The detailed stress analysis of the SM-1 steam generator tube sheet showed it to be safe from strain cycling damage. However, the pressure stresses were greater than the yield strength during the hydrostatic test. The differential between pressure stresses and yield strength indicates that some initial deformation may have taken place in the tube sheet. (auth)

None

An eddy current test system is described in which the test information is detected as a series of fields reflected from the metal surface and interior. Pulsed electromagnetic fields are caused to impinge upon the test specimen. These fields are restricted to a small cross sectional area over a path in space long enough to be useful for test purposes by devices called mask-apenture assemblies. This approach provides a number of advantages over conventional eddy current methods of comparable capabilities, including superior surface resolution, a reduction in circuit complexity, and an improvement in stability and reliability. Various applications and test results are discussed. (auth)

As a result of the evaporation explosion in the Radiochemical Processing Pilot Plant on Nov. 20, 1959, two cells were contaminated with plutonium to a transferable level of 10/sup 8/ d/m/100 sq cm. The area involved measures 40 by 20 by 27 ft high with a total surface area, including equipment, of 10,000 sq ft. The cells were decontaminated by a factor of 1000 in five months by removing loose equipment, debris, and shielding blocks and flushing with 430,600 liters of various decontaminating reagents. The remaining contamination (10/sup 4/ - 10/ sup 5/ d/-m/100 sq cm) was fixed to the surface with three coats of paint. The general beta-gamma radiation background was decreased from 2000 to 30 mr/hr and the long-lived alpha contamination in the air was reduced from 2 x 10/sup -10/ to 8 x 10/sup -13/ mu c/cc. Approximately 141 g of plutonium was flushed from the cell surfaces. The total direct effort expended was 3000 man-hr including 250 entries into the cell, 175 of which were made in plastic air suits. There were no overexposares from beta-gamma radiation and no detectable increase in the body burden of plutonium of any individual involved. (auth)

Four runs were conducted in the Zirflex-Sulfex headend hot cell equipment. Prototype PWR blanket rods, Zircaloy2 clad UO/sub 2/, irradiated from 159 to 356 Mwd/t and decayed 2 years, were declad in boiling 6 M NH/sub 4/F-l M NH/sub 4/NO/sub 3/, terminating with a F/Zr mol ratio of 7 in the spent decladding solution. Average decladding time was 1.5 hr, leaving end cap residues of about 5 g per pin. At the end of the decladding, maximum loss of uranium and plutonium to the decladding solution was 0.04 and 0.37%, respectively. The core pellets were largely shattered with less than 0.5 wt% smaller than 10 mesh. Core dissolution was complete in 5 M HNO/sub 3/ in about 40 minutes, yielding a solvent extraction feed containing 4 M HNO/sub 3/ and 100 g U/l. Solid residue from the decladding and core dissolution was less than 0.001% of the initial weight and consisted of traces of Ca, Fe, Cr, and Sn; uranium and plutonium were not detected. (auth)

Separate abstracts were prepared for thirty-one of the thirty-three sections. Of the sections not abstracted, the one entitled Fission Product Transport'' contained no information, the other, Transport of Noble Gases in Graphite'' is available in a more complete form as ORNLTM-I35 (NSA 16: 9209) (J.R.D.)

The id Thorex process, in which nitric acid is the salting'' agent in the solvent extraction of Th and U from an acid eficient feed with TBP in Amsco, was demonstrated in laboratory equipment for the recovery of synthetic Co solidated Edison Thorium Reactor fuel containing trace fission products. The acid was removed from solution of the declad fuel pellets to produce an acid deficient feed by steam stripping, and the adjusted feed was treated with bisulfite to decrease the extractability of fission products. The Th and U were extracted with 30% TBP in Amsco, and pregnant organic was scrubbed with dilute nitric acid to improve decontamination. Additional acid was added to the extraction section to increase the distribution oefficient of the Th, The Th and U could then be stripped ther simultaneously or separately. No difficulties were ound with either excessive reflux of acid or <0.3%. The co centrated aqueous waste was about 0.2 liter per kilog am of Th processed, about 1/10 of that from the aluminum n trate-salted process. Engineering studies showed that the stage height in the extraction column with the acid Thorex process was 2.1 ft compared with 4 ft with the aluminum-salted Thorex process. …

A review of radiation effects on graphite is presented. Included are discussions of the general relations of these effects with original structural properties, and details of radioinduced changes. Other discussions are devoted to stored energy, annealing, and future problems in the use of nuclear graphite. Data and illustrations concerning structure and radioinduced changes are included. (J.R.D.)

