This report discusses the Production Test 105-2-P (Supplement A) -- Activity of Pile Discharge Water. Previous studies of pile discharge water have shown that one of two processes is responsible for the large but variable amount of Mn{sup 56} activity present in the water. One process is the production of Mn{sup 56} by the reaction Mn{sup 55} on manganese impurity in the water. The amount of such impurity has been shown to be too small to produce the observed amount of Mn{sup 56} unless the mean irradiation time is increased by a large factor due to temporary sticking of manganese on the surfaces in the tubes. The other process is the production by the reaction Fe{sup 56} on iron in the film. The present production test was designed to determine which of these processes is responsible for the troublesome Mn{sup 56} activity and to what extent the activity is increased due to sticking of manganese or iron in the tubes. 4 figs.

The success attending the use of azaserine as a specific inhibitor of one atage in the metabolic pathway leading to the synthesis of inosinic acid in pigeon liver prompted us to use this antibiotic in a similar attack on purine synthesis in Scenedesmus. However, investigation of the products produced during photosynthesis by suspensions of these algae in the presence of azaserine showed that a more widespread interference with metabolism had occurred. The purpose of this communication is to describe the nature of these effects and to attempt to assess their importance in a general picture of the metabolic effects of azaserine.

This report discusses research and engineering work on the purex and redox processes at the Hanford Engineering Works in May, 1959. (JL)

The objectives of the test described in this report are to evaluate the integrity of I & E MINT fuel elements canned by the ``C`` process to determine the conversion ratio of I & E geometry E-N ``striped loadings,`` and to provide a demonstration loading for a full reactor loading incorporating a ``striped`` center loading and a fringe ``blanket`` loading. This test will involve two portions a 26 tube block loading of I & E enriched uranium and MINT fuel elements arranged in a striped array, and a 10 tube fringe blanket loading of MINT fuel elements supported by the required enriched uranium fuel columns, and accompanied by controls. Either portion may be charged independently.

This document consists of information about the cooling systems of Hanford Production Reactors. It is the purpose of this letter, written May 8, 1961, to update recommendations of high-tank temperatures required to insure acceptable high-tank backup support. It does not appear practicable to relate the somewhat arbitrary standards of reference for backup support to process operating limits, i.e., reactor power levels, particularly as a mandatory requirement. For this reason, we have chosen at this time not to include these limits as a process standards` requirement. Considerable emphasis should be placed on insuring that the high-tank backup support be maintained in the maximum practical manner. Tables are attached showing high-tank temperature versus reactor power level relationships to satisfy the intent of our backup criteria and, through compliance, will insure that high-tank flow rates will be adequate during a reactor emergency following the loss of electrical power and steam.

Nine inch long aluminum clad Li-Al alloy target elements contained in 35 miI wall Zr-2 cans are authorized for irradiation in KER-1 and KER- 2 for up to 150 equilibrium operating days. The Li-Al elements will be irradiated in 1.9 inch OD, 1.5 inch ID Zr-2 flow distributing sleeves. Normal N inner fuel elements in Zr-2 sleeves will included in the tube loadings to provide sufficient heat to maintain the loop at the desired operating temperature.

It was stated by HAPO representatives at meetings held in Washington and Savannah River on May 1st and 2nd, that roughly 200 kgs of Pu of 18 percent Pu-240 could be furnished by July 1, 1965 to Savannah River for their proposed Cm-244 program. The Pu would be produced by irradiating .2 percent U-235 depleted uranium for a period of roughly ten months. The reactivity required for the depleted uranium irradiation would be furnished by .947 percent U-235 enriched uranium. Nine tons of slightly enriched uranium would be required for each ton of depleted uranium during its complete irradiation. To implement this program to deliver Pu of high isotope content by July 1, 1965 will require immediate internal program approvals and appropriate implementation steps. These steps will include design and specification of the depleted uranium ordering appropriate quantities of E and depleted; determining and ordering appropriate canning components; and determining reactor loading patterns. Special attention will ultimately be required in the separation of the reactor products. The additional quantities of E-metal required for the loading will probably necessitate early installation of the annular type Purex dissolver.

This report gives the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. These data are given in table form. For further description of column headings and the current discharge goal exposure plan refer to Document DUN-1048.

While the safety status of the Richland facilities has in the past been deemed adequate all aspects of nuclear technology have progressed and evolved including standards of nuclear safety. During FY 1968 the nuclear safety R&D efforts continued along the lines and at about the schedule predicted at the beginning of the year. Hence, the safety problems to be studied have been identified and the program seems well-defined. While some program modifications and changes in emphasis are to be expected, the five-year outline shown here is considered to be a reasonable representation of the safety work of highest priority to be studied.

