"A convenient summary is given of useful formulas on the kinematics of high energy electron scattering together with a derivation of the relevant formulas for transforming from the center of mass to the laboratory system such parameters as scattering cross sections. The formulas derived hold for any two- body collision: the approximation (m = 0) employed for the electron scattering calculations is rigorously true for the elastic scattering of photons."

The general expression for the angular correlation between radiations produced in successive cascade transitions is derived by use of Racah algebra. The result is then specialized to the beta - gamma correlation and applied to two cases in which additional properties of the photon are specified, the circular polarization and the plane polarization. The prospect of testing time reversal and determining nuclear matrix element ratios by beta - gamma correlation measurements is explored using the nuclide Tm/sup 170/ as an example. The directional angular correlation between the 2.31-Mev beta and the subsequent 0.605-Mev gamma emitted in the decay of Sb/sup 124/ was measured as a function of the beta energy. The K-conversion coefficient of the 279-kev gamma following beta decay of Hg/sup 203/ was measured by comparing the x-ray and gamma intensities in a scintillation spectrometer. The measured valve of alpha /sub k/ = 0.195 plus or minus 0.014 indicates that the transition is M1 with E2 mixed to the extent of 63%. The angular correlation of the 107-1.24 Mev gamma cascade in Zn/sup 68/ following the decay of 68-min Ga/sup 68/ is shown. The Legendre polynomial expansion coefficients were deter-gular correlation in the decay of Sb/ sup 118/ was …

Potential methods have been examined for the reclamation of high boiler arising from the degradation of polyphenol materials in use as reactor coolants and moderators. To define the chemistry of potential reclamation processes, model polyphenol compounds were used. These include biphenyl, o, m and p-terphenyl, and p-quaterphenyl. Emphasis has been on hydrocracking, redistribution (reaction with benzene), and partial reduction. Preliminary study has been made of the application these techniques to high boiler from Santowax-OM used in the OMRE. The three methods show promise but require detailed investigation to minimize carbon formation to locate optimum operating conditions,.

The report covers work performed during the period September 1, 1959 through September 30, 1959. The general objectives of the program of "Studies of Reactor Containment" are to accomplish theoretical and experimental investigations of the loads to which external containment structures for nuclear reactors are subjected in the vent of a violent incident at the reactor core, the evaluation of methods of reducing that loading, and the study of the response of and design criteria for external containment structures as a result of such loading. Progress of technical effort during the report period is summarized for each of the eight tasks of the program.

This review lists some of the salient features of semiconductor particle counters and cannot claim to contain an exhaustive listing of all the work in the field. Performance results on the surface-barrier counters as developed at California Institute of Technology are included as typical for this type of counter, though comparable results have been obtained elsewhere.

The purpose of the test was to determine if failed blanket elements exist in other regions of the core beside F-2. FEDAL sampling ports that have indicted the greatest deviation as determined in a statistical analysis performed on a number of traverses in the FEDAL system will be tested. Data obtained from the start up runs of the FEDAL sample port Nos. 11, 31, 36 and 37 of Monitor 2 and port Nos. 14, 46, 11, 49 and 7 of Monitor 1 gave no indications of a blanket element failure. At each power increase, the radiation increase was normal with no signs of bursts or peaks of radiation which would indication the failure of a blanket fuel element.

The PWR Plant was operated at approximately 60 MW net electrical output for a total of 1000 EFPH from February 3, 1959 to March 28, 1959. During this period, while performing DL-S-225, there were two planned shutdowns, no safety shutdowns or safety insertions and one flux title. The performance of the plant was satisfactory during the period of the test.

Experiments are described which show that the velocity of compressional waves along a thin plate varies as a function of the frequency of the waves. In terms of transit times in aluminum the value is between 4.02 and 4.94 microseconds per inch.

