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The examination of 27 fuel pins irradiated in the Plum Brook reactor facility is described. Curtailment of NASA sponsored nuclear programs prevented a complete examination of all pins. Nevertheless, results include fuel pin integrity, clad ductility, clad strain, fission gas release, fuel burnup, fuel swelling, neutron fluence, metallography, and instrumentation reliability. Twenty-two fuel pins were tested for fission gas leaks; 13 pins leaked with two having visible cracks. Fuel swelling appeared to be primarily burnup dependent for burnup values up to 2 at. %. Maximum burnup reached in these tests was 2.34 at. %. In general, the fuel pellets did not crack or crumble and fuel metallography remained unchanged. The amount of fission gas released from the fuel was low, generally less than 0.5%. The maximum amount released was 2%. No incompatibilities between fuel, liner, and clad were evident.

This part of the completion report pertaining to the NERVA graphite fuel element program covers data collected during the extrusion studies. The physical properties of the fuel element reached the following values: coefficient of thermal expansion (CTE) - 7.0 x 10-6/o C (25 - l,OOOo C); modulus of elasticity - 1.5 x lo6 psi; flexural strength - - 8,000 psi; ultimate strain to failure - 5,500 pidin; good thermal stress resistance. Matrices were produced which could be vapor coated with crack-free films of zirconium carbide. The CTE of the matrix was almost equal to the CTE of the zirconium carbide coating.

Several basic errors appeared in an article recently published by Prunier et al. entitled, 'Some Properties of Xenon Liquid-Filled Nuclear Detectors'. The article describes an experiment to measure electronic phenomena in liquid xenon using single wire cylindrical chambers. The author here describes some errors made in their interpretation of their experimental observations.

Small precision mechanisms must have burr-free, sharp-edged parts to operate well. Controlling the size of burrs can lower burr removal costs and improve edge repeatability. Study results indicated that with conventional tooling approaches, Extrude Hone deburring with x-base media removes more material from the hole than desired and is less repeatable than required on precision miniature parts. With this media, the process is most applicable to precision miniature parts with burrs less than 25.4 ..mu..m thick, allowable hole size changes equal to burr thickness, and allowable hole size repeatability of +-0.2 times the actual average hole size change.

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The code ANISN-L solves the one-dimensional, multigroup, time-independent Boltzmann transport equation by the method of discrete ordinates. In problems involving a fissionable system, it can calculate the system multiplication or alpha. In such cases, it is also capable of determining isotopic concentrations, radii, zone widths, or buckling in order to achieve a given multiplication or alpha. The code may also calculate fluxes caused by a specified fixed source. Neutron, gamma, and coupled neutron--gamma problems may be solved in either the forward or adjoint (backward) modes. Cross sections describing upscatter, as well as the usual downscatter, may be employed. This report describes the use of ANISN-L; this is a revised version of ANISN which handles both large and small problems efficiently on CDC-7600 computers. (RWR)

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During 1972 and 1973 a study was conducted in the B-C Cribs, 200 East Area, to learn the extent to which jackrabbits (Lepus californicus) and their predators had dispersed buried radioactive wastes in their fecal pellets and scats. The specific objective was to gather sufficient data on the pattern of dispersal so that statistically valid sampling strategies could be developed in future programs, depending upon management planning objectives for the area. A secondary objective was to relate these data with parameters, such as topography, wind direction, vegetation types, animal behavior, that might help explain the pattern of dispersal. In 1972, 2625 circular sampling sites were surveyed along 30 transects radiating out 2.4 to 3.2 km from the B-C Cribs. Radioactive contaminated feces, urine, soil and vegetation were distributed in all directions from the cribs, but the area to the south and southwest was more densely and uniformly contaminated. Of the ultimate sampling units surveyed, 278 or 10.6% had activity in excess o f 10,000 counts per minute (cprn) measured with a Geiger-Mueller counter. Of these 278 circular areas, 179 or 64% were found within 0.5 km of the cribs, 23.4% were between 0.5 and 1.0 km, and the remaining 12.2% …

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The overall risk evaluation for various radioactive waste management concepts includes calculation of radiation doses to individuals and local populations. Radiation doses are the most appropriate measure of the consequences of unforeseen releases of radioactive materials to the environment and dose criteria are available by which the severity may be judged. A comprehensive dose computational model, developed and used for other Atomic Energy Commission studies, has been adopted to improve its flexibility and to assist in evaluating alternative means for disposal of high-level waste. Typical input terms for normal use include source terms (radionuclide release rates to man's immediate environment) and dilution factors. Outputs include individual pathway doses and total doses to maximum individuals for both an urban and a rural population. Whole-body doses plus doses to other critical organs are obtained, as well as the fractional dose contributions of individual nuclides. Doses for one year or total doses for fifty years of exposure are available. Although all of the many factors and assumptions used can be changed if desired, listings of those currently being used are given. Factors used are for the most part from recognized sources, supplemented by local data and assumptions as necessary. For doses to individuals, …

