In January and February, 1960, Lawrence Radiation Laboratory personnel conducted a series of experiments in Phase II of Project Cowboy in which tourmaline crystal transducers, located very close (3 to 50 feet) to tamped high explosive detonations, detected dynamic elasto-plastic stress waves generated in salt. The detonations occurred 110 feet below the 800-foot working level of the Carey Salt Mine, near Winnfield, Louisiana. These experiments were designed to measure dynamic stress conditions resulting from explosion in the earth media, of which little is known at present, and to provide data for comparative calculations on seismic disturbances from tamped explosions and from explosion in large underground cavities. Eleatic stress waves of 1 kilobar magnitude were observed, with velocities of about 15,000 ft/sec. Inelastic stress waves up to 6 kilobars in magnitude were measured. Velocities for these waves were in the range 9000 to 12,000 ft/sec.

Information on the metabolism of fission products in man has been obtained largely from studies carried out with parenterally-administered soluble salts of radioisotopes administered in medical treatment or in tracer studies. The recent development of the whole-body gamma spectrometer with its highly sensitive detection system has been of considerable value in extending these studies by providing data on very low levels of isotopes in man over long periods of time.

In the course of the cratering studies conducted as part of the Plowshare Program, the dependence of crater dimensions on depth of burst and the scaling laws relating crater dimensions to total energy release have been derived for chemical explosions in the desert alluvium of the Nevada Test Site. The desert alluvium is a lightly cemented sand and gravel, which was chosen for study because the first nuclear cratering explosions were fired in the medium and it was of interest to compare the nuclear and chemical explosion in the same medium. Shoemaker of the U.S. Geological Survey recently completed a detailed analysis of the Arizona Meteorite Crater and, through direct comparison with the nuclear explosion results in Nevada, arrived at an effective depth burst for the meteorite. He also reconstructed the original size and shape of the crater, and determined the limit of brecciation.

In discussion with a number of people at HAPO, KAPL and ANL a hypothesis has been evolved which appears to fit available information concerning irradiation embrittlement of uranium as well as indicate a possible solution to the problem. The purpose of this memorandum is to expound the hypothesis as an aid to those working with the problem. Since it imbodies the ideas of many people, no claim to unique authorship is implied.

The moderator fluid will be injected into the PRTR calandrin through injectors located between the shroud tubes and at the bottom of the calandrin. It is important that the size and arrangement of the injectors be such that complete mixing of the moderator will occur and prevent hot sports from forming in the moderator. Such hot spots could lead to undesired changes in the moderating characteristics due to boiling within the moderator. Also of importance is the requirement that the injector should not produce excessive turbulence at the moderator surface thereby complicating moderator level control. To determine the extent of moderator mixing within the calandrin, experimental studies were made employing a full scale PRTR calandrin mockup.

The small amount of irradiation tenting experience on the plutonium-aluminum type elements planned for the Plutonium Recycle Test Reactor (PRTR) has made such testing of great importance. The high temperature pressurized recirculating water 1706 KER facility is one possible place for conducting investigations of the irradiation behavior of this type fuel element. To obtain the maximum information from the in-reactor testing and to detect possible problems, out-of-reactor test both at room and anticipated operating temperatures must be made. Room temperature pressure drop measurements and high temperatures performance of two prototypical fuel element designs proposed for KER testing are reported in this document.

In the course of a general study of K- p interactions at 2.24 Bev/c incident K- momentum, we have investigated the following reactions, the experimentally detectable final states of Ξ Κ π system. In this report we shall discuss the possible existence of Ξ π resonances above 1530 Mev and the evidence for possible structure in the overlap regions. An evaluation of the isospin of the Ξ * will be made. In addition, production and decay angular distribution of the Ξ * will be presented.

The total number of neutrons emitted from various targets bombarded by high energy deuterons and protons was measured by using a solution of MnSO<sub>4 to thermalize and capture the neutrons. The methods of monitoring the number of particles striking the target and of calibrating the neutron detecxting apparatus are discussed in detail. Deuterons of energies to 230 Mev and protons of energies to 345 Mev were used. Targets ranging from lithium to uranium were used and were backed by secondary targets of uranium and thorium. The yields are expressed in terms of the number of neutrons emitted per incident particle. Uranium targets gave the highest yield.

Several tests are being performed and others being planned to investigate the role of heat transfer in corrosion processes. These tests are measuring both corrosion rates of metals (Zr-2 and X-8001 aluminum) under heat transfer, and the temperature rise associated with the buildup of the corrosion product. A brief description of these tests is given in this report.

The inelastic scattering of low energy neutrons from condensed matter offers a means of investigating the motions of atoms in liquids or solids down to times in the order of 10-12 to 10-13 seconds. The theoretical framework and techniques of such measurements are discussed and the results of cold neutron measurements with liquid H2O and Pb are presented. In H2O the neutron data show that for times in the order of 10-12 seconds the water molecule tends to maintain some average position with respect to its neighbors. In this sense the short time behavior of water is similar to that of a solid. Diffusion characteristic of a liquid occurs at later times. Measurements in liquid lead just above the melting point also show the same effect but not as markedly.

Programs are under way at Brookhaven National Laboratory to study the behavior of fission products released from reactor fuel materials. Major emphasis has been placed on fission product iodine because of the physiological hazard associated with the I131 isotope. A complete reactor safety analysis, considering either a slow or rapid release of fission products, requires a knowledge of the chemical and physical states of the fission products during release, the extent of their release, and an understanding of their chemical interactions with the reactor environment.

