and generation rate of gases libera… more
Date: February 1, 1978
Creator: Powers, D.A.; Dahlgren, D.A.; Muir, J.F. & Murfin, W.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radiant heat evaluation of concrete: a study of the erosion of concrete due to surface heating

Description: Experiments were carried out to investigate the erosion of concrete under high surface heat flux in connection with the core-melt/concrete interaction studies. The dominate erosion mechanism was found to be melting at the surface accompanied by chemical decomposition of the concrete beneath the melt-solid interface. The erosion process reaches a steady state after an initial transient. The steady state is characterized by an essentially constant erosion rate at the surface and a nonvarying (wit… more
Date: January 1, 1978
Creator: Chu, T.Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Advanced Reactor Safety Research Program quarterly report, April--June 1977. [LMFBR]

Description: Information is presented concerning accident energetics; core debris behavior; sodium containment and structural integrity; research for elevated temperature design criteria; fuel motion detection; ACPR fuel motion system; and advanced reactor safety research assessment.
Date: November 1, 1977
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Containment response to postulated ex-vessel core meltdown accidents in the fast flux test facility

Description: An evaluation of the containment response to ex-vessel core meltdown accidents in the Fast Flux Test Facility is discussed. Particular attention is given to the possibility of the molten fuel/steel mixture remaining in a molten form after entering the reactor cavity. For the molten pool configurations considered, significant H/sub 2/ concentrations were reached in the RCB before the reactor cavity floor was penetrated. The melt-front impacts the pressure transient, not through gas generation, b… more
Date: January 1, 1979
Creator: Pratt, W. T.; Gasser, R. D. & Marchese, A. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Integral Postdisassembly Energetics Test: A Preliminary Investigation

Description: Scaled, real-material integral tests could demonstrate mitigating mechanisms in postdisassembly energetic behavior during a hypothetical accident in a liquid metal fast breeder reactor (LMFBR). Such a test series could provide key data for accident analysis codes and LMFBR design and licensing. Studies were performed to determine important system parameters including the test geometry necessary to maintain prototypicality. Neutronic behavior of the core and radial blanket configuration was stud… more
Date: January 1, 1979
Creator: Barts, E. W.; Asprey, M. W.; Burns, R. D., III; Chapyak, E. J.; Dunwoody, W. E. & Helmick, H. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Influence of gas generation on high-temperature melt/concrete interactions. [BWR; PWR; LMFBR]

Description: Accidents involving fuel melting and eventual contact between the high temperature melt and structural concrete may be hypothesized for both light water thermal reactors and liquid metal cooled breeder reactors. Though these hypothesized accidents have a quite low probability of occurring, it is necessary to investigate the probable natures of the accidents if an adequate assessment of the risks associated with the use of nuclear reactors is to be made. A brief description is given of a program… more
Date: January 1, 1979
Creator: Powers, D.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Survey of melt interactions with core retention material. [LMFBR]

Description: A survey of the interactions of up to 220 kg stainless steel melts at 1973/sup 0/K with the candidate core retention materials borax, firebrick, high alumina cement, and magnesia is described. Data collected for the interactions include rates of material erosion, aerosol generation, gas evolution, and upward heat flux. Borax acts as an ablative solid that rapidly quenches the melt. Firebrick is ablated by the steel melt at a rate of 8.2 x 10/sup -6/ m/s. High alumina cement is found to be an at… more
Date: January 1, 1979
Creator: Powers, D.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Boilup threshold for the bottled-up transition phase pool. [LMFBR]

Description: Since the inception of the hypothesized transition phase, for the late stages of a postulated LMFBR accident, there has been a continual effort to characterize the anticipated conditions of such a hypothetical state. To date, several techniques and methods have been employed to analyze the potential for energetic criticality. As part of this effort, an arbitrary criterian of monotonical dispersiveness has been employed as the measure of diminished recriticality potential. The various attempts t… more
Date: October 1, 1978
Creator: Martin, F. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Transition phase issues. [LMFBR]

Description: The safety issues associated with the transition (core disruption) phase of hypothetical LMFBR accidents are identified and discussed. This discussion is intended to serve as a basis for defining future experimental needs to support core disruption analysis, and for defining analytical code developments required to support the licensing process and experimental analysis.
Date: December 1, 1979
Creator: Padilla, A. Jr. & Martin, F.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LMFBR safety: Task 10 - characterization of sodium fires and fission product

Description: The objectives of this project are to: develop a computer program for calculating two-dimensional, transient, natural convection phenomena such as those arising from various sodium spill accidents in Liquid Metal Fast Breeder Reactor (LMFBR) heat transfer equipment vaults, head compartments, containment buildings, and secondary heat transfer systems; develop experimental programs and conduct tests that will characterize the behavior of sodium, sodium oxide, fuel, fission product, and other aero… more
Date: January 1, 1977
Creator: Heisler, M. P.; Johnson, R. P.; Nelson, C. T.; Vaughan, E. U.; Guderjahn, C. & Eytel, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Studies of the role of molten materials in interactions with UO/sub 2/ and graphite. [GCFR type reactors]

Description: Graphite, which is being considered as a lower reactor shield in gas-cooled fast reactors, would be contacted by core debris during a core disruptive accident. Information on the interaction of graphite, UO/sub 2/, and stainless steel is needed in assessing the safety of the GCFR. In an ongoing study of the interaction of graphite, UO/sub 2/, and stainless steel, the effects of the steel components have been investigated by electron microprobe scans, x-ray diffraction, and reaction-rate measure… more
Date: January 1, 1979
Creator: Fink, J K; Heiberger, J J & Leibowitz, L
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Evaluation of molten fuel containment concepts for gas-cooled fast breeder reactors

