An experimental method is described which utilizes a simple Fermi-type chopper and conventional time-of-flight techniques in conjunction with an electron linear-accelerator pulsed neutron source to study inelastic scattering of thermal neutrons from liquid para- and ortho-para-hydrogen. The overall general agreement between theory and experiment supports the concept that the molecules in liquid hydrogen behave nearly as they would in a perfect gas. For liquid ortho-para-hydrogen, however, the extra broadening of the energy distribution of scattered neutrons suggests that some effects of the liquid state may be present. Similar observations on para-hydrogen indicate that, in this liquid as well, the motion of the molecules is affected by weak intermolecular forces. (auth)

A thermal and hydraulic design investigation of the Pathfinder Reactor, including analytical and experimental determinations, as well as a complete set of performance calculations, was carried out. A detailed analysis of the reactor energy balance was conducted. Results of the analyses indicated that the reactor will perform within the limits of the material design criteria and operational requirements. Fuel element temperatures are not excessive under the worst combination of circumstances. Thermal stresses in the superheater were minimized by designing the annular element so that temperatures are kept as uniform as possible at every axial location. In all cases, sufficient heat dissipation capacity was found to exist to ensure an ample margin of safety. (M.C.G.)

A reference pulse generator, transistorized timedifference-to-pulse- height converter, and beam pulse scaler are described and discussed as to their function in the fast neutron time-of-flight system for use with cyclotrons, The system is used for angular distribution and cross section measurements. Results are presented showing time resolution, absolute counting efficiency, and beam pulse scaling of the system. (N.W.R.)

A list is presented of subject headings used by the U.S.A.E.C. Division of Technical Information for indexing literature in the field of nuclear science and technology. (C.H.)

Research and development progress is reported on chemical-metallurgical processing, fuel cycle applications of voiatility and fluidization techniques, calorimetry, reactor safety, energy conversion, determination of nuclear constants, and routine operations. (M.C.G.)

The Oak Ridge National Laboratory has three generalpurpose research reactors which accommodate testing loops, target irradiations, and beam-type experiments. Since the experiments must share common or similar facilities and utilities, be designed and fabricated by the same groups, and meet the safe safety criteria, certain standards for these have been developed. These standards deal only with those properties from which safety and economy of time and money can be maximized and do not relate to the intent of the experiment or quality of the data obtained. The necessity for, and the limitations of, the standards are discussed; and a compilation of general standards is included. (auth)

References applicable to the problems of transponting charged particles in the areas external to accelerators are presented. The 891 references cover the period 1949 to 1981, with a few references both prior and subsequent to this period included. Part I is concerned with the more general aspects of electron optics. Part II contains the references that deal more directly with applications to particle accelerators. Arrangement within each pant is by broad subject with cross references listed at the end of each section. An author index is included. (M.C.G.)

Containment of the ORR is attained by means of a ventilation system which is capable of exhausting air from the building at a rate sufficient to ensure that all leakage of air at ground level is into the building. The exhaust air is treated by scrubbing and filtration and is discharged from a large stack at a height and velocity sufficient to guarantee that meteorological dispersion will reduce the resulting concentration of radioactive material to an acceptable level. Factors involved in selection of this type of controlled containment are discussed. Original design and modifications are described. Performance is also discussed. (M.C.G.)

Sections are included on reactor project activities, materials properties, metal and ceramic fabrication, applied research, and fundamental research. Separate abstracts were prepared for each section. (J.R.D.)

The over-all design and operation of ORR is reviewed in the light of four years of operating experience. Items discussed consist of the reactor components and instrumentation, reactor and pool cooling systems (including system cleanup), the emergency systems for electric power and reactor cooling, the waste-disposal systems (liquid, gaseous, and solid), and the building, itself. The ORR was the first of a class of reactors which combined the features of both the pool-reactor and tank-reactor types. Four years of operation indicated areas where problems of various degrees have developed. These problems are discussed. (auth)

The theory is presented in detail of an activation method for measuring the ratio of U/sup 238/ absorptions to U/sup 235/ fissions in a nuclear reactor. The origin of the activities is discussed, the equations are given for interpretation of the measurements, and the expected counting rates are computed for a typical experiment in the EGCR. (auth)

Six polymorphs of UO/sup 3/ were prepared and were identified by x-ray diffraction techniques. Differential thermal techniques were used to study the decompositions of the polymorphs to U/sub 3/O/sub 8/ and to investigate the modes of formation of the polymorphs from the hydrates of UO/sub 3/. (auth)

