Reported are: physics (B Pile, D Pile, F Pile, general physics); and water, corrosion and engineering (process water control and pressure drop studies, corrosion, graphite expansion).

This document contains information concerning the dissolved oxygen content of the Columbia River and Yakima Rivers near the Hanford Production Reactors on May 3, 1946. Data is presented in graphed form with weekly variations plotted.

The necessity of complete removal of all the radioactive isotopes of iodine was discussed in general terms in the document Iodine Conditions in Connection with Rain Production.'' It is the purpose of this document to enlarge upon this phase of operation. Calculations of maximum permissible dose of Iodine 131, 132, 133 and 135 have also been performed. 3 tabs.

None

None

The results of a multi-group, diffusion type code computation for the fast neutron flux distribution in C, K, and N reactors are presented. Relative Ni activations in conjunction with the calculated neutron spectra are used to obtain values for the integrated fast flux per MWD/AT for C and K reactors. The relative, theoretical, integrated fast flux values at the same adjacent fuel powers in C, K, and N reactors in the mid-plane of the filler layers are: (1) C = 1.0; (2) K = 1.3; and (3) N = 2.6. For C reactor, the best estimate of the integrated fast flux per MWD/AT is: 5.0 {times} 10{sup 16} nvt (> 1 MeV) = 1 MWD/AT.

The high pressure loop installed in the 3X3 reflector position of the ETR and the associated instrumentation to detect and study failure mechanisms handled the rupture tests without difficulty. Failure of the elements was initiated by shearing off a projection on the fuel elements. The first test of the series used previously unirradiated seven-rod clusters. After the projection was sheared off the fuel elements were operated for seven hours with no failure. Failure is defined as having occurred when sufficient uranium oxide has formed to split open the cladding and release large amounts of fission products into the loop water. The second and third tests used fuel which had been irradiated to 2400 MWD/T at Hanford prior to insertion into the ETR. The second test was operated for 14 hours after the projection was sheared off--again with no failure. The third test was operated for only 33 minutes after the projection was sheared off before fission product activity in the loop water caused the test to be terminated.

C Reactor horizontal control rods were originally designed to have 32 feet of poison, made of 64 six inch ``cans`` each consisting of two concentric cylinders sealed at each end and the annular space between them filled with boron carbide powder. It was discovered before startup that under irradiation the neutron, alpha reaction in the boron could cause a pressure buildup and rupture of the sealed section. As an expediency cylinders wrapped with 72 miles thick cadmium metal were substituted for the boron ``cans`` and the pressure buildup problem was eliminated. However, since for a unit volume, natural cadmium contains fewer high cross-section nuclei than natural boron, the lifetime of one of these cadmium rods in Hanford flux levels is limited. Five of the original 15 cadmium rods were replaced in 1957 with boron rods of improved design. The primary purpose of this document is to present the results of a study to evaluate the extent of burnout in the remaining ten cadmium rods and their present rate of burnout so that replacement can be scheduled before these rods start losing significant reactivity poisoning effectiveness.

Localized cladding instability or necking has resulted in failures of the Zr-2 cladding of rod cluster and tubular fuel elements and fuel rods in NaK filled capsules. The cause of this non-uniform cladding strain is thought to be a combination of the effects of irradiation and nonuniform cladding thickness. To determine the influence of these two factors and that of temperature on the susceptibility to failure, and to obtain data related to cladding thickness tolerances for the NPR fuel elements an irradiation experiment was designed. This experiment consisted of eighteen capsules each containing three Zr-2 clad uranium rods. Cladding thickness variations of up to 25 percent were introduced in the cladding by machining ``grooves`` longitudinally on the outer surface. The temperatures of the cladding were established by the thickness of the capsule wall. These capsules, charged in DR Reactor in October 1961, were prematurely discharged after five days irradiation because of a rupture. The cause of the rupture was established to be overheating and accelerated corrosion of the Zr-2 capsule body as a result of inadequate coolant to the capsule surface.

