Many configuration, transportation and operating alternatives are available to the Office of Civilian Radioactive Waste Management (OCRWM) in the design and operation of the Federal Radioactive Waste Management System (FWMS). Each alternative has different potential impacts on system throughput, efficiency and the thermal and radiological characteristics of the waste to be shipped, stored and emplaced. A need therefore exists for a quantitative means of assessing the ramifications of alternative system designs and operating strategies. We developed the Systems integration Operations/Logistics Model (SOLMOD). That model is used to replicate a user-specified system configuration and simulate the operation of that system -- from waste pickup at reactors to emplacement in a repository -- under a variety of operating strategies. The model can thus be used to assess system performance with or without Monitored Retrievable Storage (MRS), with or without consolidation at the repository, with varying shipping cask availability and so forth. This simulation capability is also intended to provide a tool for examining the impact of facility and equipment capacity and redundancy on overall waste processing capacity and system performance. SOLMOD can measure the impacts on system performance of certain operating contingencies. It can be used to test effects on transportation and …

This petition seeks exclusion for stabilized and solidified sludge material generated by treatment of wastewater from the 300-M aluminum forming and metal finishing processes. The waste contains both hazardous and radioactive components and is classified as a mixed waste. The objective of this petition is to demonstrate that the stabilized sludge material (saltstone), when properly disposed, will not exceed the health-based standards for the hazardous constituents. This petition contains sampling and analytical data which justify the request for exclusion. The results show that when the data are applied to the EPA Vertical and Horizontal Spread (VHS) Model, health-based standards for all hazardous waste constituents will not be exceeded during worst case operating and environmental conditions. Disposal of the stabilized sludge material in concrete vaults will meet the requirements pertaining to Waste Management Activities for Groundwater Protection at the Savannah River Site in Aiken, S.C. Documents set forth performance objectives and disposal options for low-level radioactive waste disposal. Concrete vaults specified for disposal of 300-M saltstone (treated F006 sludge) assure that these performance objectives will be met.

This paper is organized as follows: First, I describe the state of neutrino phenomenology. Emphasis is placed on sin/sup 2/ /theta//sub W/, its present status and future prospects. In addition, some signatures of ''new physics'' are described. Then, kaon physics at Fermilab is briefly discussed. I concentrate on the interesting rare decay K/sub L/ /yields/ /pi//sup 0/e/sup +/e/sup /minus// which may be a clean probe direct CP violation. Neutrino mass, mixing, and electromagnetic moments are surveyed. There, I describe the present state and future direction of accelerator based experiments. Finally, I conclude with an outlook on the future. Throughout this summary, I have drawn from and incorporated ideas discussed by other speakers at this workshop. However, I have tried to combine their ideas with my own perspective on neutrino physics and where it is headed. 49 refs., 3 figs., 4 tabs.

A fast ICRF magnetosonic wave, launched into a tokamak plasma, scatters off turbulent density fluctuations in the plasma edge. We use cold-fluid theory to calculate the angular distribution of the scattered wave and find it to be predominantly perpendicular to the incident wavevector for second harmonic majority heating. We calculate the mean free path and find it to be large compared to the size of tokamak devices. Therefore, scattering of ICRF magnetosonic waves by density turbulence is an utterly negligible effect. 2 refs., 1 fig.

An international group of physicists is developing the concept and design of a Tau-Charm Factory: a two-ring, electron-positron, circular collider with 1.5 /< =/ /radical/s /< =/ 4.2 GeV and a design luminosity of 10/sup 33/ cm/sup /minus/2/ s/sup /minus/1/. This paper presents the concept of the facility and outlines the tau lepton physics which can be done. A companion talk by R. Schindler discusses the D/sup 0/, D/sup /+-//, and D/sub s/ physics at a Tau-Charm Factory. 25 refs., 2 tabs.

