Monsanto Research Corporation is charged with processing encapsulated plutonium dioxide heat sources into radioisotopic thermoelectric generators (RTGs) to support deep-space missions. One of the problems associated with the sometimes protracted ground storage of these devices is the ingrowth of carbon dioxide and carbon monoxide in the gas phase due to the cyclical reaction established between the fuel (/sup 238/PuO/sub 2/) and the carbon impact body. This ingrowth proceeds according to the two equations: x(CO) + <PuO/sub 2/> = x(CO/sub 2/) + < PuO/sub 2-x/ and x(CO/sub 2/) + x < C > = 2x(CO), etc. To reduce this effect, a gas management system was instituted that enabled periodic removal of the generated CO and CO/sub 2/ with replacement by argon. The removal of these components was monitored and permitted an assessment of the degree of substoichiometry as well as its effect on the chemical activity of the CO and CO/sub 2/. This in turn was used to estimate the oxygen activity and to calculate ..delta.. anti G(O/sub 2/) as a function of stoichiometry.

A two-dimensional numerical model of a high-gain (electron-beam power > input laser beam power) free-electron laser (FEL) has been constructed which includes the effects of diffraction, refraction, and off-axis electron-beam current density and wiggler field variations. In this model, laser beam propagation is governed by a paraxial wave equation with FEL source terms. Conventional resonant electron analysis is used to represent the trapping and deceleration of electrons by the electromagnetic field. The trapped electron-beam current density is forced to decrease as the size of the trapping potential decreases so that detrapping can be simulated. The variable-parameter wiggler field is chosen so that synchronism can be maintained at a single, arbitrary radial position. The magnetic field varies at other radial positions in accordance with Maxwell's equations.

Economic development of energy sufficiency programs for developing countries are planned cooperatively with the US. Feasibility studies are proposed using each nation's resources. (PSB)

A method for separating a continuous beam of relativistic particles into four pulsed beams is investigated theoretically. The separation is periodic with period 2..pi../..omega.. so that each of the four beams consists of current pulses of duration ..pi../..omega... The separation is accomplished by a series of rf cavities in the beam line. The cavities operate in the TM/sub 110/ and have frequencies, ..omega.., 3..omega.., 5..omega.., 7..omega.., etc. The transverse momentum imparted to the beam particles results in a time-dependent displacement of the beam centroid at a position downstream of the cavity array. The mathematical limitations imposed by truncating a Fourier series are discussed, and an expression derived for the necessary phase and amplitude of each cavity. The rf induced by the beam in the cavities is treated in detail, and does not appear to be a serious problem.

Progress is briefly described on the following topics: (1) study of rare muon induced reactions, (2) measurement of ..pi../sup -/p ..--&gt;.. n + ..gamma.. and search for the eta/sub c/, (3) production of high-mass dimuons by pions, (4) production of high mass ..mu.. pairs in the forward direction in ..pi..-nucleus collisions, (5) Crystal Ball group, (6) detector studies, (7) proposed experiment at LEP, and (8) proposal to study electron-positron collisions. (WHK)

Strontium-90 and promethium-147 are fission product radionuclides with potential for use as heat source materials in high reliability, non-interruptible power supplies. Interest has recently been expressed in their utilization for Department of Defense (DOD) applications. This memorandum summarizes the current inventories, the annual production rates, and the possible recovery of Sr-90 and Pm-147 from nuclear materials production operations at Hanford and Savannah River. Recovery of these isotopes from LWR spend fuel utilizing the Barnwell Nuclear Fuels Plant (BNFP) is also considered. Unit recovery costs at each site are provided.

A geothermal test well was sited and drilled approximately 0.8 miles (1.3 km) east of Broadwater Hot Springs, near Helena, Montana. The site is on the property of the State Nursery, along the north side of Ten Mile Creek. The purpose of the drilling was to test a thermal infrared imagery anomaly and to evaluate whether a source of warm water for space heating of a series of new greenhouses could be developed to replace ones destroyed in the spring 1981 flooding of Ten Mile Creek. The well was drilled to 280 feet total depth, with no success in obtaining hot or even warm water.

The neutron-induced fission cross sections of /sup 242m/Am and /sup 245/Cm have been measured over an energy range of 10/sup -4/ eV to approx. 20 MeV in a series of experiments at three facilities during the past several years. The combined results of these measurements, in which only sub-milligram quantities of enriched isotopes were used, yield cross sections with uncertainties of approximately 5% below 10 MeV relative to the /sup 235/U standard cross section used to normalize the data. We summarize the resonance analysis of the /sup 242m/Am(n,f) cross section in the eV region. Hauser-Feshbach statistical calculations of the detailed fission cross sections of /sup 235/U and /sup 245/Cm have been carried out over the energy region from 0.1 to 5 MeV and these results are compared with our experimental data.