Ultrasonic inspection for subsurface flaws is widely used in American industry. This report reviews the general principles and specific techniques of ultrasonic testing. The information is based on a review of the technical literature plus the experience of the Quality Assurance Department at Sandia Corporation in applying this nondestructive testing technique to quality evaluation programs.

The equilibrium and maximum override values for xenon and samarium poisoning have been computed using the recently issued effective cross sections of C. H. Westcott. Values are given as a function of specific power, neutron temperature, and epithermal flux content.

The use of the DD^3 amplifier with the RIDL 200- and 400-channel analyzers has been found advantageous for certain applications. In order to use the DD2, certain modifications to the input circuits of the Analog-to Digital Converter Unit are necessary. In addition, the modifications improved the linearity of the analyzer in the low channels. Using the analyzer with the RIDL Type 30-7 Scintillation Pulse Amplifier, it was noted that non-linearity of as much as 5 or 6 channels was present below channel 20. With the modifications made and with the use of the DD2, this non-linearity has been reduced to less than 1/2 channel.

The nil-ductility-transition (NDT) temperature, as defined by the Naval Research Laboratory drop-weight test, was determined on the A212B carbon-silicon steel used in the pressure vessel of the N. S. Savannah nuclear reactor. Correlations were made with the Charpy-V-notch impact energy at NDT. Specimens taken at two different thickness location from materials used in the upper closure head of the reactor vessel yielded NDT temperatures of 0 - 20°F which correspond to Charpy-V-notch impact energies of 11-19 ft-lb. Testing of as-received material used in the lower closure head indicated that the NDT temperature was 50°F which was equivalent to an average Charpy-V-notch impact energy of 12 ft-lb. After normalizing and stress-relieving this material, in order to more closely approximate the final condition of the reactor vessel, NDT was reduced to less than 10°F.

The preliminary process design of a PRFR pilot leaching plant, which is proposed to be located in Cell B of Building ORNL, is considered. Chemical, physical, and nuclear parameters are investigated in order that the leaching operations may be carried out without any chemical or nuclear hazards.

The Turco 4501 process is recommended for the decontamination of the PRFR pilot leaching plant equipment. The caustic-tartrate-nitric acid process is recommended for the decontamination of the cell and the equipment exterior.

The Lindemann assumption of direct contact of neighboring atoms at fusion is replaced by the criterion that melting occurs when the root-mean-square amplitude of thermal vibration reaches a critical fraction ρ, presumed the same for all isotropic monatomic solids, of the distance of separation of nearest-neighbor atoms. The Debye-Waller theory of the temperature dependence of the intensity of Bragg reflection of x-rays is used, without further assumptions, to derive a generalized Lindemann law. In contrast to the Lindemann form, all physical quantities involved in this formulation are evaluated at the fusion point, and departure of the average energy of an atomic oscillation from the equipartition value is taken into account by the quantization factor of the Debye-Waller theory. If the Grüneisen constant γm of the solid at fusion is evaluated by its definition from the Debye frequency of the solid, use of the generalized Lindemann law and Clapeyron's equation permits one to express γm in terms of the bulk modulus of the solid at melting and the latent heat and volume change of fusion. By means of Grüneisen's law applied to the solid at fusion, γm can be expressed likewise in terms of the corresponding bulk modulus, thermal expansion, volume, …

A generalization of the Fermi-Thomas model for application of mixtures. This study attempts to determine the equation of state of water up to pressure of 10,000 megabars and temperatures of several thousand electron-volts.

At the request of the Alloy Preparation Group, the Nondestructive Test Development Group investigated the feasibility of determining the clad thickness on Mark X MTR Fuel Plates. As the use of induced eddy-currents was considered to be the most promising approach, a prototype instrument and probe coil utilizing this principle was developed to measure clad thickness. The results of the investigation conducted with this instrument indicate that the clad thickness of this type of fuel plats can be measured to withing +- 0.001 in.

The experimental program described has had as its objective the determination of the pressure exerted by free fission gas in operating UO2-filled reactor fuel elements.

