The electromagnetic interaction of an intense relativistic coasting beam with itself, including the effect of a confining nonperfect vacuum tank, or a quiescent rf cavity, is investigated theoretically. It is shown that the resonances that may occur between harmonics of the particle circulation frequencies and the electromagnetic modes of the cavities can lead to a longitudinal instability of the beam. A criterion for stability of the beam against such longitudinal bunching is obtained as a restriction on the shunt impedance of the rf cavity, or the Q of the vacuum tank. This criterion contains the energy spread and intensity of the coasting beam, as well as the parameters of the accelerator. Numerical examples are given which indicate that in general the resonances with the vacuum tank will not cause instabilities, while those with an rf cavity can be prevented from causing instabilities by choosing the shunt impedance at a sufficiently low but still convenient value.

Recently a number of authors have suggested modifications of the Brueckner theory of nuclear matter so as to include hole-hole interactions, as well as particle-particle interactions. Iwamoto has demonstrated that in a perturbation theory calculation the inclusion of hole-hole interaction makes no change in the ground-state energy through second order. The singular two-body potential between nucleons makes it difficult, however, to conclude anything about the contribution of these terms in nuclear matter. The formal similarity between the equation of Iwamoto and the equation for the energy gap in nuclear matter, coupled with the fact that the energy gap is very small at normal density, indicates that the effect of hole-hole interactions is probably only a very small change in the ground-state energy of nuclear matter. It is the point of this note to show that this conclusion is in fact correct, the demonstration proceeding by use of the separation method for evaluating the energy of nuclear matter.

An extensive knowledge of the effect on the mechanical properties of metals of prolonged exposure to neutron radiation is considered necessary to properly establish design and operating criteria for in-reactor pressure tubes and test loops. An opportunity to obtain a limited amount of this information on Zircaloy-2 presented itself when, after two years of service, the pressure tubes were replaced in the RE reactor recirculating test facility. Three Zircaloy-2 tubes, with a two-inch inside diameter and 48 feet long, had operated intermittently with prototypical fuel elements at water temperatures up to 250 C (480 F) and pressures up to 1350 psi. During this period, the tubes received an estimated integrated neutron exposure of 1.9 {times} 10{sup 22} nvt. After the tubes were removed from the reactor, metallographic examinations, longitudinal-tensile tests, flattening tests, and burst tests were performed. In this report, the techniques for performing the burst tests are described and the results of the burst tests are compared with the results from tensile tests on coupons cut from corresponding locations along the tube.

A preliminary analysis of the adequacy of the ``Secondary`` and ``Last Ditch`` cooling systems at the Hanford reactors indicates that action will be required prior to the slimmer months if power level limitations are to be avoided. This analysis is based upon preliminary data from recently completed trip-out tests combined with cooling water requirements at present and CY-60 power levels. More complete data will be presented shortly in HW-64417, and final evaluation of test data will be expedited. The ``Secondary`` cooling system was found to have a high degree of reliability and to be of quite adequate capacity. The ``Last Ditch`` systems will be generally inadequate for the coming slimmer months, but may be significantly improved by relatively simple-changes.

Experimental data on tritium yield from lithium-aluminum pieces irradiated under PT-IP-255-A-9-FP have been reported previously. Experimental data on plutonium yield and U {sup 235} burnout in the E metal portion of one central zone striped E-N column are now available. These data are now reported. The combined data are compared to the experimental and theoretical values used in the economic analyses of the E-N loadings.

This report presents the results, conclusions and recommendations of a comprehensive study of the hazards potential of the 1706-KER in-pile recirculation loops, Although more data are needed to verify or refute certain tentative conclusions, the general conclusion of this report is: with the exception of severe coolant loop rupture incidents, especially process tube ruptures, the loops will not possess serious hazards potential when they are operated within the limits specified in the Process Standards as amended by the acceptance of the recommendations of this report concerning the pressurizer vent system and the process tube exit trips. The potential for fuel burnout or meltdown following a coolant loop rupture should be reduced considerably after completion of Project CGI-839, ``Modification to Fuel Element Test Facilities.`` The present potentially ``worst case`` coolant loop rupture could lead to an accident comparable in severity to a single K-Reactor tube rupture and meltdown. Serious personnel and property contamination would be confined to the vicinity of the reactor following completion of Project CGI-791, ``Reactor Confinement`` unless unusual atmospheric conditions persisted during the entire release time, i.e., strong, unidirectional winds causing rapid straight-line, non-mixing travel of the fission products plume. However, graphite stack damage from a tube rupture …

Subsequent to the recent formulation and adoption of safety criteria for reactor cooling systems, there appeared the need for an independent evaluation of the safety and reliability of the K-Reactor cooling system in terms of these criteria. The primary, secondary and last-ditch cooling systems of this reactor involve a strong inter-dependence between electrical and hydraulic components of the water plant. Because of the complexity of inter-relationships between these components, the analysis was divided into two parallel studies which were accomplished during the simmer of 1959. F. D. Robbins has presented his analysis of the electrical power and control system in HW-61887. This report deals with an engineering analysis of the hydraulic and mechanical aspects of the reliability and safety of the K-Reactor Cooling System. The system, as described in this report, is that which existed during the simmer of 1959, prior to modification under Project CG-775 (now Project CG-883).

The purpose of this preliminary project proposal is to request authority to perform the design work for modifications of the Purex Plant to provide a capacity equivalent to a ``4.0 capacity factor.``

The object of tests is to determine effect of high-humidity air on the physical characteristics of filter media and separators when the filter is mounted in the horizontal position. Usual installation is with the filter mounted vertically.