We propose a 50-100,000 photo exploratory exposure of the 14{prime} BC filled with {approx}30% Neon, 70% H{sub 2}, to a broad band {bar {nu}} beam produced by whatever intensity ({approx}> 10{sup 12}) IP/pulse and energy ({approx}> 200 GeV) external proton beam is initially available. The Ne-H{sub 2} mixture permits {approx}10 x higher event rate than pure H{sub 2}; also direct detection of {gamma}, K{sub 2}{sup o}, n; better {mu}{sup {+-}}, e{sup {+-}} identification and the possibility of coherent production reactions from the nucleus as a whole as well as incoherent reactions from both neutrons and protons. The event rate vs. E{sub {bar {nu}}} and q{sup 2} will be measured to {approx}130 GeV permitting (in comparison with HBC experiments) estimate of the A dependence of {sigma}{sub T}, and (given crude flux estimates) tests of scaling and locality in d{sup 2}{sigma}/dE{sub {bar {nu}}}dq{sup 2} and {sigma}{sub T} as well as comparison of {sigma}{sub T} on n and p and of these with corresponding {nu} cross sections. Cross sections, particle momenta, invariant mass and angular correlation spectra will be measured for dominant channels permitting crude tests of {Delta}I = 1, {Delta}I = 1/2, {Delta}S = {Delta}Q, {Delta}S {ne} 2 rules. New particles and …

We propose two exposures in the thirty-inch chamber filled with deuterium, using protons of 100 and 200 GeV/c, with 50,000 pictures at each momentum. We plan to study various properties of p-n interactions including odd-prong multiplicity cross section, single and double dissociation, average {pi}{sup o} multiplicity, inclusive pion production, and correlations.

The initial phase of the Detroit Lakes Energy Systems Study was designed to assemble and analyze sufficient data from which to recommend specific classes of alternative energy supplies. Most of the information on meteorological conditions and biomass materials have been obtained. This is being compiled into a useful form for future evaluation. Research into legal and economic areas are underway. Analysis of this data is being conducted and results will be used in assessing the impact of alternative energy systems. Current technical information on solar thermal, solar photovoltaic, wind and hybrid power systems is being evaluated. Potential systems are being considered in light of their impact on the Detroit Lakes region and the northern latitudes in general. Final evaluation of the data is expected well within schedule.

Energy storage and transfer requirements for many of the present day reactor systems are listed. Two ohmic heating (OH) requirements, those for toroidal Z-pinches and Tokamaks, are described in more detail. Technologies envisioned for the power conditioning circuitry are discussed.

The report presents results of calibration tests on strain meters. The approach was divided into two phases: (1) an overview of meter performance criteria for PCPV applications and techniques for strain measurements in concrete and (2) procurement of commercially available gages and their evaluation to assess the reliability of manufacturer-supplied calibration factors. Calibration test results for gages embedded in 15.2-cm-diam by 54-cm cylindrical concrete specimens indicated that calibration factors should be determined (verified) by embedding samples of the gages in test specimens fabricated using a representative mix and that further research should be conducted on other measurement techniques based on inductance, capacitance, semiconductors, and fluidic principles.

A computer model is described for predicting ductile fracture initiation and propagation. The computer fracture model is calibrated by simple and notched round-bar tension tests and a precracked compact tension test. The model is used to predict fracture initiation and propagation in a Charpy specimen and compare the results with experiments. The calibrated model provides a correlation between Charpy V-notch (CVN) fracture energy and any measure of fracture toughness, such as J/sub Ic/. A second simpler empirical correlation was obtained using the energy to initiate fracture in the Charpy specimen rather than total energy CVN, and compared the results with the empirical correlation of Rolfe and Novak.

The laboratory development of an improved insulation material has led to the development of three types of low density silicone foam (Type IA, IB and II) and a composite foam (Type IA silicone foam/rigid polyurethane foam) that could be used in a flat plate solar collector. Type IA and IB foam are both crosslinked with SiOSi bond, the former being cured at room temperature using a platinum catalyst, whereas the latter being cured at 150/sup 0/C using a rhodium catalyst. Type II foam is a room temperature vulcanized foam, crosslinked with NCOS(CH/sub 2/)/sub 3/Si linkage. The density of Type IA and II foam has been reduced down to 2-3 lbs/ft/sup 3/ range whereas the lowest density of Type IB attained was 6 lbs/ft/sup 3/. Both IA and II low density silicone foam have a thermal insulation property comparable to those of commercially available insulation materials. TGA show that both Type IA and Type II foams gives only 1 to 2% weight loss at 200/sup 0/C. At higher temperature, however, Type IA foam shows less weight loss than Type II foam. A composite foam, where Type IA foam was used to protect a thermally less stable rigid polyurethane foam, was evaluated …

Current laser-driven ICF targets are complex sets of concentric spherical shells made from a variety of materials including the fuel (e.g., deuterium-tritium), glass, beryllium, gold, polymeric materials, organo-metallics, and several additional organic and inorganic materials depending on the particular experiments to be done. While it is not yet known what the reactor targets will be exactly, there is little reason to believe they will be just simple, low quality glass shells containing DT gas or simple spheres of deuterated polyethylene or other fuel. Consequently, many of the current targets, materials, and fabrication techniques are considered to be applicable to the long range problems of ICF reactor target fabrication. Many current material problems and fabrication techniques are discussed and various quality factors are presented in an attempt to bring an awareness of the possible fusion reactor target materials problems to the scientific and technical community.

