From Abstract: "The Laboratory has made a survey of fallout operations in the various countries of the world. The source of information has largely been the reports submitted to UNSCEAR forwarding data for their consideration. The abstracts are given in order of type of operation as shown in the table of contents."

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.

It was demonstrated that the radioactivity content of the primary system of the N.S. Savannah reactor plant was small and normal during the period of initial criticality and start-up, and during the sea trials and acceptance tests. The principal radioactive constituents (/sup 56/Mn, /sup 41/Ar, /sup 13/N and / sup 18/F) are either intrinsic to the primary system of the pressurized water reactor or are normally found in the coo1ant in concentrations comparable to those observed in this program. The /sup 56/Mn concentrations observed at the various reactor power levels were slightiy higher, relative to those for the other nuclides, than those observed in similar reactor plants. This slightly increased concentration is attributable to the fact that the coolant of this reactor was generally maintained between pH6 and pH7, whereas the primary coolants of the other plants were maintained at somewhat higher pH values. Data for fission product concentrations in the primary coolant indicate that their only significant source is uranium contamination of the reactor core surfaces. The observed concentrations do not represent any significant hazard or potential difficulty in plant operation. The small value of 5.6 x 10/sup -2/ mu g/cm/sup 2/ for the surface density of uranium indicates …

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Activities in a program to improve electromagnetic and eddy current test methods and equipment are summarized. A description of a modified version of the multifrequency eddy current testing system is presented along with discussions of various specific uses. Other information is given concerning through- transmission testing systems using pulsed eddy current fields. Information is also included concerning the use of fields and masked aperture assemblies in test arrangements which permit the inspection of the specimen from one side only. Such an apparatus incorporates the convenience of conventional eddy current test equipment and good features of the through-transmission system. (J.R.D.)

Design criteria are presented for liquid-metal loop facilities for the Advanced Test Reactor. It was concluded that achievement of the design objectives could not be predicted with any high degree of confidence when utilizing the package loop concept based on the design philosophy of the PW-19 loop. (M.C.G.)

Criteria are presented for the Titles I and II design of the Fast Flux Loop Facility which is to be a part of the ATR. This facility, a NaK-cooled in- reactor packaged loop based on the Pratt & Whitney Aircraft PW-19 loop design, is to be used for irradiation of fast reactor assemblies under simulated fast reactor operating conditions. (D.L.C.)

>Progress is reported on reactor materials and components, studies of fuels, general fuel-element development, preparation of UO/sub 2/ single crystals, radioisotope and radiation applications, materials development and evaluation, coated-particie fuel materials, corrosion studies of Fluoride Volatility Process, progress on USAEC/AECL cooperative program, fission-product deposition studies, radiationeffects study of candidate fuel materials for MGCR, gascooled reactor program, process development and evaluation of properties of F- 48 niobium alloy, and gas pressure bonding of beryllium-clad elements. (M.C.G.)

A program was initiated for the design of steam-service Zr base cladding alloy. Specifications were derived for an acceptable alloy for such service based on considerations of neutron economy, cost, H/sub 2/ embrittlement, corrosion resistance, fabricability, and strength. The selection of the field of alloy compositions having promise for meeting these specifications was made. Thirty-one alloys whose compositions were chosen from the alloy field were arcmelted and are being fabricated to sheet. Specimens cut from the sheet will be tested for response to composition. The response parameters will measure corrosion resistance at 300, 400, and 500 deg C, mechanical properties before and after corrosion exposure, and H/sub 2/ take-up during corrosion. The experiment is designed to permit analysis of the results employing computer programing to determine the optimum composition within the selected alloy field. Fundamental studies in support of the alloy design were also initiated. Film stripping techniques were developed to permit partitioning studies of alloying element between the corrosion film and the alloy substrate. Hydrogen overvoltage measurements were made for the intermetallic phases Zr/sub 2/Cu, Zr/sub 2/Ni, for Zr-90% Nb and for crystal bar Zr. The diffusion of O/sub 2/ in bulk nonstoichiometric ZrO/sub 2/ was measured: D = …

Tests were conducted to verify the adequacy of the design, construction, and components of the main heat transfer system of the Hallam Nuclear Power Facility (HNPF) for elevated-temperature and low-power operation. Tests revealed piping interferences, inoperative hangars, and valve difficulties. These discrepancies were rectified and rechecked. Detailed information concerning test results is included. (J.R.D.)

Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The experimental work centers around aspects of detecting neutrons in the presence of 10/sup 7/ r/hr gamma fields. The feasibility of U/ sup 235/ coated solid state detectors for use in these measurements is being studied. A theoretlcal investigation is also in progress on the effects of a multi-region assembly on the fundamental decay constant of injected bursts of neutrons. Other work is reported on the time-dependent neutron thermalization for bare multiplying media, particular attention is directed to the exponential time decay for pulsed bare multiplying homogeneous assemblies. Numerical expressions are given for the fundsmental eigenfunction and eigenvalue to the first and second order, respectively. An explicit analytical expression for the eigenfunction is included. (J.R.D.)

The heat contents of the sesquioxides of Er, Ho, Tm, and Yb (Er/sub 2/O/ sub 3/, Ho/sub 2/O/sub 3/, Tm/sub 2/O/sub 3/, and Yb/sub 2/O/sub 3/) in the cubic crystalline form were measured at 298 to 1,800 deg K. The Er and Ho sesquioxides gave regular heat content-temperature curves. Tm/sub 2/O/sub 3/ sesquioxide had a minor thermal anomaly near 1,680 deg K, with a heat absorption of 310 cal/mole; similarly, Yb/sub 2/O/sub 3/ had a minor anomaly near 1,365 deg K, with a heat absorption of 150 cal/mole. The heat content results are presented in both tabular form (at 100 deg intervals) and in algebraic form. Entropy increments, corresponding to the tabulated heat content results, also are listed. (auth)

A specimen of cast thorium-5 wt% plutonium and one of thorium-10 wt% plutonium were irradiated to total atom burnups of 1.9 and 2.6%, respectively, at maximum fuel temperatures of approximately 450 deg C. Both alloys displayed excellent dimensional stability with volume increases of 0.8 and 1.2% per atom per cent burnup, respectively. Three cold-rolled specimens of zirconium-5 wt% plutonium and one cold-rolled specimen of zirconium-7 wt% plutonium were also irradiated. The zirconium- plutonium alloy specimens all showed extremely poor dimensional stability, with anisotropic elongations ranging from approximately 100 to 500%. The irradiation growth coefficients for these specimens ranged from 90 to 210 microinches per inch per atom per cent burnup. The poor dimensional stability of the zirconium-- plutonium alloy specimens is attributed to a highly preferred grain orientation that presumably developed during cold rolling. (auth)

Tests at the SM-1 reactor are reported for the period October 1, 1961, to May 31, 1962. Loading changes were made in SM-1 Core II during the scheduled semiannual shutdowns in October to November 1961 and April to May 1962. Core physics tests include control rod bank calibrations, bank position at several temperature and xenon poison conditions vs core changes and energy release, shutdown neutron source decay and startup channel testing, and critical rod positions for stuck rod configurations. Shielding measurements of gamma radiation in the rod drive pit were made, and dose rates from spent fuel elements as a function of the depth of the water shield were obtained. A lift mechanism for the BF/sub 3/ detector of one startup channel was installed and preliminary testing completed. Water chemistry and radiochemistry tests included a changeover to high pH for the primary coolant, fission product monitoring for iodine, measurement of dose rates on primary system during shutdown, radiochemical analysis of primary water and crud, and change of metal corrosion samples. Buildup of radioactivity in the demineralizer was monitored by radiation surveys and film badge exposures. (auth)

The JUGGERNAUT is an intermediate-power research reactor designed and constructed as a supporting facility for chemistry and physics research. The design of this reactor is similar to that of the ARGONAUT, and those methods of evaluating the nuclear characteristics of the ARGONAUT which gave good agreement with experimental data were considered applicable to the analysis of the JUGGERNAUT. The analyses for both the JUGGERNAUT and the ARGONAUT were based on a modified two-group theory. The criticality calculations were carried out with the 1BM704 and the two-dimensional PDQ code. Reactivity effects were calculated by hand by means of perturbation techniques, with the real and adjoint fluxes obtained from PDQ calculations. (J.R.D.)

