Each of the seven tasks defined under this contract are discussed here. They include: (1) design support for an x-ray spectrometer for the ``Panchuela`` down-hole experiment at the Nevada Test Site; (2) development and demonstration of an optical alignment method for aligning the 180 degree bend achromatic magnetic section of the Ground Test Accelerator; (3) development of magnet support and manipulation concepts for the 17 magnets of the Ground Test Accelerator; (4) design support for the triplett magnet telescope assembly and its support structure (Neutral Particle Beam Program); (5) design and support for the beam diagnostic system for the Argonne Particle Beam experiment; (6) conceptual design for the modification of an Antares Marx tank for use in the Aurora Laser Program; and (7) design of poloidal gap for the Los Alamos ZTH reversed-field pinch machine.

This document is prepared in tabular form and depicts costs and safety analysis of a number of Mound construction projects. Some projects described include solvent waste handling, environmental buffer zone, and sanitary treatment plant.

This ADM documents the evaluation of the potential environmental impact hazards from the Environmental, Safety and Health Upgrades, Phase 3 project.

Interaction between fractures and rock matrix is considered in developing a criterion for treating fractured rock as a porous medium for the purpose of transport calculations. The value of a modified Peclet number determines the suitability of the equivalent porous medium approach. Using a porous medium mode, underground concentrations of {sup 14}CO{sub 2} are predicted for the proposed nuclear waste repository at Yucca Mountain, Nevada. Maximum concentrations near the ground surface are comparable to the USNRC limit for unrestricted areas; travel times are predicted to be hundreds to thousands of years for the assumed parameter values. 8 refs., 7 figs.

Pacific Northwest Laboratory has initiated a review of the Safeguards and Security systems at the Critical Mass Laboratory with regards to determining appropriate upgrading actions that assure that an effective and efficient Safeguards and Security posture consistent with DOE-RL policies, procedures, and priorities is effected. As a result of this review, PNL has concluded that specific upgrades are required at CML that provide a demonstrated enhancement to the overall security posture of the facility and are based upon prudent expenditures of government funds. It was further concluded that additional recommended upgrades provide minimal improvement to the overall security system at a significant outlay of funds.

Experimental leaching of spent fuel shows that some fission product species are preferentially released upon contact with water. We analyze the conservative case of bare spent fuel in contact with saturated tuff using diffusional mass transfer analysis. For the parameter values used, the USNRC release rate limit is not exceeded, except for {sup 99}Tc. The presence of a container and the distribution of water contact over time will assist in meeting this criterion. 6 figs., 2 tabs.

The railroad industry will have a very critical role in the eventual shipping of commercial spent fuel and defense high-level waste as provided under the Nuclear Waste Policy Act of 1982 and the 1987 amendments. The transport of spent fuel is expected to be accomplished by rail from 19 of the South`s 27 reactor sites to the proposed Yucca Mountain repository or possible monitored retrievable storage facility. The decline in total track availability, however, could significantly impact the federal government`s transportation program. Particularly the situation of continuing abandonments may limit rail opportunities at numerous reactor locations. Commercial nuclear reactor sites have the unfortunate problem of not being located on Class I railroad mainline tracks. The reactor sites are generally located in areas with limited rail traffic and thus vulnerable to rail abandonment procedures. The general deregulation of the railroad industry under the Staggers Act of 1980 also assisted in making rail abandonment, through the Interstate Commerce Commission, a rather simple and quick process. The effects of deregulation, however, have provided alternatives to abandonment. In particular, the Staggers Act has led to an enormous surge in the growth of short line and regional railroads. Such railroads have been able to effectively …

This Remedial Action Plan (RAP) has been developed to serve a two-fold purpose. It presents the series of activities which are proposed by the U.S. Department of Energy (DOE) to accomplish long-term stabilization and control of radioactive materials at the inactive uranium processing site located near Monument Valley, Arizona It also serves to document the concurrence of both the Navajo Nation and the U.S. Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by DOE and the Navajo Nation and concurrence by NRC, becomes Appendix B of the Cooperative Agreement.

Core bore samples were obtained from the severely damaged TMI-2 core during July and August, 1986. A description of the TMI-2 core bore drilling unit used to obtain samples; a summary and discussion of the data from the ten core bore segments which were obtained; and the initial results of analysis and evaluation of these data are presented in this report. The impact of the major findings relative to our understanding of the accident scenario is also discussed.

This report summarizes the 1981 experience and activities of the Monsanto Research Corporation relative to the control of ALO property damage from fires and other accidents.

Many computer programs with a variety of algorithms exist for controlling the closed orbit in synchrotrons. The scope of this note is rather modest in comparison. Based on a simple model, a study has been made to find out statistically how much kick angle is needed by each steering element and how much residual closed orbit deviation should be expected when the closed orbit is steered to go through the center of seven position monitors (M{sub 2} through M{sub 8}) in each cell. Seven independent kicks are supplied by two trim dipoles B{sub U} and B{sub D}, and six steering elements (H{sub 1} through H{sub 6}) with H{sub 3} and H{sub 4} assumed to have the same kick angle. If it is necessary to remove H{sub 3} to make a space there for a correction skew quadrupole (in every other cell), the kick angle of H{sub 4} would have to be doubled.

