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This report addresses the absolute calibration, a technique used for calibrating shock pickups. This technique can be used for an applied motion regardless of its shape.

Complete parition functions for non-rigid rotators are obtained for the linear, spherical top, and symmetric top cases, From these are derived expression giving the corrections to the thermodynamic functions due to centrifugal distortion as functions of the rotational distortion constants D. Numerical examples are given for HCN, methane, and ammonia.

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This report is about the Calibration of Crystal Accelerometers Used for Vibration at Temperature Extremes - extracted from minutes.

This report addresses the interagency mechanical operations croup subgroup on environmental testing.

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Processing of multiple types of irradiated fuel elements in Purex has been proposed to the Atomic Energy Commission as a means of realizing significant savings in overall CPD operating costs for weapons programs and permitting release of the Redox plant for non-weapons programs. The process and equipment requirements for implementing a multipurpose operations program have been under study in both plant and laboratory programs for processing slightly enriched Zircalloy-clad uranium metal fuels and plutonium-aluminum metal alloy fuels. The purpose of this document is to present the results of a preliminary engineering study on the processing of irradiated NPR, E-Metal, D-Metal, and normal uranium fuels and PRIR and Pu-240 plutonium-aluminum alloy fuels and to provide process flowsheets as the basis for scope design of a project for increasing processing flexibility at Purex.

This report talks about the Alloying Characteristics of the Rare Earth Elements with the Transition Elements

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Currently the Irradiation Processing Department is working on a program which has as its goal the reduction of radioactive discharge to the Columbia River. The most significant radioactive isotopes of concern are the relatively long lived isotopes P{sup 32}, Zn{sup 65}, As{sup 76}, N{sub p}{sup 239} and Cr{sup 5l}. Because of their relatively long life they can be found in the Columbia River well below the Hanford Plant. P{sup 32}, because it is absorbed and concentrated by the river biota is of prime concern because the dose which it contributes to man through the eating of fish is not known for certain. Included in this reactor effluent decontamination study program are studies of process water recirculation systems, process water pre and post treatment methods, and effluent disposal to an artificial lake. This report reviews the artificial lake concept to determine its feasibility and possible effects on the concentration of radioactive isotopes in the Columbia River downstream of the Hanford Plant. The findings are based on the study and evaluation of available data. Meterological, hydrological, and biological absorption aspects of the artificial lake concept were studied several years ago. Little or no scientific work has been done in recent years to …

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In the Plant Improvement Program, it is proposed to retube the K-Reactors with standard size Zircaloy-2 smooth-bore process tubes and to charge self supported fuel elements starting March 15, 1964. The first step in support of this transition program is to confirm compatibility of the fuel-tube geometry and secondly to obtain fuel-tube performance information prior to full scale commitment of the K-Reactors to this design. In view of the testing of self-supported fuel which has been accomplished to date and that which is planned, there is little incentive to install more tubes in a K-Reactor than are required to make the fuel-tube geometry check. To accomplish this, ten tubes are viewed as the maximum number that would be required. This report presents the design of a test to fabricate and irradiate ``K`` self-supported fuel elements in limited quantities.

The Purex Plant has been requested to process Z-Plant MR and EPT solutions containing about 200 kilograms of plutonium in order to alleviate processing problem at Z-Plant and to reduce the inventory of MR and EPT rework. Campaign recycle of uranium through the main plant is recommended as an economical and effective means of reworking large quantities of Z-Plant plutonium solutions. This memorandum outlines process alternates and costs for reworking the solutions and itemizes specific recommendations for process and critical mass control.

This report contains an analysis of PCCF tube flow and Panellit pressure relations at DR reactor. Supply curves are presented at front header pressures from 480 to 600 psig using cold water and the standard 0.236 inch orifice with taper down stream and the pigtail valve (plug or ball) open. Demand curves are presented for slug column lengths of 200 inches to 400 inches using 1.44 inch O.D. solid poison pieces (either Al or Pb-Cd) and cold water with a rear header pressure of 50 psig. Figure 1 is a graph of Panellit pressure vs. flow with the above supply and demand curves and clearly shows the effect of front header pressure and charge length on flow.

I&E uranium cores are to be jacketed by Sylcor and Hanford utilizing the ``Solid State Diffusion-Hot Pressure Bonding`` process. Hanford will also jacket cores by the ``Solid State Diffusion`` process, by ``Gas Pressure Bonding`` and ``Hot Die Sizing``. In this process, a layer of nickel is placed between the aluminum and uranium to prevent diffusion of the aluminum into the uranium and furnish a layer of metal capable of limiting diffusion with both the aluminum and uranium. The completed fuel element therefore, consists of a uranium tube, bonded by diffusion to a layer of nickel which, in turn, is bonded to the aluminum can. The bond set up by the ``Solid State Diffusion`` process has excellent strength, ductility, continuity, heat transfer abilities and, based on off-site experience, should withstand the changes which take place during irradiation. The objective of this test are to determine gross dimensional stability and bond quality differences between the Al-Si bonds and solid state diffusion bonds.

This report discusses the delayed neutron characteristics of a reactor which are a function of the distribution of fissions in the various fissionable isotopes. The delayed neutron characteristics of the NPRL delayed fraction and decay constants, are presented as functions of exposure to 2000 MWD/T for both room temperature and operating temperature. It is of importance to note that the delayed neutron fraction decreases from 0.693% to 0.539% with increased exposure. Thus 22% less reactivity change represents a prompt critical condition at 2000 MWD/T, compared to the zero exposure condition.

In response to an inquiry by Euratom, estimates of the costs for the production of 85 kg of 15% Pu-240 metal and for the production of 15 kg of 25% Pu-240 oxide at HAPO were recently requested by the Atomic Energy Commission. In connection with this inquiry, comments were requested regarding the possibility of establishing and measuring product plutonium oxide ``sinterability`` parameters. This report presents estimates of the costs for separations processing by the Chemical Processing Department for the cases of interest. Process ground rules and any necessary assumptions are explained. In addition, the problems of measuring oxide ``sinterability`` are briefly discussed. Highlights of this study were previously transmitted to the Irradiation Processing Department for incorporation in a formal reply to the original Commission request. Subsequently, some adjustments in ground rules have caused cost changes which are included in this report.

This report details the borehole examination and inspection results of process tube 2959 following a massive fuel failure and a low flow trip which scrammed the reactor.

The intent of this document is to establish criteria for equipment for: Receiving, handling and component inspection; miscellaneous handling and storage; final inspection; and finished storage in the new fuel cladding facility.

This report presents the dose rates which were observed during the removal of a Zircaloy-2 process tube from C Reactor. The corresponding calculated activity is also presented for the purpose of correlation with the observed dose rate. The tube was removed on July 22, 1964, after having been irradiated by a neutron flux for 560 days (based on time operated efficiency). The tube activity was monitored with a super high range TP (0-5000 R/hr) by suspending a probe through an access port in the floor of the ``D`` machinery room. As tube 3353 was pushed and cut into sections, the highest activity observed was 675 R/hr, which was seen in the center three-foot segment. The corresponding calculated activity was 650 R/hr. The neutron flux profile, as shown by tube activities along its length, was extremely peaked in the center; for example, the area under the activity curve was less than one-third of the area under a cosine curve of the same amplitude and cycle length.

Purpose of this test was to evaluate the behavior of LiAl elements at N-Reactor operating conditions. The test was made to determine the swelling rate of the LiAl alloy, effect of irradiation on mass transport of lithium and tritium in the target assembly, and effect of Al surface treatment on transport of lithium and tritium.