The advantages of conversion from Diatron 20 to Diatron 4 are discussed including economics, multi-gas detection capability, and improved helium sensitivity. Conversion procedures are described. (WHK)

When helium leak detecting is hindered by a system or atmosphere saturated with helium, leak checking can be continued by modifying the DuPont 120SSA/24-120 Mass Spectrometer Leak Detector to detect neon. Although DuPont markets a three gas leak detector (helium, neon and argon), the DuPont 120SSA/24-120 is convertible to neon by simply changing the magnet and retuning for neon peak. The sensitivity is 2 x 10/sup -9/ Atm/cc/sec/division neon. If an increase in sensitivity is desired, throttle diffusion pump with valve or install choke. Modification procedures and tuning procedures are described. (WHK)

Purpose of this document is to compare and contrast the overall burial costs of the glass and ceramic waste forms, including processing, storage, transportation, packaging, and emplacement in a repository. Amount of waste will require approximately 10,300 standard (24 in. i.d. x 9-5/6 ft length) canisters of waste glass, each containing about 3260 lb of waste at 28% waste loading. The ceramic waste form requires about one-third the above number of standard canisters. Approximately $2.5 billion is required to process and dispose of this waste, and the total cost is independent of waste form (glass or ceramic). The major cost items (about 80% of the total cost) for all cases are capital and operating expenses. The capital and 20-year operating costs for the processing facility are the same order of magnitude, and their sum ranges from about one-half of the total for the reference glass case to two-thirds of the total for the ceramic cases.

Charged-particle transport systems consisting of magnetic quadrupole lenses have been employed in recent years in the study of (n, charged particle) reactions. We have completed a new transport system that is based both on magnetic lenses as well as electrostatic fields. The magnetic focusing of this charged-particle guide is provided by six magnetic quadrupole lenses arranged in a CDCCDC sequence (in the vertical plane). The electrostatic field is produced by a wire at high voltage which stretches the length of the guide and is physically at the center of the magnetic axis. The magnetic lenses are used for charged particles above 5 MeV; the electrostatic guide is used for lower energies. This hybrid system possesses the excellent focusing and background rejection properties of other magnetic systems. For low energy charged-particles, the electrostatic transport avoids the narrow band-passes in charged-particle energy which are a problem with purely magnetic transport systems. This system is installed at the LLNL Cyclograaff facility for the study of (n, charged particle) reactions at neutron energies up to 35 MeV.

The subject of this review is intense ion beam propagation and the possibilities of measuring time dependent ion energy in the beam. Propagation effects discussed include charge separation, charge and current autoneutralization, electron thermalization and current neutralization decay. The interaction of a plasma beam with material obstacles, like collimators, and with transverse magnetic fields is also described. Depending on beam energy, density and pulse length, these interactions can include material ablation with plasmadynamic flow and undeflected propagation across transverse magnetic fields by a polarization drift. On the basis of this review I conclude that three diagnostics: a single floating potential probe, net current probes (Faraday cups) and a Rutherford scattering spectrometer appear capable of giving prompt, time dependent ion energy measurements.

Various facets of a thermonuclear type plasma that will likely require special considerations or hardening of applied diagnostic instrumentation are reviewed. The discussion will include both on-line diagnostic instrumentation requirements for satisfactory operation and considerations to reduce integrated radiation damage sufficiently for a reasonable diagnostic lifetime. Several new diagnostics aimed specifically at measurements of the plasma characteristics most appropriate to a thermonculear reactor type plasma are discussed. This will include instrumentation needed to make quantitative energy flow measurements during long term operation with the expected high input power sources, and locally very high wall power loadings. The second part of this lecture will broaden diagnostics to include materials damage measurements needed for engineering design studies. This will include needed diagnostic instrumentation to assess first wall damage, sputtering erosion at walls (and high power beam dumps), and radiation damage to components such as insulators.

We present data on proton-proton collisions, obtained at the CERN Intersecting Storage Rings, in which two roughly back-to-back ..pi../sup 0/'s of high transverse momentum (p/sub T/) were produced. The angular distribution of the dipion axis relative to the collision axis is found to be independent of both the effective mass m of the dipion system and the centre-of-mass energy ..sqrt..s of the proton-proton collision. The cross-sections dsigma/dm at the two values of ..sqrt..s satisfy a scaling law of the form dsigma/dm = G(x)/m/sup n/, where x = m(..pi../sup 0/,..pi../sup 0/)/..sqrt..s and n = 6.5 +- 0.5. We show from our data that the leading ..pi../sup 0/ carries most of the momentum of the scattered parton. Given this fact, the axis of the dipion system follows closely the direction of the scattered constituents, and we exploit this to determine the angular dependence of the hard-scattering subprocess. We also compare our data with the lowest order QCD predictions using structure functions as determined in deep-inelastic scattering and fragmentation functions from electron-positron annihilation.

To improve production of usable antiprotons using the proton beam from the main ring and the lossless injection of cooled antiprotons into the main ring, modifications of the main ring lattice are recommended.