This report describes the progress of 13 Hanford ground-water monitoring projects for the period October 1 to December 31, 1988. There are 16 individual hazardous waste facilities covered by the 13 ground-water monitoring projects. The Grout Treatment Facility is included in this series of quarterly reports for the first time. The 13 projects discussed in this report were designed according to applicable interim-status ground-water monitoring requirements specified in the Resource Conservation and Recovery Act of 1976 (RCRA). During this quarter, field activities primarily consisted of sampling and analyses, and water-level monitoring. The 200 Areas Low-Level Burial Grounds section includes sediment analyses in addition to ground-water monitoring results. Twelve new wells were installed during the previous quarter: two at the 216-A-29 Ditch, six at the 216-A-10 Crib, and four at the 216-B-3 Pond. Preliminary characterization data for these new wells include drillers&#x27; logs and other drilling and site characterization data, and are provided in Volume 2 or on microfiche in the back of Volume 1. 26 refs., 28 figs., 74 tabs.

We present a one-dimensional analytic theory of the ICRF gyroresonant absorption and mode-conversion, for the problem of minority fundamental resonance. Using the wave phase-space method, and the theory of linear mode conversion therein, we obtain explicit expressions for the coefficients of transmission (T), reflection (R), conversion (C), absorption (A). 7 refs., 2 figs.

The Arc transport line, which brings high-energy, high-intensity electron and positron bunches from the SLAC linac to the Stanford Linear Collider final focus section, has been in operation for the past few years. In this paper, we will review the techniques developed for the optical tune-up and diagnostics, recent performance, and on-going improvement programs. 13 refs., 4 figs., 1 tab.

WN{sub x}/GaAs Schottky contacts formed by reactive sputtering were found to be thermally stable up to an annealing temperature of {approximately}900{degrees}C. The interface morphology and structure of this contact under high temperature annealing conditions ( > 700{degrees}C) have been investigated by transmission electron microscopy (TEM) and x-ray diffractometry techniques. For the as-deposited samples, the thin film had an amorphous structure. After annealing at high temperatures, the amorphous phase transformed to {alpha}-W and W{sub 2}N phases. However, the contact interface remained thermally stable up to 850{degrees}C. Cross-sectional TEM micrographs revealed that annealing at temperatures above 850{degrees}C resulted in the formation of pockets'' beneath the interface. This phenomenon has been correlated with the electrical properties of the contacts, e.g., an enhancement of the barrier height of the contact. Comparisons between the interface morphology of this system and other refractory metal nitride contacts (e.g., TiN/GaAs) are also presented.

KAOS/LIB-V: A library of processed nuclear responses for neutronics analyses of nuclear systems has been generated. The library was prepared using the KAOS-V code and nuclear data from ENDF/B-V. The library includes kerma (kinetic energy released in materials) factors and other nuclear response functions for all materials presently of interest in fusion and fission applications for 43 nonfissionable and 15 fissionable isotopes and elements. The nuclear response functions include gas production and tritium-breeding functions, and all important reaction cross sections. KAOS/LIB-V employs the VITAMIN-E weighting function and energy group structure of 174 neutron groups. Auxiliary nuclear data bases, e.g., the Japanese evaluated nuclear data library JENDL-2 were used as a source of isotopic cross sections when these data are not provided in ENDF/B-V files for a natural element. These are needed mainly to estimate average quantities such as effective Q-values for the natural element. This analysis of local energy deposition was instrumental in detecting and understanding energy balance deficiencies and other problems in the ENDF/B-V data. Pertinent information about the library and a graphical display of the main nuclear response functions for all materials in the library are given. 35 refs.

The objective of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation doses that populations could have received from nuclear operations at Hanford since 1944. The project is being managed and conducted by Pacific Northwest Laboratory under the direction of an independent Technical Steering Panel. During the reporting period, we continued revision of Work Plan to reflect phased approach, began incorporating comments from TSP Source Terms Subcommittee into a draft report, continued internal PNL clearance of a draft report, began preparing information to be presented at the May TSP meeting on the Columbia River (between Priest Rapids Dam and McNary Dam), completed a draft report summarizing the approach selected for atmospheric modeling, continued developing data bases on meteorological and numerical data, and met with representatives of the Colville, Spokane, Yakima, and Nez Perce tribes to discuss contracts, data collection, proposal revisions, and other aspects of the HEDR Project.

