Conventional wet processing of textiles - dyeing, or application of such surface finishes as soil and water repellents, antistatic agents, fire retardants, permanent press agents, and starch - consumes about 0.19 quadrillion Btu's of energy per year, the equivalent of 30 million barrels of oil. Because wet processing involves immersion of the fabric in a water bath, most of the energy used is in the form of heat for drying. In the newer foam finishing approach, the chemicals for surface finishes are dispersed in a mixture of water and air. The chemicals are concentrated in a relatively small amount of water, and air is injected to form a thick, stable foam. Because little water is involved, drying time and temperature may be drastically reduced. Authur D. Little, Inc., conducted an economic and energy audit of foam processing that considered the technical feasibility, reliability, energy savings, and economic incentives for using foam finishing. We monitored four plants that finish textiles (carpets, broad-woven fabrics, and tubular knits). The plants were selected by the developer of the foaming process (United Merchants and Manufacturers, Inc.) to represent a wide range of textile finishing applications.

This report defines the concept of maintaining occupational exposures to radiation as low as is reasonably achievable (ALARA) and describes the elements necessary for specific licensees to implement, operate, and evaluate an effective ALARA program. Examples of cost-effectiveness analysis and optimization are provided. The rationale for providing more detailed guidance to specific licensees stems from the current recommendations provided by the International Commission on Radiological Protection, as well as from the increased regulatory emphasis on maintaining occupational exposures ALARA. The objective of this work is to provide the Nuclear Regulatory Commission with a basis for updating Regulatory Guide 8.10.

This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Special Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed here are ongoing. Results and conclusions described may change as the work continues.

At the Pacific Northwest Laboratory (PNL), we performed two sets of experiments to determine the effects of pertinent operational parameters and gas compositions on organic radioiodine (in particular methyl iodide (CH/sub 3/I)) capture by silver mordenite (AgZ). In the first set of experiments, we studied the effects of (1) hydrogen pretreatment of AgZ, (2) change in particle size of AgZ, and (3) the presence of water in the gas phase. In the second set of experiments we evaluated on a semi-quantitative basis the effects of nitric oxide (NO), nitrogen dioxide (NO/sub 2/), superficial face velocity, and temperature on CH/sub 3/I capture by reduced (hydrogen pretreated) silver mordenite (Ag/sup 0/Z). These studies have shown that AgZ, especially Ag/sup 0/Z, is an effective trap for CH/sub 3/I. However, its effectiveness varies with changes in operational parameters and is affected by other gases found in the process off gas of a nuclear reprocessing plant. Optimum trappig efficiency was achieved with Ag/sup 0/Z rather than AgZ, 20-40 mesh Ag/sup 0/Z rather than 0.16 cm extrudate, moisture in the gas stream, higher temperatures up to 200/sup 0/C, absence of NO, and lower superficial face velocities down to 3.75 m/min. Additionally, CH/sub 3/I can be converted …

The report from Lawrence Livermore National Laboratory, which covers the period from October 1981 to September 1982, is divided into three major sections. The first section, progress reports, includes studies in areas of industrial hygiene, instrument development, environmental protection, radiation protection and fire safety. The second section, technical notes, contains reports on interesting activities of a more limited scope. The third section lists recent publications. (JMT)

Two completely portable high-resolution germanium diode spectrometer systems are described. These detectors are capable of measuring transuranics, activation products, and fission products, including /sup 90/Sr, at sensitivities below the uncontrolled release criteria. The detectors measure x-rays, gamma-rays, or bremsstrahlung radiation as required and have been calibrated for a variety of decontamination and decommissioning scenarios. A description of a new technology for the in-situ determination of /sup 90/Sr is given.