Recent research was revived interest in electromagnetic railguns. A railgun utilizes the Lorentz force to accelerate an electrically conducting armature, which in turn accelerates a projectile. Our investigation identified the critical parameter that will lead to limits on railgun operation. These limits were incorporated in calculations of the performance of railguns. The calculations indicate that it is possible with present technology to accelerate a projectile to velocities in excess of 20 km/s.

Work conducted on a basic technology development effort with the Westinghouse Sodium Ionization Detector (SID) sensor is reported. Included are results obtained for three task areas: (1) On-line operational response testing - in-situ calibration techniques; (2) Performance-reliability characteristics of aged filaments; and (3) Evaluation of chemical interference effects. The results showed that a calibrator filament coated with a sodium compound, when activated, does supply the necessary sodium atoms to provide a valid operational in-situ test. The life time of new Cr/sub 2/0/sub 3/-protected SID sensor filaments can be extended by operating at a reduced temperature. However, there also is a reduction in the sensitivity. Non-sodium species, such as products from a smoldering fire and organic aerosols, produce an interference response from the sensor comparable to a typical sodium response.

A study of the neutron optical potential on nuclei near mass-140 was begun to extend the energy range and improve the precision of previous neutron total cross section measurements. The extended energy range of this measurement reveals maxima and minima in the total cross section that are evidence of the nuclear Ramsauer effect. A 100-MeV linear accelerator is used to produce a continuum of neutron energies from a Ta-Be conversion target. A 250-meter flight path is used to measure neutron energies by the time-of-flight method. Transmission data for /sup 140/Ce and transmission ratios for /sup 142/Ce, /sup 141/Pr, and /sup 139/La relative to /sup 140/Ce were obtained. The /sup 140/Ce data have a precision of 1 to 3% and the ratios are obtained with a precision of about 0.3%. To analyze these total cross section data a computer code was developed to calculate the total elastic, reaction, and differential elastic scattering cross sections for a neutron interacting with a nucleus. The interaction is represented by a spherically symmetric complex potential that includes spin-orbit coupling. The parameters of this potential were adjusted to approximate the /sup 140/Ce total cross over the energy range from 2.5 to 60 MeV. The energy dependence …

Identification of the elements of typical hazardous waste facilities (HFWs) that are the major contributors to the risk are focussed on as the elements which require additional considerations in the design and construction of low-level nuclear waste management repositories and HWFs. From a recent study of six typical HWFs it was determined that the factors that contribute most to the human and environmental risk fall into four basic categories: geologic and seismological conditions at each HWF; engineered structures at each HWF; environmental conditions at each HWF; and nature of the material being released. In selecting and carrying out the six case studies, three groups of hazardous waste facilities were examined: generator industries which treat or temporarily store their own wastes; generator facilities which dispose of their own hazardous wastes on site; and industries in the waste treatment and disposal business. The case studies have a diversity of geologic setting, nearby settlement patterns, and environments. Two sites are above a regional aquifer, two are near a bay important to regional fishing, one is in rural hills, and one is in a desert, although not isolated from nearby towns and a groundwater/surface-water system. From the results developed in the study, it was …

To better understand and predict tandem-mirror experiments, we are building a comprehensive Mirror Equilibrium Radial Transport and Heating (MERTH) code. In this paper we first describe our method for developing the code. Then we report our plans for the installation of physics packages for electron- and ion-cyclotron heating of the plasma.

The axial ion plugging potential in a tandem mirror is produced by electron cyclotron resonance heating (ECRH) applied at two locations in the end mirror cell. A second harmonic (..omega.. = 2..omega../sub c/) resonance is used near the midplane to generate hot electrons which yield an electron potential barrier between center cell electrons and electrons outboard of the end cell midplane. The latter group of electrons is then heated at the fundamental resonance (..omega.. = ..omega../sub c/) on the outboard side of the magnetic well which drives an ion confining potential. Fokker-Planck and Monte Carlo calculations show that such a configuration is achievable, and the scaling obeys a rather simple set of equations. Another aspect of this configuration is the experimental observation that the fundamental heating drives the overall potential of the device relative to the wall to approx. 1 kV. An analytic model predicts this behavior for very strong ECRH. Results are given a numerical study of electron confinement in a mirror cell owing to fundamental heating as the level of the rf electric field, E/sub rf/, is increased. For the second part of the paper, we show that moderate levels of uniformly distributed rf fields, called cavity fields, …

The ACP Branchbus, a high speed differential bus for data movement in multiprocessing and data acquisition environments, is described. This bus was designed as the central bus in the ACP multiprocessing system. In its full implementation with 16 branches and a bus switch, it will handle data rates of 160 MByte/sec and allow reliable data transmission over inter rack distances. We also summarize applications of the ACP system in experimental data acquisition, triggering and monitoring, with special attention paid to FASTBUS environments.