A major objective of the SP-100 Program Nuclear Assembly Test is to demonstrate the performance of a full-scale nuclear subsystem of a 100-kWe space nuclear power supply. The test will be run in a large vacuum chamber to protect the Nb-1Zr components from oxidation during operation. Much information about the oxidation of niobium and Nb-1Zr alloy already exists, and previous work in this area is reviewed. Oxidation of Nb-1Zr can proceed by solution, internal oxidation, and/or film formation. At temperatures up to about 650 K (377/degree/C), oxidation generally follows a parabolic rate law because of the formation of protective oxide(s). At higher temperatures, oxidation becomes linear, but results are extremely sensitive to pressure and other system variables. Results obtained by several investigators could not be predicted using empirical equations developed by one investigator relating the increase in oxygen concentration to pressure, temperature, time, and specimen thickness. Additional data are required to provide more reliable guidelines for system operation that will protect against catastrophic effects. 20 refs., 12 figs., 7 tabs.

The purpose of this manual is to provide users of UCB-NE-108 with the information necessary to use UCB-NE-108 effectively. UCB-NE-108 is a computer code for calculating the fractional release rate of readily soluble radionuclides that are released from nuclear waste emplaced in water-saturated porous media, and transported through layers of porous media. Waste placed in such environments will gradually dissolve. For many species such as actinides and rare earths, the process of dissolution is governed by the exterior flow field, and the chemical reaction rate or leaching rate. In a spent-fuel waste package the soluble cesium and iodine accumulated in fuel-cladding gaps, voids, and grain boundaries of spent fuel rods are expected to dissolve rapidly when groundwater penetrates the fuel cladding. UCB-NE-108 is a code for calculating the release rate at the interface of two layers of porous material, such as the backfill around a high-level waste package and natural rock, to check compliance with the US Nuclear Regulatory Commission's (USNRC) subsystem performance objective. It is an implementation of the analytic solution given below. 6 refs., 2 figs.

The quenching of Einstein A-coefficients was observed by measuring the branching ratio of visible and XUV line intensities for CIV, CIII, and NV ions. 16 refs., 11 figs., 1 tab.

Transient photoconductivity and ESR measurements were done to relate the ionized dangling bond density of thick hydrogenated amorphous silicon (a-Si:H) detectors. We found that only a fraction (/approximately/30--35%) of the total defect density as measured by ESR is ionized when the detector is biased into deep depletion. The measurements on annealed samples also show that this fraction is about 0.3. An explanation based on the shift of the Fermi energy is given. The measurements show that the time dependence of relaxation is a stretched exponential. 8 refs., 4 figs., 1 tab.

Erosion/corrosion in single-phase piping systems was not clearly recognized as a potential safety issue before the pipe rupture incident at the Surry Power Station in December 1986. This incident reminded the nuclear industry and the regulators that neither the US Nuclear Regulatory Commission (NRC) nor Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code require utilities to monitor erosion/corrosion in the secondary systems of nuclear power plants. This report provides a brief review of the erosion/corrosion phenomenon and its major occurrence in nuclear power plants. In addition, efforts by the NRC, the industry, and the ASME Section XI Committee to address this issue are described. Finally, results of the survey and plant audits conducted by the NRC to assess the extent of erosion/corrosion-induced piping degradation and the status of program implementation regarding erosion/corrosion monitoring are discussed. This report will support a staff recommendation for an additional regulatory requirement concerning erosion/corrosion monitoring. 21 refs., 3 tabs.

Over 4100 ft (1100 ft oriented) of Mesaverde core was taken during the drilling of the three Multiwell Experiment (MWX) wells, for study in a comprehensive core analysis program. This core traversed five separate depositional environments (shoreline/marine, coastal, paludal, fluvial, and paralic), and almost every major sand in the Mesaverde at the site was sampled. This paper summarizes MWX core analysis and describes the petrophysical properties at the MWX site; reservoir parameters, including permeabilities of naturally fractured core; and mechanical rock properties including stress-related measurements. Some correlations are made between reservoir properties and mineralogy/petrology data. Comparisons are made between the properties of lenticular and blanket sandstone morphologies existing at the site. This paper provides an overview of a complete core analysis in a low-permeability sandstone reservoir. 66 refs., 17 figs. , 9 tabs.