Separate abstracts were prepared for most sections of this report. The one remaining section is theoretical chemistry. (DLC)

This paper describes a computer code, RYLLA, which models the deposition of x-rays into thin metal slabs, and transports the resulting photoelectrons, finding the distribution of electrons leaving the slab from both the front and back surfaces. The slab must be homogeneous, but can contain a mixture of up to 5 different elements. Due to the short electron mean free path at low electron energies, RYLLA should be used only for studying thin slabs, roughly < 100 mg/cm/sup 2/ for low Z metals, and < 10 mg/cm/sup 2/ for high Z metals. X-ray energies should be in the range of 1 to 150 keV, as they are deposited only via photoionization and Compton scattering processes. Following photoionization, a hole exists in the electron cloud of the absorbing atom. This fills either by Auger or fluoresence, resulting in lower energy holes which are also filled. Fluoresence photons are transported and absorbed in the same manner as the primary photons, except that they are isotropically produced. Once all photons have been transported and absorbed, and all holes have been filled, a space- and energy-dependent electron source spectrum has been obtained. This is used in a discrete ordinate expansion solution of the 1-D …

Past energy-consumption trends and future energy-conservation opportunities are investigated for the nation's iron and steel industry. It is estimated that, in 1980, the industry directly consumed approximately 2.46 x 10/sup 15/ Btu of energy (roughly 3% of total US energy consumption) to produce 111 million tons of raw steel and to ship 84 million tons of steel products. Direct plus indirect consumption is estimated to be about 3.1 x 10/sup 15/ Btu. Of the set of conservation technologies identified, most are judged to be ready for commercialization if and when the industry's capital formation and profitability problems are solved and the gradual predicted increase in energy prices reduces the payback periods to acceptable levels.

The Office of Industrial Programs of the Department of Energy has undertaken a program to demonstrate to industry the benefits of installing various energy-conserving devices and equipment. This report presents results on one of those systems, a high-temperature ceramic recuperator designed and manufactured by Sylvania Chemical and Metallurgical Division, GTE Products Corporation of Towanda, Pennsylvania. The ceramic cross-flow recuperator unit recovers waste heat from the hot combustion gases and delivers preheated air to high-temperature burners of various manufacture. Of the 38 host site installations included in the program, sufficient operating data were obtained from 28 sites to evaluate the benefits in terms of energy and economic savings that can be achieved. Performance and cost data are analyzed and presented for those 28 installations, which covered a variety of applications, sizes, and industry types. Except for 5 sites where unusual operating or data-collection problems were encountered, the improvements in performance of the recuperated furnaces equalled or exceeded estimates; the average of the total fuel savings for these 23 sites was 44.0 percent, some portion of which resulted from furnace improvements other than recuperation. Payback times were calculated for both total costs and for recuperator-related costs, using a cumulative annual after-tax cash …

Toroidal and poloidal rotation has been measured in the Poloidal Divertor Experiment (PDX) tokamak in ohmic- and neutral-beam-heated plasmas in a variety of discharge conditions and in both circular and diverted configurations. Rotation velocities were deduced from Doppler shifts of magnetic dipole (M1) lines and lines of optically allowed transitions in the visible and uv regions, from K/sub ..cap alpha../ emission, and also from an array of magnetic pickup loops. Poloidal and toroidal rotation velocities in ohmically heated discharges were unusually less than 3 x 10/sup 5/ cm/sec. Near the plasma edge the toroidal-rotation velocity varies with poloidal angle both before and during neutral-beam injection. No systematic poloidal rotation was observed during neutral-beam injection centered about or displaced 10 cm from the horizontal midplane, which implies that the poloidal damping time tau/sub theta/ < 0.5 tau/sub ii/, consistent with theoretical estimates.

The major objective of this report is to help the US Nuclear Regulatory Commission (NRC) in its regulatory mission, particularly with respect to improving the use of cost-benefit analysis and the economic evaluation of resources within the NRC. The objectives of this effort are: (1) to identify current and future NRC requirements (e.g., licensing) for valuing nonmarket goods; (2) to identify, highlight, and present the relevant efforts of selected federal agencies, some with over two decades of experience in valuing nonmarket goods, in this area; and (3) to review methods for valuing nonmarket impacts and to provide estimats of their magnitudes. Recently proposed legislation may result in a requirement for not only more sophisticated valuation analyses, but more extensive applications of these techniques to issues of concern to the NRC. This paper is intended to provide the NRC with information to more efficiently meet such requirements.

