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in creator/contributor: "Baker, L. Jr."

open access

Hydrogen-generating reactions in LWR severe accidents

The available data on the reactions of Zircaloys, stainless steels, uranium metal and uranium dioxide with steam at temperatures above about 1000/sup 0/C and the reactions of core melts during concrete penetration have been reviewed and assessed for the IDCOR Program. The uranium metal is included because small quantities can be formed from the high temperature interaction between Zircaloy and uranium dioxide and because the uranium data adds insight into the nature of the reactions of core mat… more

Date: January 1, 1983

Creator: Baker, L., Jr.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Core debris behavior and interactions with concrete

Post-HCDA, core-debris behavior is considered in three locations: (1) within the reactor vessel, (2) within the cavity below the reactor vessel, and (3) within the concrete below the reactor cavity. In-vessel behavior is dominated by considerations of the fragmentation of molten fuel and steel on quenching in an excess of sodium to form particulate debris beds. In-vessel coolability depends primarily on the availability of sufficient horizontal surface area so that the particulate bed depth is … more

Date: January 1, 1977

Creator: Baker, L., Jr.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Droplet heat transfer and chemical reactions during direct containment heating

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 external diffusive resistances to reaction. The results indicate that reactions will be incomplete for many conditions characteristic of direct containment heating sequences.

Date: January 1, 1986

Creator: Baker, L., Jr.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Source term experiment STEP-3 simulating a PWR severe station blackout

For a severe PWR accident that leads to a loss of feedwater to the steam generators, such as might occur in a station blackout, fission product decay heating will cause a water boiloff. Without effective cooling of the core, steam will begin to oxidize the Zircaloy cladding. The noble gases and volatile fission products, such as Cs and I, that are major contributors to the radiological source term, will be released from the damaged fuel shortly after cladding failure. The accident environment w… more

Date: May 21, 1987

Creator: Simms, R.; Baker, L., Jr. & Ritzman, R. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Growth of internally-heated core debris pools into soluble and insoluble structures. [GCFR type reactors]

The calculations have demonstrated the method and the type of results that can be obtained; however, they are preliminary. The upward heat transfer has not been treated in detail. The upper-surface temperature of the upper frozen crust was assumed to remain at 1500/sup 0/C. This is consistent with a previous one-dimensional analysis of transient layer behavior. Future development of the method is expected to result in a detailed treatment of the molten-steel pool above the fuel mass. Also, the … more

Date: January 1, 1978

Creator: Baker, L., Jr.; Cheung, F. B. & Bingle, J. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Transient heat transfer in concrete. [LMFBR]

The experimental method to study transient heat transfer in concrete has been applied to three concretes of very different compositions. The similarity curves obtained for the three concretes were very much alike. Thermodynamic analysis was used to derive values of the effective volumetric specific heats. The analysis involved the development of idealized compositions to represent the concrete constituents in an approximate way. These were used in conjunction with experimental similarity curves… more

Date: January 1, 1978

Creator: Baker, L., Jr.; Cheung, F. B. & Bingle, J. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Heat transfer from internally-heated molten UO/sub 2/ pools. [PWR; BWR]

Experimental measurements of heat transfer from internally heated pools of molten UO/sub 2/ have been obtained for two cell sizes: 10 cm x 10 cm and 20 cm x 20 cm. The experiments with the large cell have supported a previous conclusion from early small data that the measured downward heat fluxes are higher than would be expected on the basis of considerations of thermal convection. A convective model underpredicts the downward heat fluxes by a factor of 2.5 to 4.5 for all but one early experim… more

Date: October 10, 1978

Creator: Stein, R. P.; Baker, L., Jr.; Gunther, W. H. & Cook, C.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Studies of Metal-Water Reactions at High Temperatures: I. The Condenser Discharge Experiment: Preliminary Results With Zirconium

The condenser-discharge method of conducting molten metal- water reactions at high temperatures was refined. Two methods to measure energy input to specimen wires and, therefore, to compute initial metal temperatures were developed. Calculated metal temperatures were estimated to be accurate to within 100 deg C. Two reaction cells were designed, one for operation at atmospheric pressure with water at room temperature, and the other for operation at high pressure and with water at elevated tempe… more

Date: May 1, 1961

Creator: Baker, L., Jr.; Warchal, R.L.; Vogel, R.C. & Kilpatrick, M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Core-debris accommodation research: status and plans. [LMFBR]

The results of a recent task force study to review the US DOE core-debris accommodation program are presented. The status of technology for in-vessel retention, debris carryover, and ex-vessel retention is summarized. The potential safety issues and the research and development needs are reviewed and a series of tasks and facility requirements are defined. The status of particulate debris-bed coolability experiments are reviewed in detail. Possible mechanisms which might prevent channel formati… more

Date: January 1, 1982

Creator: Baker, L., Jr.; Pedersen, D.R.; Sowa, E.S.; Gabor, J.D. & Alter, H.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Status of core-debris coolability experiments with real and simulant materials at Argonne National Laboratory. [LMFBR]