There are two fundamental reasons to have a full knowledge of the angular distribution of power from an insertion device: 1. To evaluate the heat-load distribution on the first optical element in a beamline. 2. To estimate the total radiated power which will impinge on the walls of an insertion device. This is important to ensure needed cooling of the insertion device walls. The photodesorption is another closely related phenomenon determined by the exposure of the insertion device walls to the radiated power and of consequence to the successful operation of the storage ring. In this paper, we will primarily focus on undulators, but also consider situations as the value of K increases to the wiggler regime. These calculations are very involved and cumbersome and we shall only present some specific results related to the 6-GeV insertion devices.

This memorandum recommends the use of water quenching, rather than air quenching, for pressed slugs in any future project to substantially update the Building 313-M slug manufacturing facility. At the outset of the recently canceled Project S-4092, Improved Slug Processing Facility (ISPF), 313-M, consensus of the SRP liaison team was to replace the existing water quench facility with air quenching. Principal motivations were to eliminate a liquid waste stream, reduce the quantity of process water used, and attain a more reliable mechanical system. During the ensuing years, unforeseen difficulties with air quenching have been realized. Also, effective methods of reducing and treating the waste streams generated by water quenching have been developed. Both methods the author believes will work. However, the propriety of either method of quenching is a function of the system into which it is being incorporated. Each method carried with it a lot of concealed constraint s and carefully designed additional equipment. There is today a consensus that water quenching is preferable. For future reference, some advantages and disadvantages of the two quenching methods are discussed.

This report details activities for the time period of November, 1987 through January, 1988. Further results are presented from the axially heterogeneous assembly ZPPR-17, a part of the JUPITER-III program. The loading of the ZPPR-17C assembly, with 13 half-inserted control rods, is described along with operational measurements, calculation models, and measurements and prediction of criticality. From ZPPR-17A, calculated and measured results are given for reaction rates and measured results for bowing, expansion and small sample worth experiments. From the earlier metal-fuel ZPPR-15 program results are given for measurements and calculations of Doppler reactivity coefficients.

The presentation given here is restricted to discrete event simulation. The complexity of and time required for many present and potential discrete simulations exceeds the reasonable capacity of most present serial computers. The desire, then, is to implement the simulations on a parallel machine. However, certain problems arise in an effort to program the simulation on a parallel machine. In one category of methods deadlock care arise and some method is required to either detect deadlock and recover from it or to avoid deadlock through information passing. In the second category of methods, potentially incorrect simulations are allowed to proceed. If the situation is later determined to be incorrect, recovery from the error must be initiated. In either case, computation and information passing are required which would not be required in a serial implementation. The net effect is that the parallel simulation may not be much better than a serial simulation. In an effort to determine alternate approaches, important papers in the area were reviewed. As a part of that review process, each of the papers was summarized. The summary of each paper is presented in this report in the hopes that those doing future work in the area will …

One of the uncomfortable features of the Chasman-Green lattice is that the chromaticity-correcting sextupoles are all very strong compared with those in the FODO-type lattice. Because of their strengths, when their arrangement creates certain harmonic components, the dynamic aperture is severely reduced and on is forced to add more sextupoles to eliminate harmful harmonic components.During the course of design studies, S. Kramer has made many computer runs to investigate tune shifts resulting from horizontal orbit deviations in sextupoles. An interesting observation is that the average tune shift is definitely related to the dependence of tunes on the betatron oscillation amplitudes (or, equivalently, the transverse emittances). This note is an ``attempt`` to explain the connection at least qualitatively. It is no more than an attempt since the explanation is not yet quantitative and it may even be somewhat inconsistent.

One of the most troublesome phenomena during the commissioning of synchrotrons is the linear horizontal-vertical coupling. Because of its linear nature, on can in principle obtain the analytical solution provided that all sources of skew quadrupole field are known completely in the entire ring. In spite of all this, many standard diagnostic procedures and measurements become rather confusing and often lead to wrong conclusions. The purpose of this note is to explain some of the simpler relation which are useful in understanding measurement of tunes and the amount of coupling.

This memorandum documents a study that showed a cyclic occurrence of porosity in U-Al alloys produced in Building 321-M. Review of process data shows that the extent of porosity is more pronounced in months of warm, humid weather and less pronounced in cooler, drier months. This porosity is most likely caused by hydrogen, which becomes dissolved in the molten U-Al alloy during casting. Although excessive porosity was the cause of some observed process anomalies, this type of porosity has no significant effect on yield or fuel tube quality.