The FASTBUS Segment Driver, hereafter referred to as the FSD, is a list-driven, microcoded interface between the UNIBUS of a PDP-11 system and the FASTBUS. The list structure used by the FSD allows the programmer on the PDP-11 to program a sequence of data transfers to take place without the aid or intervention of the PDP-11. This allows the FASTBUS to be driven at FSD rates, independent of the PDP-11 processor. Due to the difference in speed between the FASTBUS and UNIBUS, the major goal of the FSD was to provide an interface which could transfer data on FASTBUS without significantly reducing the bandwidth in a multi-master system. This was accomplished by bursting data on the FASTBUS through a 256 word fast buffer internal to the FSD. Data can be transferred at near FASTBUS rates through this memory and only moved on the UNIBUS when the FSD is not master of FASTBUS. This allows other masters in the same system to transfer their data while the FSD is moving data on the slower UNIBUS.

A series of thermal-hydraulic and cladding materials deformation experiments were conducted using light-water reactor fuel bundles as part of the Pacific Northwest Laboratory Loss-of-Coolant Accident (LOCA) Simulation Program. This report is the formal operations plan for TH-2--the second experiment in the series of thermal-hydraulic tests conducted in the National Research Universal (NRU) reactor, Chalk River, Ontario, Canada. The major objective of TH-2 was to develop the experiment reflood control parameters and the procedures to be used in subsequent experiments in this program. In this experiment, the data acquisition and control system was used to control the fuel cladding temperature during a simulated LOCA by using variable reflood coolant flow.

Direct and indirect costs of decontamination are considered in the benefit-cost analysis. A generic form of the benefit-cost ratio is evaluated in monetary and nonmonetary terms, and values of dollar per man-rem are cited. Federal and state agencies that may have jurisiction over various aspects of decontamination and waste disposal activities are identified. Methods of decontamination, their general effectiveness, and the advantages and disadvantages of each are outlined. Dilute or concentrated chemical solutions are usually used in-situ to dissolve the contamination layer and a thin layer of the underlying substrate. Electrochemical techniques are generally limited to components but show high decontamination effectiveness with uniform corrosion. Mechanical agents are particularly appropriate for certain out-of-system surfaces and disassembled parts. These processes are catagorized and specific concerns are discussed. The treatment, storage, and disposal or discharge or discharge of liquid, gaseous, and solid wastes generated during the decontamination process are discussed. Radioactive and other hazardous chemical wastes are considered. The monitoring, treatment, and control of radioactive and nonradioactive effluents, from both routine operations and possible accidents, are discussed. Protecting the health and safety of personnel onsite during decontamination is of prime importance and should be considered in each facet of the decontamination process. …

Vertical poloidal asymmetries of hydrogen isotopes and low-Z impurity radiation in the PDX tokamak may be caused by poloidally asymmetric sources of these elements at gas inlet valves, limiters or vacuum vessel walls, asymmetric magnetic field geometry in the region beyond the plasma boundary, or by ion curvature drifts. Low ionization states of carbon (C II- C IV) are more easily influenced by edge conditions than is CV. Vertical poloidal asymmetries of CV are correlated with the direction of the toroidal field. The magnitude of the asymmetry agrees with the predictions of a quasifluid neoclassical model. Experimental data and numerical simulations are presented to investigate different models of impurity poloidal asymmetries.

The gamma-ray dose fraction from a moderated /sup 252/Cf source was determined by using three types of dosimetry systems. Measurements were carried out in air at a distance of 35 cm from the surface of the moderating sphere (50 cm from the source which is at the center of the sphere) to the geometrical center of each detector. The moderating sphere is 0.8-mm-thick stainless steel shell filled with D/sub 2/O and covered with 0.5 mm of cadmium. Measurements were also carried out with instruments and dosimeters positioned at the surface of a 40 cm x 40 cm x 15 cm plexiglass irradiation phantom whose front surface was also 35 cm from the surface of the moderating sphere. A-150 tissue-equivalent (TE) plastic ionization chambers and a TE proportional counter (TEPC) were used to measure tissue dose, from which the neutron dose equivalent was computed. The ratio of gamma-ray dose to the neutron dose equivalent was determined by using a relatively neutron-insensitive Geiger-Mueller (GM) counter and thermoluminescent dosimeters (TLD). In addition, the event-size spectrum measured by the TEPC was also used to compute the gamma-ray dose fraction. The average value for the ratio of gamma-ray dose to neutron dose equivalent was found …

