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Monthly activities for the following studies are given: (1) pile graphite monitoring; (2) graphite burnout and chemical studies; (3) graphite physical properties studies; (4) controlled temperature exposure; (5) thermal conductivity of gases; (6) damage mechanism study; (7) special exposures; and (8) experimental graphite program.

Although there has been considerable progress toward an understanding of the processes of photosyntehsis in recent years, the advances have been followed rather lcosely by symposia, monographs and reviews of the subject matter, particularly during the last three years. In view of the comprehensive coverage it would appear that the present review might very well be limited to a discussion of certain subjects of special interest to the authors and some with which they are especially familiar. These are (1) the extensive discussion by Warburg and his co-workers of their proposal for the existence of a light induced oxygen absorption (and corresponding carbon dioxide evolution) which can amount to three or four times the net oxygen evolution by the same light; and (2) the discovery of the early participation of 7 and 5 carbon sugars in carbon dioxide reduction in photosyntehsis together with some observations on the kinetics of the metabolic transformations. While it is true that a considerable number of significant publications have appears in other aspects of photosynthesis (the Hill reaction and its coupling with carbon dioxide reduction; photochemistry of chlorophyll and related synthetic materials as model reactions in relatively simple defined physical systems; transfer of light energy …

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The following are the maximum recommended design pressures when using 2S-H14-72S clad process tubes: (a) long duration (Operating Pressure) - 500 psi at tube entry. (b) Short duration (Emergency Pressure) - 600 psi at any point along tube length. (c) If several distoration of some tubes (as of fringe tubes in older piles) is expected the operating pressure limit of the tubes in question should be lowered to compensate for the expected distortion.

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In order to determine the effects of atomic explosions on small civil defense shelters for family use, 29 simple structures were built along an arc 1200 ft from the target point and exposed to Buster Bursts B, C, and D. The structures were of four basic types; covered-trench, metal-arch, wood-arch, and basement lean-to. Because of poor cohesive properties of the soil, much of the earth cover on the shelters was removed by the first shot. Since test procedures prevented restoration of structures and replacement of cover after each blast, test results were materially affected. Partly above-grade cover-trench shelters provided less protection against blast than belowgrade cover-trench shelters and were much less desirable as protection against gamma radiation. Metal-arch shelters set in concrete appeared to have good potentialities with minor design modifications. Wood-arch shelters as designed, proved to be unsuitable substitutes for metalarch shelters. No worthwhile information was obtained on basement lean-to shelters. Unusual conditions disclosed design deficiencies in entrance construction, front, and end sections, and effective earth cover. Small shelters are potentially capable of meeting requirements of civil defense. (auth)

This report details the behavior of water used in nuclear reactors. Detailed studies concerning water quality and water chemistry are reported.

This study was undertaken at the request of the Hanford Works to investigate the possibility of detecting 3/8 inch diameter boron-steel control-balls which become lodged within cracks between the graphite blocks of an atomic pile. The cracks concerned occur radially from 4 3/16 inch diameter holes which pass vertically through the pile. The problem is complicated by the following facts: The graphite blocks are conducting and will therefore give rise to spurious signals primarily due to the cracks between blocks. Numerous aluminum tubes containing water and bars of uranium pass horizontally through the pile at distances closer to the hole than the ball at its extreme position. The vertical holes themselves are warped in an arbitrary manner. Calculations were made to determine theoretically whether or not the ball could be detected. Best operating frequency and coil design were also determined. Tests were made utilizing a specially designed search coil and a test section of graphite pile. Measurements of particle voltage vs. position relative to the coil were made and compared with that resulting from the graphite.

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This is an addenda to the final draft for Program X. It contains two changes one for the storage basin for discharged fuel elements and the other for a fuel element storage facility immediately adjacent to the work area. Specifications for each facility are given.

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The purpose of this specification is to set forth in a single document a coherent set of requirements as affected by interrelated design and operating conditions. Basic values, dimensions, and other parameters fundamental to establishment of design specifications for the individual reactor components are given. This document will eventually become a part of the complete ``Design Specifications for ``X`` Reactor`` to be issued later. At that time some of the information given here (such as the moderator dimensions) will appear elsewhere in the document and therefore there is some duplication. Such information was necessary to give the complete scope. An attempt is made to give the basis or background at the end of the document. All references pertinent to the choice are probably not included.

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The phenomenon of alpha particle emission, a general observable property for the nuclides above lead, makes it possible to relate these nuclides energetically. The radioactive decay energy along a radioactive series can be summed so that the total decay energy for each nuclide in the series is known with respect to its position above teh bottom of the series, that is, with respect to its terminal lead (or bismuth) isotope. This can be done for each of the four mass types and, as shown, one can obtain this information for all the collateral members as well as the members in the main line of decay. Thus it is possible, using the relation between mass and energy and the known mass of the alpha particle, to convert this radioactive decay energy ine ach case to a relative mass value based on the mass of one of the four end products, Pb{sup 208}, Pb{sup 207}, Pb{sup 206}, or Bi{sup 209}. If the absolute mass of each of these is known, it is then possible to calculate the absolute mass for all the heavy nuclides above lead for which decay energy data are known or can be estimated. The absolute mass of only …

A revision of tube power limits based on boiling considerations was presented earlier. The limits were given on a basis of tube power versus header pressure. However, for convenience of operation, the limits have been converted from tube power to permissible water temperature rise. The permissible {triangle}t`s water are given in this document.

Attached is a secret draft of 300 Area expansion for the proposed ``X`` Program (600 MWD level for indefinite period) made up of the following: (1) assumptions; (2) present facilities and to what extent inadequate; (3) description of proposed work; (4) advantages to be gained and justification for proposed work; (5) why existing or alternate facilities cannot be used; (6) estimate of cost; and (7) attachments.

The factors responsible for the advances of 100-X compared with the older areas are: Simplification of the process, such as elimination of separate process water clearwells, by having the filtered water reservoirs perform that function. Combination of separate buildings into one building, such as combining filter pump house and process pump house. Use of electric standby. Use of higher capacity pumps and filter basins, and so fewer number of units. Centralization of control and operation. More compact arrangement of plant components. Use of waste heat for space heating, recovered from reactor effluent, backed up by steam plant.