The two major areas of interest in the debris-bed coolability experiments at ANL are: (1) development of a data base against which existing debris bed coolability models can be compared and to provide insight into the development of future models and (2) investigation of the possible mechanisms which prevent channel formation in a debris bed with real material experiments. The mechanism under consideration are: (a) subcooling of overlying sodium, (b) UO/sub 2+x/ reduction by sodium, (c) failure… more

Date: January 1, 1982

Creator: Pedersen, D.R.; Sowa, E.; Gabor, J.D.; Jones, S.; Baker, L., Jr. & Epstein, M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Summary results of the treat source term experiments project (STEP)

A series of four experiments has been conducted at the Argonne National Laboratory in the Transient Reactor Test Facility (TREAT) aimed at providing data for characterizing the radiological source term for severe light water reactor accidents having the greatest contribution to risk (1,2). In each of the tests, four fuel elements were exposed to environmental conditions similar to the fuel in a reactor at the time volatile fission products and noble gases are released. The 1 m long fuel element… more

Date: January 1, 1988

Creator: Baker, L., Jr.; Ritzman, R. L.; Fink, J. K.; Simms, R.; Schlenger, B. J. & Herceg, J. E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Structural and containment response to LMFBR accidents

The adequacy of the containment of fast reactors has been traditionally evaluated by analyzing the response of the containment to a spectrum of core disruptive accidents. The current approach in the U.S. is to consider fast reactor response to accidents in terms of four lines of assurance (LOAs). Thus, LOA-1 is to prevent accidents, LOA-2 is to limit core damage, LOA-3 is to control accident progression and LOA-4 is to attenuate radiological consequences. Thus, the programs on the adequacy of c… more

Date: January 1, 1978

Creator: Marchaterre, J. F.; Fistedis, S. H.; Baker, L., Jr.; Stepnewski, D. D.; Peak, R. D. & Gluekler, E. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Chemical characteristics of material released during Source Term Experiments Project (STEP) in-pile tests: Part 1

A series of four experiments aimed at characterizing the radiological source term associated with postulated severe light water reactor (LWR) accidents has been conducted at Argonne's Transient Reactor Test Facility (TREAT). The STEP tests drove fuel elements to the point of severe cladding disruption in steam environments by fission heating and oxidation of the Zircaloy cladding. The released fission products and volatile cladding constituents entrained in the steam/hydrogen flows were capture… more

Date: September 1, 1986

Creator: Schlenger, B. J.; Dunn, P. F.; Herceg, J. E.; Simms, R.; Horton, E. L.; Baker, L., Jr. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Thermal interactions of a molten core debris pool with surrounding structural materials. [LMFBR]

Analytical and experimental results on individual aspects of the overall problem of the interaction of a large mass of LMFBR core debris with concrete or other materials are reviewed. Results of recent heat transfer experiments with molten UO/sub 2/ have indicated the importance of internal thermal radiation and methods to take account of this are developed. Effects of gas release and density difference are considered. The GROWS-2 Code is used to illustrate the effects of various assumptions.

Date: January 1, 1979

Creator: Baker, L., Jr.; Cheung, F B; Farhadieh, R; Stein, R P; Gabor, J D & Bingle, J D

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Interactions of certain refractory materials with sodium

Commercial refractories of alumina, magnesia, zirconia, and silica, as well as samples of graphite, thoria, beryllia, boron carbide, and quartz, were tested for compatibility with high-temperature and boiling sodium. Samples were exposed either to static sodium at 850/sup 0/C for five hours or to boiling sodium for about an hour. Graphite, thoria, beryllia, boron carbide, and refractories with high alumina or magnesia contents, but with low silica and chromic oxide contents, were found to be co… more

Date: May 1, 1976

Creator: Fink, J. K.; Heiberger, J. J.; Kumar, R.; Blomquist, R. A.; Leibowitz, L.; Sowa, E. S. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Molten core debris-sodium interactions: M-Series experiments. [LMFBR]

Five new kilogram-scale experiments have been carried out. Four of the experiments simulated the situation where molten core debris flows from a breached reactor vessel into a dry reactor cavity and is followed by a flow of sodium (Ex-vessel case) and one experiment simulated the flow of core debris into an existing pool of sodium (In-vessel case). The core debris was closely simulated by a thermite reaction which produced a molten mixture of UO/sub 2/, ZrO/sub 2/, and stainless steel. There wa… more

Date: January 1, 1979

Creator: Sowa, E S; Gabor, J D; Pavlik, J R; Cassulo, J C; Cook, C J & Baker, L., Jr.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fission product release from aluminum-based fuel melts

No Description Available.

Date: August 1, 1992

Creator: Baker, L., Jr.; Gunther, W.; Sharon, A.; Bonomo, B.; Fink, J. K.; Hutcherson, M. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department