Operations at the Hanford Site since 1944 have resulted in the discharge of large volumes of process cooling water and other waste waters to the ground. These effluents, which have reached the unconfined ground water, contain low levels of radioactive and chemical substances. The movement of these constituents in the unconfined ground water is monitored as part of the Ground-Water Surveillance Program. During 1982, 324 monitoring wells were sampled at various times for radioactive and chemical constituents. Tritium are the primary ones used to monitor the movement of the ground water. This report describes recent changes in the configuration of the tritium and nitrate plumes. The tritium plume continues to show increasing concentrations near the Columbia River. While it is mapped as having reached the Columbia River, its contribution to the river has not been distinguished from other sources at this time. The general plume configuration is much the same as in 1978, 1979, 1980, and 1981. The size of the nitrate plume appears stable. Concentrations of nitrate in the vicinity of the 100-H Area continue to be high as a result of past leaks from an evaporation facility.

Two principal underground energy storage technologies are discussed--Seasonal Thermal Energy Storage (STES) and Compressed Air Energy Storage (CAES). The Underground Energy Storage Program objectives, approach, structure, and milestones are described, and technical activities and progress in the STES and CAES areas are summarized. STES activities include aquifer thermal energy storage technology studies and STES technology assessment and development. CAES activities include reservoir stability studies and second-generation concepts studies. (LEW)

Lower hybrid waves at two different frequencies f/sub 1/ and f/sub 2/ are launched simultaneously from two localized antennas, and a third wave is observed to arise near the plasma edge at the frequency f = f/sub 2/ - f/sub 1/. This phenomenon can be explained by an echo effect near the plasma surface.

All chemical data for geothermal fluids in Nevada available as of December 1981 are maintained on GEOTHERM, a computerized information system. This report presents summaries and sources of records for Nevada. 7 refs. (ACR)

The reset of the self-correction current is performed by heating up a part of the self-correction coil and dumping the self-correction current to zero and then cool down again to make the superconducting state under the high multipole components free condition. If we perform the reset procedure of self-correction coil with higher multi-components not in free condition then these higher multi-components will be trapped by self-correction coils. From this point of view we must notice that after excitation of the main coil, even in the zero current in the mail coil, there exists a residual magnetic field due to the persistent current in the main coil superconducting wires. To get the higher multi-components free space in the coil, we insert a thin iron tube inside the main coil, outside the self-correction coil. At very low magnetic field, even if we use a thin soft iron tube, we will be able to get enough shielding effect. On the other hand, at very high magnetic field, the iron tube will saturate completely and its permeability ..mu.. decreases from about 4000 ..mu../sub 0/ to lower than 2 ..mu../sub 0/. This means the iron shielding tube becomes completely transparent against the magnetic flux at …

The DOE/NSF Nuclear Science Advisory Committee (NSAC) is preparing a new Long Range Plan for the development of nuclear science. This document, written as input to the Long Range Plan subcommittees; describes a number of ways that experiments with incident neutrons impact on outstanding problems in nuclear reactions and spectroscopy. It is argued that major extensions of present capabilities are required to carry out these experiments.

On June 8, 1983, a beam consisting of a single S-band bunch was transported through the linac into the beam switchyard (BSY) and analyzed in the C-line (Beamline 27) at 30 GeV. The C-line toroid 2712 measured an intensity of approximately 2 x 10/sup 9/e/sup -//pulse. The exact intensity was uncertain due to the limited response time of the toroid for fast, single-bunch beams. However, the linear Q intensity monitors (Lin Q) showed the transmission of the beam through the linac between Sectors 2 and 30 to be fairly flat with an intensity of 3 x 10/sup 9/e/sup -//pulse in the final 19 sectors. The CID Faraday cup, which is located adjacent to the Gun Lin Q, was used to check the calibration of the Lin Q.