The UDD sensor bar with modified cross-section (0.0938-in. thick by 0.25-in. high overall) was analyzed to determine its resonant frequencies. Thermal and fluid-induced stresses due to steady-state and LOCE loads were also calculated. The sensor bar was shown not to be subject to vortex-shedding lock-in and was shown to meet applicable criteria of the ASME Boiler and Pressure Vessel Code. Seismic loads are insignificant compared to fluid loads.

This report was prepared for the DOE Nuclear Data Committee and covers work performed at ORNL since April 1978 in areas of nuclear data of relevance to the U.S. applied nuclear energy program. The report was mostly generated through a review of abstracts of work completed to the point of being subjected to some form of publication in the open literature, formal ORNL reports, ORNL technical memoranda, progress reports, or presentation at technical conferences. As much as possible the complete abstract of the original publication is reproduced with only minor editing. In a few cases progress reports were written specifically for this publication. The editors have selected the materials to be included in this report on basis of perceived interests of DOE Nuclear Data Committee members and cannot claim completeness.

The proceedings are presented of a Geothermal Commercialization Workshop conducted by the Division of Geothermal Resource Management, Department of Energy. The workshop was held in January-February 1979 at The MITRE Corporation facility in McLean, Virginia. The workshop addressed geothermal hydrothermal commercialization achievements and needs in the areas of Marketing and Outreach, Economics, Scenarios, and Progress Monitoring.

Research is reported on fracture mechanics analyses and investigations, effect of high temperature primary reactor water on subcritical crack growth of reactor vessel steels, investigations of irradiated materials, pressure vessel investigations, and thermal shock investigations. (FS)

Sputter deposition of metals with a negative substrate bias results in a deposit containing relatively large concentrations of the sputtering gas. This phenomenon has been applied as a technique for storage of the radioactive gas, /sup 85/Kr, which is generated in nuclear fuels for power production. Alloys which sputter to yield an amorphous product have been shown to contain up to 12 atom % Kr (42 cm/sup 3/ of Kr(STP)/g of deposit; concentration equivalent to a gas at 4380 psi pressure). Release from these metals occurs at so low a rate that extrapolation to long times yields a /sup 85/Kr release at 300/sup 0/C of about 0.06% in 100 years. A preliminary evaluation of the engineering feasibility and economics of the sputtering process indicates that /sup 85/Kr can be effectively trapped in a solid matrix with currently available techniques on a scale required for handling DOE-generated waste or commercial reprocessed fuels and that the cost should not be a limiting factor.

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Separate abstracts were prepared for the ten sections of the report. The report also includes lists of publications, theses, professional activities, and organization charts. (HLW)

Multistep Hauser-Feshbach calculations with preequilibrium corrections were made for neutron-induced reactions on yttrium and zirconium isotopes between 0.001 and 20 MeV. Recently new neutron cross-section data have been measured for unstable isotopes of these elements. These data, along with results from charged-particle simulation of neutron reactions, provide unique opportunities under which to test nuclear-model techniques and parameters in this mass region. A complete and consistent analysis of varied neutron reaction types using input parameters determined independently from additional neutron and charged-particle data. The overall agreement between calculations and a wide variety of experimental results available for these nuclei leads to increased confidence in calculated cross sections made where data are incomplete or lacking. 75 references.

The bibliography contains 1067 citations from the literature of critical and near-critical nuclear experiments. It provides an up-to-date index to reports containing useful data for many types of criticality studies. Most of the reports can provide specifications for relatively simple critical configurations necessary for validating nuclear constants and calculational techniques. The reports of more than 1143 experimentors at 38 international facilities since 1943 are cross-referenced. The collection contains the prototypes of many different designs of nuclear reactors and studies performed to insure the safe use of fissile materials in chemical processing plants, storage facilities, and transportation containers. The bibliography has three volumes. Volume 1 contains the main listing of citations with abstracts. Volume 2 is a set of indexes organized by report number, publication date, experimental facility, and author name. Volume 3 provides a subject index, concorded on the significant keyphrases derived from titles, and an index of keyterms derived from titles, and an index of keyterms extracted from titles and abstracts. The bibliography was printed by computer as a selection from a computerized system at Lawrence Livermore Laboratory contaning information and data on criticality experiments.

The goals of this project were: (1) To train twenty teams, each from a different region, to organize and run workshops to build inexpensive, practical solar greenhouses. (2) To help create working solar greenhouse experts in the field available to respond to their community's needs. (3) To establish a national model program for solar greenhouse construction workshops. (4) To determine whether the barn-raising style used in the greenhouse construction workshops could be taught in the format of a 3 1/2 day seminar with a follow-up workshop. (5) To determine whether the audio-visual exhibit and printed materials used in the seminar were effective. (MOW)