The countercurrent gas-liquid system BF3(g)—anisole·BF3(l) for the concentration of boron isotopes has been studied. The single-storage separation factor varies from 1.039 at 0°C to 1.029 at 30°C. Rate of exchange is rapid, and, with efficient contacting equipment, complete exchange may be obtained in less than 15 sec. A total separation of 1.525 has been realized in laboratory equipment. The critical-product reflux reaction is quite efficient. Only about 55 moles of BF3 remain in each million moles of effluent solvent under laboratory conditions. The vapor pressure of BF3 over the complex rises sharply as the temperature is increased. At 0°C the pressure is 150 mm Hg, and at 40°C the pressure has risen to 1800 mm Hg. From vapor-pressure measurements, an approximate upper limit of ΔH= -12kcal per mole of complex was calculated for the reaction [equation not transcribed]. Qualitative tests indicate good resistance of anisole to decomposition by BF3 under plant conditions. The uncatalyzed exchange of boron between BF3 and BCl3 was found to be too slow to be exploited in a countercurrent system. The single-stage, equilibrium separation factor for the Nitrox system is a function of acid concentration. At 26°C the factor ranges from 1.064 with 1 M acid …

The flux through a given region is proportional to the total lengths of the neutron flight paths that intersect that region. The analytical Monte Carlo procedure manufactured neutron flight paths and totaled the lengths of all paths intercepted by the regions illustrated in Figure 1. The procedure was designed to utilize the various symmetries in the lattice. / Consider a portion of the lattice whose planar cross-section is shown in Figure 5. If R is the region in which the flux is to be estimated and F the fuel rod in which the neutron originated, then flight path P results in an intercepted length whose reflection in the plane is L. On the other hand flight path P' intercepts R' with length L'. R' is not the region to be studied, but a translation of the flight path P' to F' would result in the neutron intercepting R. The origin in P was arbitrary. For each neutron originating in P another could, with equal probability, have originated in P' with parallel paths. Hence consulting L' in R' towards the total flux is equivalent to starting a neutron at P'. Thus consideration of all regions symmetric to R with respect to …

A tranistorized d.c. coupled amplifier having very good gain stability, as well as very low drift of the output d.c. level, has been designed. Low frequency input signals with an amplitude of .04 to 2 volts peak-to-peak, approximately, coming from a low impedance source (voice soil of a speaker system) are amplified to an approximate peak-to-peak amplitude of 4 volts. The output is intended to drive a load of the order of 100 kohm.

The feasibility of removing and recovering cesium-137 from various HAPO process solutions by precipitation of Cs2ZnFe(CN)6 has been demonstrated previously. Pilot plant studies of calcination and steam hydrolysis of non-radioactive Cs2ZnFe(CN)6 precipitates by members of the Process Equipment Development Operation are currently in progress. In support of these pilot plant studies, experiments were performed to determine the extent, if any, to which cesium volatilizes during calcination and hydrolysis of Cs2ZnFe(CN)6 precipitates containing cesium-137. Experimental procedures and results are presented in this report.

This report discusses the mathematical and statistical questions concerned with the estimation of a leak rate from data collected during a reactor containment vessel pressure test such as that performed on the PRTR vessel in May, 1959. A mathematical method is suggested in Section 3 for the construction of a total number of gas molecules in the containment vessel time series using vessel absolute pressure and temperature readings at several positions within the vessel. A formula for the precision of the series is given in terms of the individual instrument precisions. The question of accuracy and its relationship to the temperature gradient within the vessel is also considered.

It is desirable that a reactor exhibit a self-regulating effect. If this were not true any disturbance to the reactor would result in a continual increase in the magnitude of the disturbance and the reactor would be unstable. In this investigation the reactor is considered to have two reactivity feed-backs: metal temperature and water temperature reactivity effects. These two variables through a metal temperature coefficient and water temperature coefficient determine not only the reactor stability but also determine many operational characteristics.