This report describes a simple, efficient, and flexible program for cubic spline interpolation in one dimension, suitable for inclusion in the ANL Subroutine Library and in an interactive timesharing system. Most of the cubic spline programs already available either restrict the boundary conditions to knowledge of the first derivative at both end points, or require the second derivatives to vanish at these points. The program described here removes these restrictions and enables the user to adopt boundary conditions appropriate for his own problem. The advantage is demonstrated for the extreme case of interpolating the function x log (1/x), which has singularities in all its derivatives at x = 0.

The Met-L-X storage unit and fixed-pipe system performed adequately, but the distribution provided by the nozzles as located is not satisfactory. Relocation of the nozzles does not appear to offer much promise for improvement because the number of nozzles required would necessitate a piping array nearly impossible to design or install around existing equipment. It would leave little room for equipment to be protected in a new installation. The tests reported did not address the question of whether Met-L-X powder will extinguish a sodium fire even if properly applied.

This report was compiled at the Hanford Engineering Development Laboratory operated by Westinghouse Hanford Company, a subsidiary of Westinghouse Electric Corporation, for the United States Atomic Energy Commission, Division of Reactor Development and Technology, under Contract No. AT (45-1) 2170. It describes technical progress made in the Interlaboratory LMFBR Reaction Rate Program during the reporting period. The Interlaboratory LMFBR Reaction Rate (ILRR) program has been established by USAEC/RDT to develop a capability to accurately measure neutron-induced reaction rates for LMFBR fuels and materials development programs. The initial goal for the principal fission reactions, {sup 235}U, {sup 238}U, and {sup 239}Pu, is an accuracy to within {+-}5 at the 95% confidence level. Accurate measurement of other fission and non-fission reactions will be required, but to a lesser accuracy, between {+-}5 to 10% at the 95% confidence level. A secondary program objective is improvement in knowledge of the nuclear parameters involved in fuels and materials dosimetry measurements of neutron flux, spectra, fluence, and burnup. These accuracy goals for the ILRR program are severe; measurements of fast-neutron-induced reaction rates have not been rapidly moving toward this level of precision. Using a number of techniques in well established neutron environments of current interest for …

The Coulomb production of {Sigma}{sup 0} hyperons on uranium and nickel nuclei has been measured in a beam of {Lambda} hyperons at the CERN Proton Synchrotron. The results for the {Sigma}{sup 0} lifetime, {tau}{Sigma}{sup 0} = (0.58 {+-} 0.13) x 10{sup -19} sec, and for the {Sigma}{sup 0}-{Lambda} magnetic transition moment, |{mu}{Sigma}{sub {Lambda}}| = (1.82{sub -0.18}{sup +0.25}) nuclear magnetons, are in agreement with SU(3) predictions.

In this project we propose to measure: (1) the elastic differential cross-sections of 100-500 GeV protons in (p,p) collisions by use of nuclear emulsions, and (2) the energy spectrum and d{sigma}/dEd{Omega} of the light fragments {sub 1}H{sup 2}, {sub 1}H{sup 3}, {sub 2}He{sup 3}, {sub 2}He{sup 4} in (p,N) collisions at the same energy range using the electronic E-{Delta}E detectors.

Gaseous and liquid wastes released from the 200 Area from 1965 through 1971 are presented. Recommendations are given to provide facilities and/or modifications to existing facilities which will reduce the radioactivity discharged to the ground. (TFD)

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During the quarter covered by this progress report (December 15, 1971 to March 15, 1972), the effects of variations in arterial pressure and heart rate on cardiac ouiput, efficiency as measured at the heart diaphragm, maximum air chamber pressure, average input power to the heart diaphragm, maximum blood chamber pressure and volumetric efficiency have been determined at various atrial pressures for a 7 cm base Kwan-Gett artificial heart made of smooth Silastic and equipped with Silastic flap inflow and Silastic tricuspid outflow valves. One animal experiment has been completed in which the in vitro measurements made on the artificial heart were verified in vivo. A second animal experiment in which the output power of the artificial heart will be determined over a long period of time is now in progress. Preliminary consideration has been given to the establishment of a nuclear powered artificial heart system in vitro test program. A preliminary design of an artificial heart to be driven by a nuclear engine has been drawn. (auth)

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Within the past few months two excellent summaries sup{(1,2)} of the state of our knowledge of the weak interactions have been presented. Correspondingly, we will not attempt a comprehensive review but instead concentrate this discussion on the status of CP violation; the question of the neutral currents, and the weak equivalence principle.

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The irradiation behavior of reactor graphites at high temperatures (500/sup 0/ to 1400/sup 0/C) to high fluences (up to 4 x 10/sup 22/ n/cm/sup 2/) is reviewed. Recent data generated during the period 1965 through 1971 are emphasized. The review covers graphite manufacture, irradiation damage, dimensional and structural changes, thermal expansion, thermal conductivity, Young's modulus, strength, and irradiation-induced creep.

This report describes a simple, efficient, and flexible program for cubic spline interpolation in one dimension, suitable for inclusion in the ANL Subroutine Library and in an interactive timesharing system. Most of the cubic spline programs already available either restrict the boundary conditions to knowledge of the first derivative at both end points, or require the second derivatives to vanish at these points. The program described here removes these restrictions and enables the user to adopt boundary conditions appropriate for his own problem. The advantage is demonstrated for the extreme case of interpolating the function x log (1/x), which has singularities in all its derivatives at x = 0.

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This is the final report for the work performed on Aerojet Nuclear Systems Comany Purchase Order N-900104, "Creep of AISI 347 Stainless Steel in Gaseous Hydrogen."

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