A probe for measurement of the space between fuel plates in high-burnup MTR-type fuel elements by eddycurrent techniques is described/su The sensing section is supported near the end of a flattened stainless steel tube into which a rectangular hole was cut to receive it/su The sensing section consists essentially of two slightly bowed springs, the midsections of which protrude slightly above the upper and lower surfaces of the flattened tube. Each spring- carries a section of a ball bearing as the contact point/su It is these two slightly bowed springs that serve as expanding calipers sensing variations in the spacing between adjacent plates. Essentially the rest of the probe is a long handle to permit probing and a conduit for the electrical leads. A two-wire shielded cable is firmly attached to the unflattened end of the probe and then attached to a modified Wheatstone bridge, from which the output is fed into a chart recorder. (M.C.G.)

Continuous dissolution of Zircaloy-2 in a titanium dissolver appears practical using as a dissolvent refluxing 3 M HNO/sub 2/-l.2 M HF--0.4 M HBF/sub 4/-0.6 M Cr(III)-0.4 M Cr(VI)--0.46 M Zr. Dissolution and corrosion rates were 10 mg/cm/sub 2/-min and 0.0 mil/mo in short term tests, respectively. A stable product solution containing 0.36 M Zr was obtained after addition of aluminum nitrate to complex fluoride ion. Another reagent investigated for use in continuous dissolution was 16 M HNO/sub 3/-2.6 M F-0.025 M HBF/sub 4/-1.4 M Zr with short term titanium corrosion rates of 0.0 mil/mo. However, Zircaloy-2 dissolution rates were only 3 mg/cm/sup 2/-min in the latter reagent. (auth)

A review is given of the present state of knowledge concerning the condensed phases of He{sup 3}. Attention is confined to the pure substance, and emphasis is placed upon the theoretical understanding of the material.

A number of organisms have been examined for their ability to produce electron-spin-resonance signals at low temperatures in response to illumination. The efficiency of the response is of the order of not less than 5%, and the wavelength for maximum response is generally slightly on the longer side of the wavelength of maximum absorption, with a minimum appearing at the wavelength of maximum absorption.

The solution photochemistry of chlorophyll and chlorophyll analogs is described. Many cases of electron transfer to or from the porphyrin macrocycle have been found, but in no case has any very large degree of energy storage been achieved. Because of the very rapid back-reaction for products with a {Delta}F of approximately -30 kcal, some solid state models in which such an energy storage might be achieved are described and their possible relation to the natural photosynthetic apparatus is given. We can see that while the solid state model (phthalocyanine) allows an approach from a somewhat different point of view, the net result is the same as what was sought, but so far not found, when we looked at the solution chemistry of chlorophyll (and chlorophyll model substances), namely, the transfer of an electron, or hydrogen atom, from the excited porphyrin to an electron acceptor at a high reduction level which can be used to reduce the ultimate carbon dioxide reducers, followed by the donation of an electron ultimately from water to the remaining radical ion, or lattice, which produces the net results of the transfer of the hydrogen from water to carbon dioxide.

It is almost sixty years since Emil Fischer was describing on a platform such as this one some of the work which led to the basic knowledge of the structure of glucose and its relatives. Today we will be concerned with a description of the experiments which have led to a knowledge of the principal reactions by which those carbohydrate structures are created by photosynthetic organisms from carbon dioxide and water, using the energy of light. The speculations on the way in which carbohydrate was built from carbon dioxide began not long after the recognition of the basic reaction and were carried forward first by Justus von Liebig and then by Adolf von Baeyer and, finally, by Richard Wilstatter and Arthur Stoll into this century. Actually, the route by which animal organisms performed the reverse reaction, that is, the combustion of carbohydrate to carbon dioxide and water with the utilization of the energy resulting from this combination, turned out to be the first one to be successfully mapped, primarily by Otto Meyerhoi and Hans Krebs. Our own interest in the basic process of solar energy conversion by green plants began some time in the years between 1935 and 1937, during …

The General Electric Company operates eight large filter plants for the Atomic Energy Commission at the Hanford works in the state of Washington. Because of the importance of water to the process, research and development on water treatment has been an important part of the overall Hanford research and development program. The research and development on water treatment has resulted in important capital and operating savings and in the production of better quality water. It is the purpose of this paper to present some of the information developed by the programs. 3 tabs.

