Quarterly report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between October 1 to December 31, 1960 and was conducted by the United States and the European Atomic Energy Community (EURATOM).

Purpose of this test was to determine the adequacy of the export system for supplying flow to a dual reactor area under simulated emergency conditions.

This document defines the user`s process and functional requirements which shall be used as the basis for the preparation of the design for Project CGI-905, Interim Modifications for Improved Coolant Backup 100-B, C, D, DR, F, and H Reactors. The objective in making these modifications is to provide improved reliability and adequacy in the last ditch reactor cooling systems for current and short-range forecast conditions. Performance requirements for the last ditch cooling system are based on the reactor cooling system criteria set forth in Document HW-66929. These performance criteria require that the last ditch cooling system be independent of both the primary and secondary cooling system including piping to the reactor manifold, and that it must be capable of providing shutdown flow indefinitely, assuming instantaneous loss of power to the primary system and concurrent failure of the secondary system to provide its rated flow.

The process criteria proposed use of the existing organic wash column, 10, as a stripping column for the neptunium accumulation and isolation cycles. It is now proposed to employ a new processing concept which will permit the use of the scrub section of the neptunium extraction column, 1S, for neptunium stripping thereby obviating the use of the 10 Column. This proposed new scheme will provide increased neptunium stripping efficiency and greater processing flexibility for the 1S Column. The revision will require four new jumpers, but will permit the deletion of eight jumpers required for the original proposal. This document discusses the technical bases and incentives for the proposed change and presents revised flow diagrams and jumper routings.

Twenty columns of OIIIN-B fuel elements, ten with bumper rails of the present design and ten with elliptical bumper rails, will be charged into D Reactor in pairs, i.e., a column of fuel elements with one rail design will be charged adjacent to a column containing the other bumper rail design. Performance of the elliptical bumper rail will be based on relative visual appearance and measured weight loss. The twenty columns of weight and measured fuel elements required for this test may also be used to fulfill the fuel requirements for required for this test may also be used to fulfill the fuel requirements for PT-IP-442-A.

The objective of this production test is to compare the irradiation behavior of N Reactor inner fuel tubes (NIE1 elements) having negligible warp after beta heat treatment to the behavior of NIE1 elements with extensive warp after beta heat treatment which were straightened and beta heat treated a second time. The information from this test will be used in the development of a program to evaluate the irradiation behavior of NIE1 elements in various conditions of pre-irradiation warp and straightening.

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Neutron activation analysis provides the extremely high sensitivity necessary for the measurement of many trace elements. Activation techniques are presently being used to measure the concentrations of various undesirable parent isotopes in reactor process tubing, slug jackets and their corrosion film, and in process vater and vater treatment chemicals. The interpretation of results from activation analysis are sometimes complicated by the fact that a given radioisotope may be produced by fission neutrons (threshold reactions) from other elements as well as by the more common thermal neutron (n,{gamma}) reactions. Shielding the sample with cadmium prior to irradiation or irradiating in the graphite reflector will minimize the contributions from thermal or fission neutrons, respectively. The purpose of this study has been to measure the ratios and magnitudes of the thermal and fission fluxes in process tubing and to compare these with values at locations where neutron activations can be performed. Also, it was of interest to measure the ratios and magnitudes of the thermal and fission fluxes from a point in the lattice to a point well into the graphite reflector, and to determine if the fission neutron spectrum as measured by two threshold reactions, changes appreciably over this region. These data …

Results of the final dynamic experiments with the ironremoval process model using Fe/sup 59/ indicated that the intrinsic-radiotracer method is rapid, accurate, and suitable for continuous readout. Results from both static and dynamic experiments on the use of Mn/sup 54/ to aid in removing manganese from process water indicated that intrinsic radiotracers can be used to help remove low-concentration critical impurities. One phase of the hazards evaluation was concerned with the ingestion of radiotracer residues which might arise from corrosion of radiotracer-containing steel products. It was concluded that no hazard exists from this source. Another part of the hazards study was concerned with the technical hazards to sensitive industries which might use steel containing radiotracer residues. This area is the most sensitive one encountered in the study. The study of the mechanism of formation of free radicals in polymeric materials was continued. Emphasis was placed on examination of the effect of structural factors on the efficiency of free-radical site formation, especially in acrylate polymers. An initial investigation of the effect of polymer tacticity was completed using polypropylene. The influence of molecular mobility on site formation in polymethylacrylate was established. Measurements of the volatile products from irradiation of the polymers was …

"The canonical (hamiltonlan) formulation of a relativistic dynamical theory is outlined, and the existence and explicit construction of general hamiltonian theories of relativiatic interacting particles are discussed. These hamiltonian theories are shown to contain certain elements of arbitrariness which are eliminated in manifestly coveriant formulations."

From Abstract: "Comparisons with other intensity measurements in individual spectra indicate that the National Bureau of Standards spectral-line intensities may have average errors of 20 percent, but first of all they provide uniform quantitative values for the seventy chemical elements commonly determined by spectrochemists. These data are presented by element in part I, and all 39,000 observed lines are given in order of wavelength in part II."

The development of swaging and vibratory compaction process for fabrication of clad UO2 fuel rods is described. The cost is less than 50% of that for an equivalent core fabricated from pellets. The irradiation testing of vibratory filled and swaged UO2 rods is reported for burn-ups from 2,000 to 12,000 Mwd/t UO2; the results indicate that the rods are capable of excellent performance power reactors.