The Soviet Union has described industrial use of nuclear explosions to produce underground hydrocarbon storage. To examples are in the giant Orenburg gas condensate field. There is good reason to believe that three additional cavities were created in bedded salt in the yet to be fully developed giant Astrakhan gas condensate field in the region of the lower Volga. Although contrary to usual western practice, the cavities are believed to be used to store H/sub 2/S-rich, unstable gas condensate prior to processing in the main gas plants located tens of kilometers from the producing fields. Detonations at Orenburg and Astrakhan preceded plant construction. The use of nuclear explosions at several sites to create underground storage of highly corrosive liquid hydrocarbons suggests that the Soviets consider this time and cost effective. The possible benefits from such a plan include degasification and stabilization of the condensate before final processing, providing storage of condensate during periods of abnormally high natural gas production or during periods when condensate but not gas processing facilities are undergoing maintenance. Judging from information provided by Soviet specialists, the individual cavities have a maximum capacity on the order of 50,000 m/sup 3/.

Lawrence Livermore National Laboratory (LLNL) has conducted a long-term single-pass continuous-flow (SPCF) leaching test of the glass waste form PNL 76-68. Leaching rates of Np, Pu, and various stable elements were measured at 25/sup 0/ and 75/sup 0/C with three different solutions and three different flow rates. The purposes of the study were: (1) to compare SPCF leaching results with the results of a modified IAEA leach test performed by Pacific Northwest Laboratories (PNL); (2) to establish elemental leach rates and their variation with temperature, flow rate and solution composition; and (3) to gain insight into the leaching mechanisms. The LLNL and PNL leach tests yielded results which appear to agree within experimental uncertainties. The magnitude of the leach rates determined for Np and the glass matrix elements is 10/sup -5/ grams of glass/cm/sup 2/ geometric solid surface area/day. The rates increase with temperature and with solution flow rate, and are similar in brine and distilled water but higher in a bicarbonate solution. Other cations exhibit somewhat different behavior, and Pu in particular yields a much lower apparent leach rate, probably because of sorption or precipitation effects after release from the glass matrix. After the initial few days, most elements …

The Mirror Fusion Test Facility (MFTF) vaccum vessel will be about 60m long and 10m in diameter at the widest point. The allowable operating densities range from 2 x 10/sup 9/ to 5 x 10/sup 10/ particles per cc. The maximum leak rate of 10/sup -6/ tl/sec is dominated during operation by the deliberately injected cold gas of 250 tl/sec. This gas is pumped by over 1000 square meters of cryopanels, external sorbtion pumps and getters. The design and requirements have changed radically over the past several years, and they are still not in final form. The vacuum system design has also changed, but more slowly and less radically. This paper discusses the engineering effort necessary to meet these stringent and changing requirements. Much of the analysis of the internal systems has been carried out using a 3-D Monte Carlo computer code, which can estimate time dependent operational pressures. This code and its use will also be described.

Electron-photon transport calculations have been carried out for the 50 MeV electron beam generated by ATA when it is incident on a carbon beam dump. Energy spectra are calculated at various points within the dump for the purpose of determining the power density profile. In addition, energy spectra of scattered electrons transported through small holes in the dump are calculated for the purpose of determining the extent to which they would interfere with a beam-emittance and beam-energy diagnostic based on the extraction of small beamlets through penetrations in the dump.

The reliability of the emergency ac-power systems typical of several nuclear power plants was estimated, the costs of several possible improvements was estimated. Fault trees were constructed based on a detailed design review of the emergency ac-power systems of 18 nuclear plants. The failure probabilities used in the fault trees were calculated from extensive historical data collected from Licensee Event Reports (LERs) and from operating experience information obtained from nuclear plant licensees. It was found that there are not one or two improvements that can be made at all plants to significantly increase the industry-average emergency ac-power-system reliability, but the improvements are varied and plant-specific. Estimates of the improvements in reliability and the associated cost are estimated using plant-specific designs and failure probabilities.

The results of laboratory experiments involving the flow of two commercial flocculant solutions through Berea sandstone core plugs at 225/sup 0/C are summarized. The two flocculants used are TFL-398 and TFL-362 (commercial flocculants supplied by Tretolite Division of Petrolite Corporation). The flow of brine containing these flocculants through these sandstone cores resulted in considerable permeability reductions during the flow experiments even when used at concentrations of only 5 ppM. The reduction in permeability is attributed to the plugging of pore spaces by the degradation products. The results of these experiments demonstrated that the use of a flocculant can cause severe formation damage. It is, therefore recommended, to always conduct laboratory tests prior to the use of any specific flocculant for geothermal applications to avoid any damage to injection wells.

A method is described for locally rescaling the curvilinear coordinates used in continuous rezoning of Lagrangian meshes by the equipotential method. In this way the zone aspect ratio may be brought closer to unity.

This report gives a detailed description of the input and output of the statistical model code STAPRE for compound-nucleus reactions including a special section on the various level density options of the code. It is to be used in conjunction with the report IRK 76/01 + Add 76 + Add 78 by B. Strohmaier and M. Uhl which describes in detail the physical models on which the code is based and its general organization and structure.