Research was continued in the areas of intrinsic radioactive tracers for industrial process control and the influence of structural factors in radiation- induced graft polymerization. The use of in-process isotope neutron soarces to produce short-lived radiotraces is discussed. A 10c Po--Be neutron source was obtained for exploratory experiments. The design and construction of a neutronsource storage shield and an activatioa-cell holder are underway. The effect of structural factors oii the eIficiency of free-radical site formation in acrylate and methacrylate polymers was emphasized. Site measurements versus dose were made for poly-n-hexylmethacrylate. Two additional methods for measuring free-radical conceiitrations, a chemical method employing diphenylpicrylhydrazyl and hydroquinone and a method based on molecular-weight decreases, were developed. The grafting studies were continued. (M.C.G.)

Methods by which the radial deposition mechanism was determined in experiments with simulated waste solutions are reviewed. Based on this mechanism, an expression for the rate of solid deposition with internal heat generation was developed by a combined heat and material balance. A sample calculation for Purex waste showed that a moderate heat generation rate of 5000 Btu/hr/ft/sup 3/ would decrease the time to fill a 12-in.-dia calcination vessel from 78 to 55 hr. For the calcination stage of the process in which the deposited solids are heated in the absence of a liquid phase, a solution was developed for the equation of heat transfer with the temperature profile from the solid deposition stage as an initial condition. For the example Purex waste with a heat generation rate of 5000 Btu/hr ft/sup 3/, less than 15 min would be required for calcination, compared to about 8 hr in experiments with simulated wastes. (auth)

Several safety parameters are calculated for a large, fast, Na-cooled, oxide-fueled reactor. The Doppler coefficient is studied as regards its effect on the reactivity during a power excursion, and its dependence on the neutron spectrum, on the concentrations of U/sup 238/, Pu /sup 239/ , a nd Pu/sup 240/, on spatial temperature and power distributions, and on temperature. Other parameters studied include the Na temperature coefficient of reactivity, and the reactivity insertion caused by total Na loss; reactivity coefficients caused by thermal expansion of fuel and steel cladding; the excess operating reactivity; and the reactivity caused by a fuel slump. The effects of a Be reflector on neutron lifetimes are determined. The safety aspects are balanced against economic considerations. (T.F.H.)

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Recently a T = 1 resonance in the {Lambda}-{pi} system called Y{sub 1} has been observed with a mass of 1385 MeV. Two types of resonances have been predicted that might relate this observation to other elementary-particle interactions: (1) P 3/2 resonances in the {Lambda}-{pi} and {Sigma}-{pi} systems predicted by global symmetry, corresponding to the (3,2/ 3/2) resonance of the {pi}-N system, (2) a spin-1/2 Y-{pi} resonance resulting from a bound state in the {bar K}-N system. The position and the width of the observed Y{sub 1} resonance agree with both theories, but since the spin and parity have not yet been determined, they cannot distinguish between the two theoretical interpretations.

This report discusses the critical mass control specifications for Hoods 7-C and 9-B have become obsolete due to needed storage within the confines of Hood 9-C, and equipment modifications. Nuclear safety in Hood 7-C and 9-B depends almost entirely on controlling the mass and geometry of the plutonium compounds not confined by the processing equipment. Generally, the processing vessels and associated piping are designed and arranged in the hood to be critically safe at full operating capacity. This safety is not assured, however, if plutonium masses outside of the equipment exceed certain proportions of geometry and mass. For those cases where always safe geometry confinement cannot be assured, administrative controls are established.

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 purpose of this document is to define the process requirements of the modifications and additions to the last ditch cooling systems and to outline the functional descriptions of the proposed equipment.