One of the problems which may be encountered in the operation of NPR, or of any similar pressurized-water reactor, is the deposition of crud in the reactor core, particularly on the surfaces of the fuel elements. This crud consists primarily of iron oxides resulting from the corrosion of the piping. It has generally been found to deposit preferentially in a radiation field such as is present in the reactor core. Such deposition is undesirable for two reasons. First, the crud will become activated, and on subsequent release may create radioactivity levels in the ex-reactor components of the primary loop high enough to be a hazard to maintenance and operating personnel. Secondly, the crud deposit is a poor conductor of heat, and even a rather thin film can raise the cladding temperature by 100 -- 200{degree}C and result in accelerated corrosion of the cladding.

None

None

This document, dated May 3, 1966, presents data from the zirconium tube sample evaluation program at the Hanford Reservation. Data presented includes: (1) operating history, (2) flow characteristics, (3) time in core, and (4) average temperature for numerous samples. The document consists entirely of data.

This report itemizes the irradiations performed by Testing for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.

The results are reported of a literature search for information concerning the heterogeneous, gas phase, catalytic hydrogen-oxygen recombination. Laboratory scale experiments to test the performance of specific metal oxide catalysts under conditions simulating the atmosphere within a nuclear reactor containment vessel following a loss-of-coolant blowdown accident are suggested.

An elementary description is given of the basic vocabulary and concepts associated with finite difference modeling. The material discussed is biased toward the types of large computer programs used at the Lawrence Livermore Laboratory. Particular attention is focused on truncation error and how it can be affected by zoning patterns. The principle of convergence is discussed, and convergence as a tool for improving calculational accuracy and efficiency is emphasized.

Each paper in the volume has been separately abstracted and indexed. (DG)

Specifications are reported which were developed for several epoxy resins and hardeners used in filament winding. The specifications are concise, aimed at testing convenience, and contain the minimum number of tests necessary to define the material.

Some recently discovered regularities in the spectra of heavy elements which are also applicable to the analysis of the spectra of lighter atoms are described. It is pointed out that stepwise resonant multiphoton methods are irreplaceable tools in the study of high lying states in a complex atomic system. Systematic applications of these methods has permitted regularities to be observed which also hold for the lighter elements. It is noted that greatly increased understanding of the excited state structure of heavy atoms is not possible. 8 references. (JFP)

The space charge detuning of a dc beam due to electrons trapped is shown to be essentially energy independent. This leads to a curvature in the ..nu.. vs p relation. Left uncorrected, this would result in a "brick-wall" instability. It is shown that the strength of octupole field required to correct the curvature increases as the third power of the energy. Thus, large octupole correction coils are needed. The possibility of using stronger sextupole corrections to reduce the octupole requirement is suggested. However, this would mean that the working line would not shrink with energy, and ISABELLE would be required to operate with a tune spread greater than or equal to 0.02 even at 400 GeV.

The DT fusion neutron irradiation of eleven BNL-LASL superconductor wires, six LASL Spinel, Al/sub 2/O/sub 3/, and YAG crystals (two of each), six NRL five 9's crystalline, tetragonal GeO/sub 2/ samples and four LASL-IIT high purity single crystals (MgO, YAG, Spinel and Al/sub 2/O/sub 3/) is described. The sample position, beam-on time and neutron dose record are given. The maximum neutron fluence on any sample was 1.87 x 10/sup 16/ neutrons/cm/sup 2/.

The DT fusion neutron irradiation of eleven BNL-LAST superconductor wires, six NRL GeO/sub 2/ crystals, two YAG, two Spinel and two Al/sub 2/O/sub 3/ crystals for LASL and four LASL high purity single crystals of MgO, YAG, Spinel and Al/sub 2/O/sub 3/ is described. The sample position, beam-on time, and neutron dose record are given. The maximum fluence on any sample was 1.51 x 10/sup 16/ neutrons/cm/sup 2/.

Because groundwater movement can have important effects on buried nuclear wastes, hydrologists need to know if future climatic changes will influence the accuracy of groundwater flow calculations. Groundwater recharge (and therefore groundwater flow) depends on surface water balance. (Surface water balance equals precipitation less losses to evaporation, runoff, and storage.) To develop input data for modeling future climatic effects, we have made the following simplifying assumptions: (1) Climate (and therefore water balance) will behave in the future very much as it has in the past. (2) Groundwater recharge responds linearly to precipitation. (3) Future long-term climatic changes can be classified into groups or regimes that are similar to those of the past. Our current research is aimed at providing input data to the Waste Management Program's site suitability task. 16 figures, 1 table.

None