This report deals with the REXCO-code predictions of the SRI SM-2 test. Two calculations were performed with the REXCO-HEP code: one used the pressure history of the core detonation products as input and the other the pressure-volume relations of the detonation products as input. The other inputs of the computer analysis are the vessel and the core-barrel dimensions and boundary conditions, the constitutive equations of the vessel and the core barrel materials, and the equation of state for the coolant. The REXCO-predicted well deformations, pressure loadings, and dynamic strain histories at various gauge positions are compared with the experimental data. Results of the comparisons are discussed.

A possible accident scenario in a Gas-Cooled Fast Reactor (GCFR) is the leakage of secondary steam into the core. Considerable analytical effort has gone into the study of the effects of such an accidental steam entry. The work described in this report represents the first full scale experimental study of the steam-entry phenomenon in GCFRs. The reference GCFR model used for the study was the benchmark GCFR Phase II assembly, and polyethylene foam was used to provide a very homogeneous steam simulation.

The contact of two liquid materials, one of which is at a temperature substantially above the boiling point of the other, can lead to fast energy conversion and a subsequent shock wave. This phenomenon is called a vapor explosion. One method of producing intimate, liquid-liquid contact (which is known to be a necessary condition for vapor explosion) is a shock tube configuration. Such experiments in which water was impacted upon molten aluminum showed that very high pressures, even larger than the thermodynamic critical pressure, could occur. The mechanism by which such sharp pressure pulses are generated is not yet clear. The report describes experiments in which cold liquids (Freon-11, Freon-22, water, or butanol) were impacted upon various hot materials (mineral oil, silicone oil, water, mercury, molten Wood's metal or molten salt mixture).

A fission-product source (FPS) was irradiated in EBR-II to provide data for calibrating the facility's fuel-element rupture detector (FERD), which is a delayed-neutron monitor, and germanium-lithium argon-scanning system (GLASS), a fission-gas-activity monitor. A metal alloy source, Ni-3.2 wt.% uranium, provided quantitative recoil release of the fission-product nuclides. The source alloy, in tubular form, was irradiated as core-region segments of 18 capsules in the FPS subassembly. The irradiation showed that the response of the FERD was linear with increasing reactor power. The magnitude of the FERD signal was dependent on local fission rate for the FPS and the flow path of the sodium carrying the delayed-neutron emitters. The relatively high fission-gas activity released by the FPS allowed accurate calibration of the GLASS under several modes of operation and provided data for verifying a gas-release model for the reactor.

Report on electrochemical energy development, including development of advanced, high-temperature lithium/metal sulfide batteries for vehicle propulsion and stationary energy storage.

Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward understanding and improving the components of molten-carbonate-electrolyte fuel cells operated at temperatures near 925 K.

A transient, two-dimensional code has been developed to provide a detailed description of fuel-clad conditions during a TOP accident. Emphasis has been directed toward development of a framework within which fuel motion and ejection can be viewed following pin failure. All code modules have been rigorously verified. Illustrative application of the code, with the exercise of its many and varied features, have been included.

This report describes the Fuel Dynamics Test E6 and analyzes the test data. A cluster of six fresh FTR-type fuel pins surrounding a previously irradiated pin was tested to failure in a simulated $3/s FFTF accident.

Type 308 CRE stainless steel weld specimens were subjected to metallographic and fractographic analysis after failure in elevated temperature (593 degrees C) creep-fatigue tests. The failure mode for specimens tested under continuous-cycle fatigue conditions were predominantly transgranular. When the test cycle was modified to include a hold time at the maximum tensile strain, the failure mode became predominantly inter-phase. Sigma phase was observed within the delta-ferrite regions of the weld. However, the presence of sigma phase did not appear to affect the failure mode.

The degenerate parabolic equation has been used to model the flow of gas through a porous medium. Error estimates for continuous and discrete time finite element procedures to approximate the solution of this equation are proved and a new regularity result is described.

Materials used in coal-conversion systems are exposed to high pressure, high temperature, corrosive and erosive gases, and liquids containing particulate matter. These severe environments necessitate an assessment of the integrity of components to prevent premature failures. Gamma radiography was evaluated as a viable technique for testing such components in the laboratory or after operation in situ. Penetrameters (image-quality indicators) were developed for refractory-lined vessels and transfer lines, and exposure times for various combinations of refractory-steel thicknesses were determined. Radiography with /sup 60/Co was performed on gasifier vessels, combustor vessels, and critical transfer lines in existing pilot plants using the experience gained through laboratory experiments. The results show that gamma radiography is a practical and effective method to detect critical conditions in coal-conversion system components.

Appendix containing a survey of terrestrial ecology and preliminary botanical monitoring of Nott Island, Connecticut to accompany a report on habitat field investigations of the Nott Island Upland Habitat Development Site in Connecticut.

Appendix containing supplementary data from an experiment conducted to examine variance in physical and chemical variables made at a naturally occurring marsh and an artificially made experimental marsh. It accompanies a report on habitat development field investigations of the Windmill Point Marsh Development Site, James River, Virginia.

Appendix containing supplementary statistical data to accompany a report on habitat field investigations of the Windmill Point Marsh Development Site, James River, Virginia.

Appendix outlining the baseline inventory of terrestrial flora, fauna and sediment chemistry to accompany a report on habitat field investigations in the Bolivar Peninsula Marsh and Upland Habitat Development Site in Galveston Bay, Texas.

Appendix containing a preliminary ecological survey of terrestrial biotic resources at Nott Island, Connecticut to accompany a report on habitat field investigations of the Nott Island Upland Habitat Development Site in the Connecticut River, Connecticut.

Appendix containing supplementary analytical data to accompany a report on habitat development field investigations of the Windmill Point Marsh Development Site, James River, Virginia.

Appendix outlining the baseline inventory of aquatic biota to accompany a report on habitat development field investigations in the Bolivar Peninsula Marsh and Upland Habitat Development Site in Galveston Bay, Texas.

Appendix containing calculations of the mass transport of chemical components and the error terms used to accompany the second volume of a report on the environmental impacts of marsh development with dredged material as part of a study on the feasibility of marsh development using dredged material at the Windmill Point Marsh Development Site, James River, Virginia.

Appendix outlining the baseline inventory of water quality, sediment quality, and hydrodynamics to accompany a report on habitat field investigations in the Bolivar Peninsula Marsh and Upland Habitat Development Site in Galveston Bay, Texas.

Appendix containing supplementary tabulated data to accompany a report on habitat development field investigations of the Windmill Point Marsh Development Site, James River, Virginia.

Report regarding analysis of a lock and dam in the Arkansas River. "The purpose of this study is to take 8 years of instrumentation data from Lock No. 5 and report it in such a manner that it can be used later in other studies, such as a finite element analysis. Included is a discussion of the quality of the data and a brief comparison of measured values with design cases for several soil-structure interaction cases" (p. 5).

Final report documenting a high-sensitivity airborne gamma radiation and magnetic field survey of the Brownsville and McAllen National Topographic Map segments including a description of the program and results.

This report summarizes habitat development activities at the Nott Island Upland Habitat Development Site in the Connecticut River near Essex, Connecticut, including aspects of engineering, botany, soils, and wildlife.