This document provides a framework for the use of four Mobile Energy Laboratories (MELs) by federal agencies. These laboratories are made available by the US Department of Energy Federal Energy Management Program (FEMP) to measure and analyze the efficiency of on-site energy conversion, distribution, and end-use application. The MELs are customized passenger buses converted to provide transportation and storage of sophisticated energy monitoring, auditing, and analysis equipment. The MELs also provide mobile work space for specially trained engineers and technicians. One MEL is currently assigned to each of the following agencies: Department of the Army, Department of the Air Force, Department of the Navy, and Department of Energy. Experience over the past five years has indicated the need for centralized MEL administration, application scheduling, test procedure development, user training, and technical oversight. This need is evidenced by increasing requests for MEL use and the economies available by having trained full-time MEL operators and near continuous MEL operation. Other evidence suggests that a regional, rather than Departmental, administration can reduce the costs of MEL relocation.

This is one of nine studies undertaken by contractors to the US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM), to provide a technical basis for re-evaluating the role of a monitored retrievable storage (MRS) facility. The study evaluates the relative reliabilities of systems with and without an MRS facility using current facility design bases. The principal finding of this report is that the MRS system has several operational advantages that enhance system reliability. These are: (1) the MRS system is likely to encounter fewer technical issues, (2) the MRS would assure adequate system surface storage capacity to accommodate repository construction and startup delays of up to five years or longer if the Nuclear Waste Policy Amendments Act (NWPAA) were amended, (3) the system with an MRS has two federal acceptance facilities with parallel transportation routing and surface storage capacity, and (4) the MRS system would allow continued waste acceptance for up to a year after a major disruption of emplacement operations at the repository.

Disposal of spent fuel or high level nuclear waste into marine sediments would create high temperature-high gamma radiation environments adjacent to waste canisters. Under these conditions sediments will react producing pore waters that differ significantly from those occurring naturally. These changes may enhance canister corrosion or facilitate transport of radionuclides through unreacted sediments beyond the heated zone. In addition, the term &#x27;&#x27;near field&#x27;&#x27; needs clarification, as it is used widely without having a precise meaning. Research in three areas was undertaken to improve our understanding of near field chemical processes. Initially, isothermal experiments were carried out in &#x27;&#x27;Dickson&#x27;&#x27; hydrothermal systems. These were followed by an experimental program directed at understanding the chemical effects of temperature-gradient induced transport. Finally, additional experimentation was done to study the combined effects of hydrothermal conditions and intense gamma radiation. Having completed this body of experimental work, it was concluded that near field conditions are not an obstacle to the safe use of abyssal marine sediments for the disposal of spent fuel or high level nuclear wastes. 41 refs., 6 figs., 17 tabs.

Growth of perturbations due to stimulated thermal Rayleigh scattering was observed on a laser beam propagating in a 1 meter cell of CC14. Initial sinusoidal irradiance perturbations were seeded onto the laser leam, and their amplification in the cell was recorded by a near field camera. The perturbation growth rate is in agreement with analytical predictions of linearized propagation theory.

The radial charge-state distribution and transport of iron impurity ions in ohmically heated TFTR plasmas has been determined by a detailed comparison of the x-ray spectra obtained from a high resolution multi-chord crystal spectrometer with the predictions from plasma modeling calculations. 9 refs., 3 figs., 1 tab.

This paper is an attempt to provide a summary review of conclusions from previous studies on this subject. Subject headings include: conceptualization of the greenhouse effect, the climatic effect of doubled CO/sub 2/, interpretation of the climatic record, diagnosis of apparent and possible model deficiencies, and the palaeoclimatic record.

The Advanced Neutron Source (ANS) (Difilippo, 1986; Gamble, 1986; West, 1986; Selby, 1987) will be the world's best facility for low energy neutron research. This performance requires the highest flux density of all non-pulsed reactors with concomitant low thermal inertial and fast response to upset conditions. One of the primary concerns is that a flow cessation of the order of a second may result in fuel damage. Such a flow stoppage could be the result of break in the primary piping. This report is a review of methods for assessing pipe break probabilities based on historical operating experience in power reactors, scaling methods, fracture mechanics and fracture growth models. The goal of this work is to develop parametric guidance for the ANS design to make the event highly unlikely. It is also to review and select methods that may be used in an interactive IBM-PC model providing fast and reasonably accurate models to aid the ANS designers in achieving the safety requirements. 80 refs., 7 figs.