Description: Four in-vessel molten fuel containment concepts for the GCFR were compared, namely, (1) a ceramic crucible, (2) a borax bath, (3) a heavy metal bath, and (4) a steel bath. The ceramic crucible is the simplest but depends on substantial upward heat removal. The borax bath and the heavy metal bath concepts offer better performance but would require design changes and an increased experimental effort. The steel bath concept is a good compromise and has potential for further improvement by combinin… more
Date: October 1, 1979
Creator: Kang, C.S. & Torri, A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Melt/concrete interactions: the Sandia experimental program, model development, and code comparison test. [PWR; BWR]

Description: High temperature melt/concrete interactions have been studied both experimentally and analytically at Sandia under sponsorship of Reactor Safety Research of the US Nuclear Regulatory Commission. The purpose of these studies has been to develop an understanding of these interactions suitable for risk assessment. Results of the experimental program are summarized and a computer model of melt/concrete interactions is described. A melt/concrete interaction test that will allow this and other models… more
Date: January 1, 1979
Creator: Powers, D.A. & Muir, J.F.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Debris bed heat removal models: boiling and dryout with top and bottom cooling. [Deep bed model]

Description: A one-dimensional deep bed model for incipient dryout is developed which predicts deep bed behavior but not shallow bed behavior. A fluidization criterion results which indicates that a debris bed cannot be fluidized by the vapor flow. However, the maintenance of channels within the bed is predicted. A top-subcooled bed model is presented and evidence (both experimental and calculational) is given that the top-subcooled zone removes heat in series (not in parallel) with the boiling zone for sod… more
Date: January 1, 1979
Creator: Lipinski, R.J. & Rivard, J.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Molten fuel containment analysis for SLSF experiments. [LMFBR]

Description: The Sodium Loop Safety Facility (SLSF) experiments are being conducted in the Engineering Test Reactor (ETR) at the Idaho National Engineering Laboratory to furnish information concerning the behavior of fast reactor fuel elements under a hypothesized loss-of-flow accident conditions. These experiments involve measurements and observations that will permit an assessment of the location and time of sodium void initiation, the nature of sodium expulsion and reentry, the time and nature of claddin… more
Date: January 1, 1979
Creator: El-Genk, M.S. & Moore, R.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Dual change-of-phase in forced flow on a finite wall, with application to SLSF safety analysis

Description: An important study related to the safety analysis of Liquid Metal Fast Breeder Reactors (LMFBRs) is to understand the phenomena of molten fuel relocation and refreezing on the core cold structures following a hypothesized loss-of-flow accident (LOFA). An assessment of molten fuel containment capability for the Sodium Loop Safety Facility (SLSF) in-pile experiments following a postulated LOFA is presented, considering the conditions of molten fuel flow, simultaneous melting in the outer duct wal… more
Date: January 1, 1979
Creator: El-Genk, M S & Moore, R L
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Growth of molten core debris pools in concrete. Progress report, April 1--June 30, 1979. [LMFBR]

Description: The heat and mass transfer processes taking place in molten core debris/concrete systems have been experimentally investigated. Two types of experiments have been conducted. The first experiment simulates the growth of a molten debris pool in a composite sacrificial bed. This experiment models debris pool growth in an inner, low-melting point, sacrificial material zone followed by a melting attack on the concrete bed. The purpose of the inner zone is to quickly melt and dilute the debris pool s… more
Date: July 1, 1979
Creator: Abdel-Khalik, S I
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Comparison of measured and calculated average void fraction in volume-boiling pools with inclined boundaries. [LMFBR]

Description: Accident analysis of an HCDA in an LMFBR often involves consideration and calculation of thermal hydraulic events related to boiling pools of fuel and steel mixtures in the disrupted core, as well as the subsequent motion of these two-phase mixtures out of the core. In many cases, the thermal-hydraulic state of the boiling fuel-steel or fuel pool may determine the initial or boundary conditions for subsequent calculations. Calculations of boundary heat losses are directly dependent on knowledge… more
Date: January 1, 1979
Creator: Greene, G. A.; Jones, O. C., Jr.; Abuaf, N. & Schwarz, C. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Simulation of heat and mass transfer processes in molten core debris-concrete systems. [LMFBR]

Description: The heat and mass transport phenomena taking place in volumetrically-heated fluids have become of interest in recent years due to their significance in assessments of fast reactor safety and post-accident heat removal (PAHR). Following a hypothetical core disruptive accident (HCDA), the core and reactor internals may melt down. The core debis melting through the reactor vessel and guard vessel may eventually contact the concrete of the reactor cell floor. The interaction of the core debris with… more
Date: January 1, 1979
Creator: Felde, D K
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sodium concrete reactions. [LMFBR]

Description: The data from an extensive series of sodium/concrete reaction tests are presented and mechanisms by which the reactions proceed are analyzed. The results indicate water transport and the resulting sodium/water reaction dominate both the chemical energy release and H/sub 2/ generation. A mechanism which explains the limited penetration of concrete observed in most of these tests is proposed.
Date: January 1, 1979
Creator: Colburn, R. P.; Muhlestein, L. D.; Hassberger, J. A. & Mahncke, A. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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