Preliminary results are presented from calculations concerning the kinetics and transport of a single SST exhaust plume. Curves are shown that exhibit the effect of different transport rates on axis ozone concentration and total ozone destruction per unit plume length. (auth)

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Gold plated Kovar pads were eutectic bonded to p and n-type SiGe specimens using a 98 wt% AuSi preform alloy. This joining technique was shown to yield strong reliable bonds. A method based on this technique is described for producing bonding pads to the outermost elements of the MC2730 RTG thermopile. (auth)

The entire Argonne Radiological Impact Program is briefly outlined, and part of the program dealing with radiation hazards from nuclear power plants is discussed in detail. Various models and predictions of carcinogenic hazard are examined and compared with actual experience in U. S. and foreign populations. All of the models predict a significant increment in malignant mortality with increasing background. Observation of the actual populations at risk shows not only no increment, but an actual decrement, so that these predictions are left quite without observational support. It is concluded that extrapolation of high- rate and usually hlgh dose-level studies to low rates and low levels is probably invalid, and that radiation at such levels and rates does not constitute an environmental carcinogen of significance. (auth)

This bibiography is a compilation of unclassified publications of work done at the Los Alamos Scientific Laboratory (LASL) for the years 1967 through 1971. Papers published in those years are included regardless of when they were actually written. Publications received too late for inclusion in earlier compilations are also included. Declassification of previously classified reports is considered to constitute publication. All classified issuances are omitted. The bibliography includes LASL reports, papers released as non-LASL reports, journal articles, books, chapters of books, conference papers (whether published separately or as part of conference proceedings issued as books or reports) papers published in congressional hearings, theses, and U. S. patents. Papers are included in the following categories: accelerators, aerospace studies, analytical technology, astrophysics, atomic physics, biology and medicine, chemical kinetics, chemistry, cryogenics, crystallography, engineering and equipment, EPR and NMR studies, equation of state and shock studies, explosives and detonations, fission physics, health and safety, hydrodynamics and radiation transport, instruments, mathematics and computers, mediumenergy physics, metallurgy and ceramics technology, molecular spectroscopy, Moessbauer effect, neutronics and criticality studies, nuclear physics, nuclear safeguards, optics and lasers, organic chemistry, physics, plasma physics, propulsion systems, reactor technology, solid state science, theoretical physics, thermionics, -waste disposal, and miscellaneous. Author, …

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A routine, BCMAT, is presented for solving a system of linear algebraic equations with a periodic band matrix. (DLC)

Abstracts of 1803 U. S. and non-U. S. publications concerning a broad range of standards used in nuclear science and technology are included. The publication dates span the period 1962 through 1972, inclusive. Abstracts are arranged chronologically within four categories entitled Reactors and Engineering, Instruments and Calibration, Radiation and Radiation Protection, and Miscellaneous. A subject index is also included. (auth)

S>The effect of a 0th harmonic octupole (that is, constant in dependence on azimuth) on stable betatron oscillations is treated in smooth approximation. In this approximation, an exact invariant is obtained. Bounded motion results, except when the octupole component is very large. A condition for stability- is obtained and, in the case of bounded motion, an expression for the amplitude variation is given. Some comments are made regarding the method of phase averaging. (auth)

The SNAP 8 Program was directed toward the development of lightweight nuclear reactors which would operate in space for greater than 10,000 hr at a power level of 600 kW(t). Toward this objective, two reactors were designed, built, and successfully operated. The experimental reactor (S8ER) was an engineering test of a prototype core, but did not have flight-developed hardware. The developmental reactor (S8DR) was a nuclear system test to verify the operability of the integrated flight configuration. The development, design characteristics, operating experience, experimental results, and supporting tests for the S8ER and S8DR are discussed. 20 references. (auth)

Data are summarized on radioactivity in environmental samples collected during 1972 within the Hanford plant boundaries, but excluding areas under the control of individual contractors. Some data are included on samples collected off-site. Data are included on the content of /sup 90/Sr, tritium, and total alpha radioactivity in samples of Columbia River water, surface waters, and drinking water collected at various locations; the content of /sup 131/I and gross alpha and BETA radioactivity in air samples collected both on-site and off-site; the content of /sup 239/Pu in samples of soil and vegetation; and the conlent of /sup 137/Cs, /sup 90/Sr, /sup 65/Zn, and /sup 239/Pu in tissue sampl es of migratory waterfowl, native birds, deer, and other wild mammals. Aerial surveys of gamma radioactivity were conducted at an altitude of 500 ft twice durirg 1972 and no unusual radioactivity was detected. Active, inactive, and retired radioactive waste burial sites were inspected for general physical condition and evidence of disturbance. (CH)