Abstract: A cyclic stress analysis of the SM-1 primary system was carried out. Problems encountered in the fabrication of PM-2A Core II and SM-lA Core II are described, and the results of an examination of damaged SM-lA Core I stationary fuel elements reported. A preliminary study of the radiation damage to SM-1 reactor vessel was made and the possibility of annealing the vessel discussed. Performance analyses are presented for five cores: SM-1 Core, SM-1 Core 1 rearranged and spiked, SM-1 Core II with special components, PM-2A Core 1, and SM- 1A Core 1. Preliminary critical experiments were made with SM-2 elements in a SM- 1 core configuration and nuclear and thermal analyses of the use of SM-2 elements in SM-1, SM-1A, and PM-2A completed. A throttling steam calorimeter was selected for measuring moisture carry-over on the PM-2A steam generator. Test procedures for evaluating the shielding of the SM-1, SM-lA, and PM-2A plants are summarized. Radiochemical and chemical analyses of SM-1 coolant and crud are summarized, and methods of activity control discussed. Preliminary results of studies of the properties of reactor pressure vessels under irradiation and no irradiation conditions are summarized briefly.

(p,xp) reactions are those nuclear reactions induced by high energy protons in which both the mans and the charge of the target nucleus are reduced by x-1 units. The most common type of these reactions to be expected in the 100 to 400 Mev region involves the exclusive emission of protons as a results of the interactions. The specific (p,xp) reactions investigated in this study were those where 2 is less than or equal to x where x is less than or equal to 5.

The F-48 columbium base alloy maintains useful mechanical properties for structural application up to 2600 degree F. Short-time tensile and creep rupture strengths have been determined for four F-48 plates, each from a different heat and with a different work history. Flow testing in a high-temperature, high-pressure air stream has been conducted to study oxidation behavior of the bare meatal. Auto-ignition is found to occur at a stream temperature of 2600 degree F. The phenomenon appears to be temperature dependent only. Development of an oxidation protection coating, utilizing environmental flow test apparatus, is proceeding.

The method of dispersion relations has in recent years found a wide application for the study of elementary particle reactions. Most of the work, however, deals with reactions of the type [formula], while the theory of those with more than two particles in the final state is still in a very preliminary stage. One reason for this is that even with only three particles in the final state the theory is already much more complicated. Nevertheless, a further development of the theory seemed to us very desirable. The theory at present is being developed on various levels simultaneously. Generally speaking, the aim of this paper is to put the theory in a form as closely as possible analogous to Mandelstam's formulation of the theory of reactions of type [formula]. In the later sections we specialize on reactions [formula], but as much as possible the formulation is in more general terms.

"A method and equipment are described for determining the surface parameters of contact required for heat transfer calculations. In this method, the output of a surface analyzer for one surface is recorded on one channel of magnetic tape and the output for the other surface of the contact pair on a second channel. The tape is played back to an analog computer which then integrates the analog voltage to compute the void volume thickness, the number of contact points, and the ratio of metallic contact area to the total area."

"The quantum theory problem of constructing explicitly a local Lorentz invariant model field theory which has an asymptotic particle interpretation and gives rise to an S matrix different from unity is discussed. It is proved that if a local covariant field H(x) has a complete current, the S matrix associated with this field is identically equal to unity. Results show that in order to get an interaction, the current is not allowed to have a terminating expansion in terms of a free field. The absence of a finite connection between a free field and an interacting field tended to confirm the belief that in local quantum field theories with particle interpretation the requirement of the existence of scattering forces in the physical states are such that it is not pos sible to identify them with a linear space spanned by ""free'' particle states."

Test work was completed on development of a stripping method for the amine extraction (Amex) process which produces a concentrated uranyl nitrate solution for shipment to the refinery. This procedure offers potential cost savings by simplifying the overall mill-refinery flowsheet. The process involves treatment of the amine extract with calcium nitrate solution to convert the uranium in the solvent to a nitrate complex, stripping the uranium with water or dilute nitric acid, and recovery of nitrate from the solvent for recycle by contact with a lime slurry.

Further calculations have been made to determine the desired radial fuel distribution in the HFIR and in the forthcoming HFIR critical experiment. In the process the design of the core was changed to include a 1-cm-thick annular space of water between the two nearly equally thick fuel annuli, a metal-to-water ratio in the fuel annuli of 1.0 (0.050 in. thick plates and coolant channels ) was specified, and the active length of the core was increased from 18 to 20 in. Results of the calculations indicated that the largest ratio of maximum meat thickness to minimum meat thickness occurred in the inner fuel annulus and was equal to 3.6, while the maximum fuel concentration occurred in the outer fuel annulus and was equivalent to about 0.7 g of U-235/cm^3 of meat. The total U-235 loading for this core was 8.01 kg, which results in a core lifetime of about 14 days.

A total of 104 thermal cycles between 250°F and 1350°F were imposed on a 3 1/2-in. and a 4-in. freeze flange to determine their susceptibility to thermal fatigue. The flange clamping arrangement was modified and various gaskets were used during the cycling in an effort to reduce the gas leakage problem.

Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined included (1) core screen samples, (2) core specimen array No. 1, (3) blanket specimen array No. 2, (4) core solution line specimen arrays No. 103 and 103A, (5) blanket solution line specimen array No. 203. Complete information is still not available on all the specimens removed from the reactor, however, those data which have been accumulated are presented. These include corrosion rates, computed from specimen weight-changes, and results of chemical analyses of scales removed from the specimens or specimen holders. Also included in the report is a summary of the HRT operating schedule during exposure of the specimen and of the status of examinations for those specimens removed from the reactor prior to run 20.