Materials and specifications for the construction of the N-Reactor buildings are presented.

None

The attached pages show the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. For further description of column headings and the current discharge goal exposure plan the reader is referred elsewhere.

The rail shipment of large quantities of radiocesium involves a potential accidental release of this material in a readily available form to the biosphere. The magnitude of the associated potential damage to man and his environment is evaluated in this report. The evaluation of the consequences of an accidental release of Cs-137 from the Shielded Transfer Tank, Model II (STT) assumes loss of Cs-137 to the atmosphere or to surface-water. Release to the atmosphere could result from a collision followed by fire or explosion. In the event of a fire, a small fraction of the Cs-137 vould be volatilized. An explosion would disperse the Cs-137 still adsorbed to Decalso as particulates. In either case, the material is assumed to be dispersed by atmospheric mechanisms which can be described by modified Sutton equations. The accident involving a fire or explosion assumes that 1 percent or 10 percent, respectively, of 90,000 curies of Cs-137 is dispersed in a metropolitan area. Contamination of the surrounding suburban area is also involved. Damage estimates amount to about 60 million dollars and 400 million dollars, corresponding to a 1 percent and a 10 percent release respectively. Another possible type of accident involves the release of the …

Metallographic examination has been completed on samples from the Nichrome V wire mesh furnace belt in the 232-Z building incinerator. During service the furnace belt had broken in several places where the wire was welded together. A grain boundary phase was found in weld metal during metallographic examination of the as received material. It is probable to conclude that the failure during service was caused by accelerated corrosion of the weld and that the accelerated corrosion in that area was related to the structure of the weld metal. It would be informative to examine welds from the furnace belts that have not failed to further study the cause for the failure.

The objective of this production test is to authorize the installation of at least 40 additional large size Zircaloy process tubes in graphite channels that have been enlarged to 2.275 inches at C Reactor and to charge these tubes with large diameter (CVIN) fuel elements to obtain preliminary conversion ratio data and further qualitative data regarding the irradiation behavior of large diameter fuel element designs.

A survey of the PITA-18 nonpoisonous spline program was conducted in conjunction with a study to determine the best method of eliminating the variability of axial flux on the fuel performance parameter, q. The results of this survey and the conclusions reached in the rupture coefficient study were found to be inter-dependent such that both are presented in this report. The data from the PITA-18 nonpoisonous spline program, as received, is the output of the NOLA-2 computer program. One quantity of interest is the rupture potential relative to a cosine, commonly referred to as the relative rupture potential. As programmed, the relative rupture potential, which was derived by applying the rupture model to individual fuel elements, might be expected to vary linearly with the rupture rate. The use of the relative rupture potential was studied over the period of July 1962 through December 1963. The results of this study are presented.

The C reactor is presently, operating with all process water discharging through one downcomer. Pressure measurements at the downcomer lid show the top tray is nearly flooded, thus prohibiting further flow increases until the downcomer is modified or both downcomers are used simultaneously. Operation with two downcomers can result in two sources of error in the power calculation: (1) Errors in measured outlet temperature can occur, apparently due to the increased venting capacity. The magnitude of the effect is probably unpredictable and could not be compensated for in the power calculation. Since the temperature error occurs only downstream of the downcomer vents, the logical solution is to move the outlet temperature devices to the risers. The method of administering bulk temperature limits will have to be changed to account for the thermal shield flow entering downstream of the outlet thermohms. (2) Simultaneous flow and temperature unbalances can result in power calculation errors since there is no way of knowing the actual flow through each downcomer. It is assumed that the power calculation would have to be made from the total flow and the average of the two outlet temperatures. The primary purpose of this study was to determine whether the …

This document considers the costs of rhenium formation as produced by irradiating tungsten. Two isotopic compositions of tungsten are considered for the study. The cost for reactor-formed rhenium appears to be prohibitively high -- over $20 per gram. This cost would exist for tungsten containing 90% 186, 9, 184, and 1% tungsten 182 and 183. The cost of alloy made fro natural isotopic compositions of tungsten would be higher by a factor of 3, and would take prohibitively long to produce significant quantities of rhenium. Thus, detailed numbers are not shown or considered for the natural isotopic composition of tungsten.