Reactivity lifetime calculations were made for an 800Mw(t) pebble-bed reactor on the basis of a batch-fueling cycle, a once-through equilibrium cycle, and a gradedexposure equilibrium cycle. The maximum lifetime, obtained with the graded-exposure equilibrium cycle, was 1.41 fissions per initial fissionable atom. In this case the conversion ratio was 0.62 and the neutron leakage from the core was 0.078. The same fuel composition gave 1.29 fissions per initial fissionable atom on a once-through equilibrium cycle and 0.92 fissions per initial fissionable atom on a batch cycle. (auth)

Activities in a project aimed at the improvement of fuel elements for high flux test reactors are reported. The investigation of new fuel compositions, distributions, and geometries is being undertaken to increase fuel life, to improve the flux distribution, and to provide a means of safely reaching higher reactor operating power and power density in these reactors. The effects of nuclear irradiation on the fuel and structural materials is being studied to predict the performance of these materials in more advanced reactor designs. A summary of the past year's progress is given and the fabrication and irradiation of samples containing up to 50 wt % U--Al alloys, cermets of UO/sub 2/, U/sub 3/O/ sub 8/, UC, UN, U/sub 3/Si, and Al, clad in various Al an d Be--Al materials is described. The use of ThO/sub 2/ and Th cores, the addition of BeO to cermet cores and high density fuei cores of U--Al intermetailics produced by powder metallurgy techniques were studied during the year. High strength APM claddings involving Al/sub 2/O/sub 3/ contents from 8 to 10% were tested and indicate the need for improved quality control of the APM material. Duplex claddings involving burnable poison layers and APM clad …

The following quarterly report covers the period from May 16 to August 15, 1962. This report summarizes the progress being made on the study of the saturation and recovery of the hole which can be burned into the magnetic resonance band associated with the F-center in KCl.

In order to evaluate entry into the atmosphere of an oblate (equatorial bulge) earth a standard atmosphere was used in conjunction with the standard rotating oblate spheroid. The density variation encountered in any one polar orbit around the earth will vary by about a factor of ten, due to oblateness. Therefore, the important effects on the re-entry trajectory are atmospheric density and oblateness of the earth. The SNAP configuration burn up characteristics will differ considerably between the steep (6/sup 0/) entry of the NASA Scout test and the orbital decay trajectory. However, the test can verify heat transfer rates on the actual configuration, and by proper calculation of material response, the actual decay breakup prediction can be improved.

None

None

None

A CIIIE (enriched) element, one of two elements which failed April 5, 1962 in tube 2955C, was shipped to the Radiometallurgy Laboratory for detailed examination. The element was 21st from the downsteam end. A more severe rupture which occurred in the 19th piece from the downsteam end was believed to have caused the initial rupture indication. After a hot startup a heat cycle developed in the part of the reactor containing tube 2955 increasing the bulk water temperature about 20 per cent. At about the same time the temperature rise was noted, the first rupture indication was seen. The reactor was shutdown 40--45 minutes later, tube 2955 was pushed, and the two ruptures were found. The element was classed as a ``hot spot`` failure. Detailed examination was requested to determine the cause of failure and characterize the nature of any observed corrosion.

This report, for July 1962 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and safety and security.

This is the monthly report for the Hanford Laboratories Operation July 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

The interim report included an analysis of those E-N case and blanket loading conversion ratio data which were available at that time, and an extrapolation of those data to expected, optimum, E-N operating conditions. Since issuance of the interim report further tritium yield data have become available from extraction of the tritium from the lithium-aluminum slugs irradiated in the second E-N core loading, and from the large batches of lithium-aluminum slugs irradiated as part of the blanket loading. Since these data complete the planned program of tritium analyses for the E-N demonstration load, it is felt appropriate that they be reported at this time. No further plutonium yield data have been received since issuance of the interim report and for this reason the plutonium conversion ratio is still tentative. It may be different when data from the second core test loading has been received.

The purpose of this report is to transmit revised goal exposure plans for normal production material. These plans supersede previous recommendations. Inherent in these plans are the assumptions: (1) The plant must produce a product containing six percent Pu-240, and (2) product blending capabilities are such that there are no restrictions, other than economic, on Pu-240 buildup at an individual reactor. Due to recent assessed changes in metal performance and conversion of DR Reactor to bumper natural material, revision of recommended goal exposure plans is called for. During the past year a significant shift in the relative metal performance between reactor types occurred. You may have observed the low rupture frequency at the C and K reactors compared to the rupture frequency at the old reactors. Based on the observed experience, goal exposures should be raised for C and K material and lowered for old reactor material. The goal exposure plans recommended herein are based on present, July 1962, assessed rupture performance and the latest conversion tables, incremental metal costs and burnout cost data. The current reactor optimization program was used to determine optimum goal exposures.