The Experimental Boiling-Water Reactor (EBWR) was designed, built, and operated to provide experience and engineering data that would demonstrate the feasibility of the direct-cycle, boiling-water reactor and be applicable to improved, larger nuclear power stations; and was based on information obtained in the first test boiling-water reactors, the BORAX series. EBWR initially produced 20 MW(t), 5 MW(e); later modified and upgraded, as described and illustrated, it was operated at up to 100 MW(t). The facility fulfilled its primary mission - demonstrating the practicality of the direct-boiling concept - and, in fact, was the prototype of some of the first commercial plants and of reactor programs in some other countries. After successful completion of the Water-Cooled Reactor Program, EBWR was utilized in the joint Argonne-Hanford Plutonium Recycle Program to develop data for the utilization of plutonium as a fuel in light-water thermal systems. Final shutdown of the EBWR facility followed the termination of the latter program.

A comprehensive set of elementary functions has been implemented portably in Ada. The high accuracy of the implementation has been confirmed by rigorous analysis. Moreover, we present new test methods that are efficient and offer a high resolution of 0.005 unit in the last place. These test methods have been implemented portably here and confirm the accuracy of our implemented functions. Reports on the accuracy of other function libraries obtained by our test programs are also presented.

A conference at Argonne National Laboratory for executives and technical personnel in small and medium-size manufacturing companies summarized how materials evaluation and inspection by nondestructive methods are changing and broadening. The application of these rapidly emerging techniques in maintaining and improving the quality and competitiveness of manufactured products was stressed. Individual papers have been cataloged separately.

In horizontal flow through a rectangular channel, the channel cross section can be oriented so that the long side is either vertical or horizontal. The effect of cross-section orientation on the fluid dynamic characteristics of two-phase flow is of interest in plate-fin heat exchanger design because a heat exchanger can be similarly oriented to operate in either of the two orientations. An earlier study of two-phase flow patterns and frictional pressure gradients in a small rectangular channel with the channel cross section oriented with the long side vertical was performed and reported. This report presents the results of a complementary study of the same channel, but with the channel cross section oriented so that the long side was horizontal. Flow patterns were studied and a flow pattern map, using superficial gas and liquid velocities as co-ordinates, was developed. Measured two-phase frictional pressure drops were analyzed using the concept of two--phase flow multipliers. Results from the two channel orientations were compared. While there are some notable differences in flow patterns at low mass qualities and low mass fluxes, in the practical range of interest for plate-fin heat exchanger design the effects on frictional pressure gradient are minimal and the modified correlation …

Six alloys have been selected as candidate container materials for the storage of high-level nuclear waste at the proposed Yucca Mountain site in Nevada. These materials are Type 304L stainless steel (SS), Type 316L SS, Incoloy 825, P-deoxidized Cu, Cu-30%Ni, and Cu-7%A1. The present program has been initiated to determine whether any of these materials can survive for 300 years in the site environment without developing through-wall stress corrosion cracks, and to assess the relative resistance of these materials to stress corrosion cracking (SCC). A series of slow-strain-rate tests (SSRTs) jn simulated Well J-13 water which is representative of the groundwater present at the Yucca Mountain site has been completed, and crack-growth-rate (CGR) tests are also being conducted under the same environmental conditions.