Prior to assembly into the 80" bubble chamber, the expansion system was subjected to a series of tests to check piston dynamics and gain information on the reliability of the various components. Furthermore, the rest provided operating personnel with the opportunity to become familiar with the operation and maintenance of the expansion system. Two separate tests were performed with the apparatus that was located at the north end of the AGS experimental area; one during the week of Oct. 15 and the other during the week of Nov. 12. The system was run with helium gas supplied from AGS compressor room and the piston was operated at room temperature.

When the design of the refrigerator was begun, one of the important parameters was refrigeration capacity required. In order to estimate the required hydrogen refrigeration load the following had to be considered: 1. Dynamic Load due to pulsing of the chamber. Although this has been determined some two years ago through test work, it has not been published as of this date and will be presented here. 2. Static losses due to conduction, radiation, and convection. This is covered by Eng. Note BC-03-0-B. 3. Cool-down requirements. This is covered by Eng. Note BC-03-0-C.

We have decided to try pressure-moulding coathangers, and this is a report on the specifications and tolerances R. R. Rau and I have calculated

These procedures are intended to be used for the initial operation of the expansion system and serve as a basis for a more complete and revised form to be written once operating experience has been gained. An attempt has been made to offer a logical and systematic presentation to facilitate operation and maintenance of the system by the operating personnel. Thus, the sequence of valve actuations has been presented in matrix and check list form to minimize errors; this also has the advantage of making it easier to adapt certain expansion system procedures to programmed control by a process control computer.

The purpose of this report is to compare multi-layer insulation and liquid nitrogen shielding as methods of insulating the 80-inch Liquid Hydrogen Bubble Chamber.

Reliability of individual components and the ability to produce refrigeration even if one or two of these components should be in operable are the prime design parameters of this cycle. Each component was looked at with these two parameters in mind and any item that had obvious objections was either rejected or backed up with another piece of equipment. Along this line, you will notice (refer to line schematic) two hydrogen compressors and two nitrogen compressors; for full capacity all are required. However, in the event of the loss of use of one of these compressors, it will still be possible to produce at least 50% of the rated capacity. To eliminate outside influences, the cycle was designed around what may be called a closed cycle cascade system; with the assumption that there is no loss of power, cooling water, the equipment can run indefinitely. The nitrogen and hydrogen cycles are of the Simple Linde type with pre-cooling making use of the Joule-Thompson Effect for the refrigeration produced. The low-temperature components of the cycle have no moving parts other than valves, consisting entirely of counter-flow heat exchangers to lower the temperature of the incoming high-pressure gas to a level where …

On the basis of measurements made upon analogues of the proposed magnet, it was decided that the distribution of ampere-turns between the two exciting coils should be in a ratio of about 1:33:1. This distribution is expected to minimize the variation of the magnetic field intensity over the depth. of the chamber. Simplicity of construction demands that there be an integral number of turns in each layer of conductors. If no water connections are to be made at the inside of the coils, each coil must contain an even integral number of layers.

GE is amending its application of 6/5/57 to construct and operate the Nuclear Test Reactor in order to incorporate changes in procedure and equipment.

The wrist badge provides a dosimeter that is useful in estimating the radiation dose to the hands and forearms. Its new shield system gives good gamma and slow neutron dose discrimination with duPont 552 film packets. The film can be evaluated using the present technique and equipment. Several attempts to develop hand dosimeters have been made. Finger rings using film have been used routinely but have not been entirely satisfactory for all situations. The wrist badge was developed to provide improved gamma and slow neutron dose measurement of the upper extremities under certain appropriate conditions. The wrist badge dosimeter is not a substitute or alternate for finger ring dosimeters but is a necessary dosimeter for some extremity exposure situations.

A disposal method is needed for wastes generated from the decontamination of the NPR primary coolant loop. The limitations imposed by facilities design criteria for the disposal of NPR wastes preclude direct river release of the spent cleaning solutions because of the anticipated quantities of radioactive material in these wastes. The soil at a 100-N Area trench or crib should not be relied on for removing radionucleotides by ion exchange or filtration because of the high salt content of the wastes and the presence of solubilizing reagents. Permanent or long term storage of large volume of decontamination wastes would be expensive. A waste treatment is sought for concentrating the radioactive materials to volume suitable for long term storage and which would permit dispersal of the excess liquid to the environs.

Continued operation of F reactor with high water collection rates during the past 12 years has resulted in numerous detrimental effects. In addition to promoting external corrosion tube leaks, water leaks have corroded the Gunbarrel to the biological shield donut assemblies and cast iron thermal shield blocks, thus preventing the majority of tubes in F reactor from unrestrained thermal expansion. Fatigue of the Van Stone flange under the resulting compression loads leads to eventual failure in some cases. In addition, excessive compression loads exerted against the nozzle gasket result in plastic deformation and eventual failures of the gasket.

The effect of the (n, 2n) and (n, o<) reactions on the neutron economy of a beryllium moderated reactor is investigated.

Storage of the fission products separated from the product streams of the Purex process is being accomplished using a smaller volume of accompanying solution than any other process here-to-fore used at HAPO. The operating technique and control mechanisms which are needed to store large quantities of these highly radioactive wastes are not yet fully understood, but considerable insight into the problem has been gained from the experience at Redox during the last 36 months. The basic intentions of the 241-A Storage Facility design is to control the boiling wastes by providing suitable tanks to contain the liquid and a vapor system provided with suitable seals to control the vapors. This document (Part I) will present a somewhat detailed description of the Purex Storage Facility and a review of the activities there before plant start-up. Part II, published under separate cover, contains a description of Waste Farm Technology including a process description and a recommended plan for operation.