This document establishes the need for an integral fuel oxidation test which can give confidence to the predictions made by the OXIDE computer code for fuel and core damage during water ingress events in the Modular High Temperature Gas Cooled Reactor (MHTGR). This testing will provide clear engineering evidence to demonstrate that the core of the MHTGR can survive a moisture ingress incident with minimum investment risk and without danger to the reactor personnel or to the public. In particular, these tests will determine the degree of particle debonding and compact stack densification as a function of the fractional compact matrix burnoff. Also included in the document is a description of the proposed tests, and, a test matrix of the planned experiments. 3 refs., 1 fig., 1 tab.

An extensive campaign of in situ deformation modulus measurements was recently completed using a standard NX borehole jack. These results were obtained in a granite intrusive where spent nuclear-fuel assemblies and electrical heaters had raised the rock temperatures 10{sup 0}C to 40{sup 0}C above ambient. We present an analysis of temperature effects based on 41 preheat and 63 post-heat measurements in three boreholes. Using analysis of covariance statistical techniques, we found that the deformation modulus is affected by heat, loading direction, and position within the borehole. The analysis also uncovered a significant interaction between the effects of heating and loading direction. We used 123 measurements from the same boreholes to evaluate the "Draft Standard Guide for Estimating the In Situ Modulus of Rock Masses Using the NX-Borehole Jack" which was recently proposed by Heuze. In particular, we examined the criterion for screening measurements in those cases where contact between the jack platen and the borehole wall was incomplete. We found that the proposed screen appears to operate randomly on the data and is therefore ineffective. 3 figs., 1 tab.

FY 1981 laboratory and field studies related to the Radionuclide Migration project are described. Results are presented for radiochemical analyses of water samples collected from the RNM-1 well and the RNM-2S satellite well at the Cambric site. Data are included for tritium, {sup 85}Kr, {sup 129}I, and {sup 36}Cl. The maximum-concentration tritium, peak appears to have arrived at RNM-2S near the end of FY-1981. Laboratory studies emphasize the sorptive behavior of alluvium and tuff and its dependence on mineralogy. Results from batch measurements and crushed-rock and whole-core column studies are presented.

Sorption of americium and plutonium was measured in a controlled, oxygen-free atmosphere and in air on a series of tuff samples. Sorption of plutonium was greater in the controlled atmosphere than in air. Sorption of both elements is higher on zeolitized tuff than devitrified tuff. Sorption of strontium, cesium, barium, cerium, and europium is being measured on tuff samples of mineralogies not previously studied, and samples from the USW-G1 drill hole have been selected for study. Work on the dependence of the sorption ratio on element concentration (barium and europium) and on solution-to-solid ratios is reported. Progress on controlling Eh and making Eh measurements is presented. Some tuff-water systems exhibit reduced or negative Eh values under oxygen-free conditions. Development of a method for encasing cores for flow studies is discussed. Field geologic mapping is being conducted in the Lunar Crater volcanic field of central Nevada. Mineralogy-petrology studies are being conducted on core samples from the USW-G1 exploration hole in Yucca Mountain. Zeolite heating tests of core samples from UE25a-1 show density, volume, and weight changes that correlate with alteration of mineral assemblages. Hydrogen-deuterium ratios in water evolved from a clinoptilolite specimen from Yucca Mountain have been measured. Jacket seals leaked …

The Spent Fuel Test-Climax (SFT-C) was conducted to evaluate the feasibility of retrievable deep geologic storage of commercially generated spent nuclear-reactor fuel assemblies. One of the primary aspects of the test was to measure the thermomechanical response of the rock mass to the extensive heating of a large volume of rock. Instrumentation was emplaced to measure stress changes, relative motion of the rock mass, and tunnel closures during three years of heating from thermally decaying heat sources, followed by a six-month cooldown period. The calculations reported here were performed using the best available input parameters, thermal and mechanical properties, and power levels which were directly measured or inferred from measurements made during the test. This report documents the results of these calculations and compares the results with selected measurements made during heating and cooling of the SFT-C.

The chemistry of groundwater at Yucca Mountain and vicinity has been reviewed and compared with the chemistry of water from the Nevada Test Site and surrounding areas such as the Amargosa Desert and Oasis Valley. Sodium is the primary cation and carbonate is the primary anion in water from the saturated zone of the tuffaceous aquifer at Yucca Mountain. Other major cations present are calcium, potassium, and magnesium; other major anions are sulfate and chloride, with lesser quantities of fluoride and nitrate. Aqueous silica is also present. The primary purpose of this review was to survey water-composition data and look for relations among the compositional variables that could provide insight into the processes that control the composition and would ultimately affect radionuclide transport. The following conclusions were inferred from the review. Major cation concentrations are controlled by rock dissolution and mineral precipitation reactions as well as by cation exchange with existing minerals. Aqueous carbonate initially comes from atmospheric and soil-zone carbon dioxide, but there is evidence at Yucca Mountain that carbon dioxide in the gas phase of the unsaturated zone supplies additional carbonate to saturated-zone water in the tuffaceous aquifer as mineral dissolution and precipitation reactions raise the pH of …