>Thirty papers are included on reactor kinetics with emphasis being placed on reactor safety and design considerations resulting from kinetic work. Information is presented on power excursion programs, reactor transfer function determination and application, reactor instability and thermal-hydraulic problems, and analytical methods in reactor kinetics. The accomplishments in the field and areas needing emphasis are discussed and summarized. Constructive suggestions are made on program direction and information dissemination. Separate abstracts were prepared for each paper. (N.W.R.) lOl2 Data and analytical work on various power excursion tests are summarized and discussed in order to show the present position and understanding of reactor kinetics under accident conditions. The results show that our understanding of plate-type, water-moderated systems of the low power research type seem to be in good shape. On the other hand, information on radiolytic gas formation and transient boiling phenomena is not understood too well. Data are primarily presented on safety experiments with SPERT I and KEWB; however, some information is presented on power excursion tests of Borax I, SPERT III, Triga, Treat, and Godiva. Results show that the problem of predicting the response of reactor systems is on a much firmer basis, even without knowing very much about details. …

A copper pulverizer-mixer was designed for homogenizing Molten-Salt Reactor Project (MSRP) fuel. The copper sampling ladle that contains the solidified fuel is placed in the pulverizer-mixer, which is agitated on a mixer mill. The fuel is fractured out of the ladle, pulverized into a homogeneous powder, and transferred to a storage bottle. The homogenized fuel sample is then available for analysis. (auth)

The smear study shows that at least 80% of the floorsmear surveys which were made in a clear area of the Chemical Engineering Building during the course of this study indicated radioactivity equal to or less than 10 d/m/ ft/sup 2/ alpha and equal to or less than 200 d/m/ft/sup 2/ beta-gamma. The smear survey technique is excellent for use in a highhazard area, such as a Pu facility. It is capable of detecting as little as 10 d/m/ft/sup 2/ of alpha contamination with a high degree of confidence. The smear survey is also useful in determining whether the radioactivity on an item is low enough so that it may be removed from an active area. (auth)

To test the fire and explosion resistance of new plutonium metallurgy gloveboxes and to obtain information pertinent to fire control, fire and explosion tests were conducted in one of the gloveboxes. It was found that over l0% oxygen is required for non-metal, and that over 5% oxygen is required for freely burning metal fires. However, metal chips will burn with as little as 1% oxygen if additional heat is furnished. Standard dry chemical, Met-L-X, and carbon dioxide extinguishers were excellent for nonmetal fires. An eutectic salt mixture was excellent for metal fires. (auth)

Rippling phenomena due to heating in fuel plates of SM and PM type reactors are investigated analytically using small deflection theory of plates. Temperature variations across the width of the plate are accounted for. Detailed calculations are conducted for simply supported plates. It is found that within the limitations imposed by small deflection theory that the amplitude of the plate ripples induced by the heating is directly proportional to the initial amplitude. (auth)

Nuclear and thermal analyses were performed to determine the characteristics of the Type 5 core in the SM-1 and SM-1A reactor plants as a function of geometry and composition. The following nuclear properties were investigated: core energy release, maximum midlife reactivity, average fuel burnup fraction, B-10 reactivity coefficient, and power distribution. Thermal parameter surveys determined the effects of channel thickness and power distribution upon the DNBR, nominal and hot channel thermal performance, and fuel plate thermal stress. From the nuclear and thermal analyses, a Type 5 core reference design was selected with fuel plates of 70-mil plate thick ness, 7-mil clad thickness, and 38 wt % UO/sub 2/ in the matrix, having initial core loading o4 108 Kg U/syup 235 and 260 gm B/sup 10/. (auth)