There is a certain tolerance of error implicit in any calculation based upon measured physical data. Occasionally, the error is explicitly recognized by attaching a plus or minus variation to the calculated quantity. More often, however, the error is simply neglected. The present analysis was performed to quantify the error implicit in a typical TAI (Trip-After-Instability) limit calculation. This error results from the precision of measurement of each of the parameters used in the calculation of the TAI limit. Though not specifically considered, the results of this work could be used to establish the required minimum level of accuracy of the tube outlet temperature monitoring equipment. Further, some of the generalized equations could probably be programmed into the ROL (Reactor Operating Limits) to indicate how far each Panellit gauge could be ``rolled`` without exceeding a fixed minimum TAI limit. Since the examination of these other possibilities is beyond the scope of this report, they are left as suggestions for future work only.

The design of a transistorized d-c coupled amplifier having very good gain stability and low drift of the output d-c level is described. Low-frequency input signals from a low-impedance source are amplified by the system to an approximate peak-to-peak amplitude of 4 v. (J.R.D.)

A proposed design and development program for a potentially economical, high-performance, sodium-heated steam generator is described. The concept employs modular units grouped together to provide for any combined power level desired. Fabrication expense is shown to be reduced by the reduction in heat transfer area requirements. This reduc, tion is achieved through improved heat transfer coefficients which exist under supercritical steam conditions. The testing of two small units ( approximates 18 Mw total) is shown to be sufficient to verify performance for any size unit because of the modular concept employed. (auth)

This document discusses a proposal that certain presently installed reactor process water outlet temperature data logging equipment in subject reactors to be replaced with new functionally simplified equipment of a more adequate design. The primary purpose of the proposed installation is to replace existing equipment which is obsolete and in three reactors is worn out to the point where the equipment is out of service frequently for periods of time up to 8 hours or more. The new equipment will provide reliable process tube temperature information for use in the functions of reactor control and product accountability. Based upon anticipated incremental production gains resulting from use of the new equipment, the amortization period for the project is calculated at 2.7 years.

Members of the Biology Division presented 168 lectures during the period February to August 1961, compared with 116 for each of the two preceding reporting periods. Of these, 96 were before professional societies at home and abroad, and 28 were presented as part of the Traveling Lecture Program.

Urania rods 6-in. long and 0.475-in. in diameter were extruded and sintered to densities exceeding 94% of the theoratical urania density. The rods dropped freely through a straight metal tube 8-in. long with an internal diameter 0.004-in. greater than the diameter of the rods. All properties of the extruded and sintered rods relevant to their use as a nuclear fuel material were at least equal to the corresponding properties of pressed and sintered urania pellets. Extruded and sintered urania rods can be produced with standard ceramic-industry machinery. From preliminary estimates it appears that extrusions may be produced more cheaply than pellets. (auth)

A survey was made of unclassified literature dealing with the control of activity build-up in pressurized water reactors by high-pH coolants. Survey results indicate that a high-pH coolant is desirable for control of induced radioactivity build-up in pressurized water reactors containing significant amounts of stainless steel and that no significant hazards are introduced by adoption of a high-pH coolant. Lithium hydroxide was found to be the most acceptable agent for coolant pH control. Strong-base-form mixed-bed resin is effective in maintaining both coolant pH and coolant purity. (auth)

Pilot unit Zirflex dissolutions were carried out on near prototypical tube-in-tube type elements clad in oxidized Zircaloy. The runs were made with the elements horizontal and at simulated large scale operating conditions. No significant difference was noted between the actual decladding achieved in these experiments and that which was predicted from prior studies on similarly oxidized elements with somewhat different geometries. No gas blanketing nor diffusion effects were observed. Initially, preferential attack was noted on areas where oxide film had been scratched or handled. However, near the end of a run a random distribution of undissolved cladding existed; 90% of the cladding was removed in 6.5 hours. (auth)

Activities are reported on development work on a mass flow system capable of measuring externally the properties of homogeneous flow, slurries, highly corrosive fluids, and multi-phase fluids. In the proposed system, the fluid passes through an S-shaped tube wherein measurements of the angular momentum and density yield mass flow directly. (B.O.G.)

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