This document contains visual aids used in an invited talk entitled Modern Solid State Laser Materials, presented at the Conference on Lasers and Electro-Optics (CLEO) held in Anaheim, California, on June 20, 1984. Interest at LLNL in solid state lasers focuses on evaluating the potential of solid state laser media for high average power applications, including inertial fusion power production. This talk identifies the relevant bulk material parameters characterizing average power capacity and uses chromium and neodymium co-doped gadolinium scandium gallium garnet (Nd:Cr:GSGG) as an example of a laser material with improved laser properties relative to Nd:YAG (plausible large-scale growth, more efficient spectral coupling to xenon flashlamp radiation, reduced stimulated emission cross section, adequate thermal shock and optical damage threshold parameters, etc.). Recently measured spectroscopic, kinetic, and thermo-mechanical properties of Nd:Cr:GSGG are given.

We calculate analytically the expected tune shifts due to systematic sextupole and decapole errors in the SSC dipoles of reference design A at an energy of 20 TeV. The momentum-dependent tune shift due to sextupole error is d nu/sub x/ = -0.0557 for ..delta..p/p = +-2 x 10/sup -5/. The random sextupole component in the SSC dipoles ..delta..b/sub 2/ should be less than 5 x 10/sup -4/.

This report incorporates all lectures and presentations at the International Training Course on Implementation of State Systems of Accounting for and Control of Nuclear Materials held October 17 through November 4, 1983, at Santa Fe and Los Alamos, New Mexico and Richland, Washington, USA. Authorized by the US Nuclear Non-Proliferation Act and sponsored by the US Department of Energy in cooperation with the International Atomic Energy Agency, the course was developed to provide practical training in the design, implementation, and operation of a State system of nuclear materials accountability and control that satisfies both national and international safeguards requirements. Major emphasis for the 1983 course was placed on safeguards methods used at bulk-handling facilities, particularly low-enriched uranium conversion and fuel fabrication plants. The course was conducted by the University of California's Los Alamos National Laboratory and Exxon Nuclear Company, Inc. Tours and demonstrations were arranged at the Los Alamos National Laboratory, Los Alamos, New Mexico, and the Exxon Nuclear fuel fabrication plant, the Battelle Pacific Northwest Laboratory, Westinghouse Fast Flux Test Facility Visitor Center, and Washington Public Power System nuclear reactor facilities in Richland, Washington. Individual presentations were indexed for inclusion in the Energy Data Base.

The Advanced Test Accelerator (ATA) is a linear induction electron accelerator whose design parameters are 50 MeV, 10 kA and 70 ns pulse duration. The key physics issues affecting performance of the accelerator involve beam dynamics during transport through the accelerator structure. In this report, we present experimental results describing the initial operating phases of ATA. These results illustrate the complexity of the beam transport phenomena but also indicate the means to stabilize beam dynamics. Improvements in beam transport, which result from deploying various stabilization techniques, are also presented.

A review is given of E/sub T//sup 0/ and neutral pion spectra from various interactions. Inclusive single particle production at large transverse momentum from heavy nuclear targets at Fermilab and at ISR are briefly discussed, followed by some results of measurement of transverse energy emission in the central region of pA collisions. An experiment at ISR is described in which the total neutral energy emitted in the central region was measured using an electromagnetic shower counter which detected the photons from the decays of neutral pions and neutral etas. The apparatus is described and selection criteria are given. Resulting energy spectra are given. Multiplicity distributions were related using the Wounded Nucleon Model. (LEW)

Progress in the following studies on radioactive waste management is reported: defense waste technology; Nuclear Waste Materials Characterization Center; waste isolation; and supporting studies. 58 figures, 22 tables.

This study was designed to observe the feasibility of the use by NRC licensees of the tissue equivalent proportional counter (TEPC) system as a neutron monitoring instrument. Laboratory tissue equivalent proportional counters were irradiated using /sup 252/Cf sources at NBS and PNL and were irradiated inside containment of four operating nuclear power plants (two boiling water reactors and two pressurized water reactors). On the average, neutron dose-equivalent rates determined using the TEPC were 1.05 times the calculated dose-equivalent rates for the bare and moderated /sup 252/Cf sources and 0.86 times the dose-equivalent rates determined using the multispheres inside containment of nuclear power plants. Further, neutron dose equivalent rates determined using portable remmeters were an average of 1.71 times the dose equivalent determined using the multispheres inside the containment of nuclear power plants. It was observed that while electronic noise from temperature and vibrational effects inside containment prohibited an adequate measure of absorbed dose from gammas, the measurement of neutron absorbed dose was unaffected by these environmental parameters. It is recommended that for use inside containment at nuclear power plants: (1) the laboratory scale TEPC is the superior technique for accurate determination of neutron dose equivalent, (2) for remmeters similar to …

Construction of the experiment cavern on the 27th level of the SOUDAN iron mine in northern Minnesota began early this year and will be complete early in 1985. The first 1200 tons of the detector itself is also under construction in the US and UK; installation will begin in mid 1985. Physics exploitation will begin early in 1986 and the first 1200 ton module will be complete early in 1987. The detector may be expanded to between 3 and 5 such modules in the cavern. The detector is an iron tracking calorimeter (rho = 2) consisting of stacks of corrugated steel sheets each 1.2 mm thick. The corrugations form hexagonal channels 1 m long and 16 mm in diameter. A uniform electric field along these channels is provided by the voltage grading arising from the constant standing current in the Hytrel tubes (rho = 2 x 10/sup 12/ ..cap omega.. cm) that line each channel. The tubes are insulated from the steel by sheets of mylar. Ionization in the gas in the tubes drifts in the uniform field to the end of the tube where it is amplified linearly and detected by a matrix of anode wires and cathode strips. …

The purpose of this Public Participation Plan is to describe the Department of Energy's plan for involving the public in the decision-making process required by the National Environmental Policy Act (NEPA) of 1969 as related to the Uranium Mill Tailings Remedial Action (UMTRA) Project. This project was authorized by congress in the Uranium Mill Tailings Radiation Control Act of 1978, PL95-604. The Act provides for a cooperative effort with affected states and Indian tribes for the cleanup of designated inactive uranium mill tailings sites and associated vicinity properties, which are located in ten western states and in Pennsylvania. The Act was amended in 1982 to also include vicinity properties contaminated with residual radioactive material in Edgemont, South Dakota.

The Public Information Plan is intended to be used in conjunction with the DOE-UMTRA Project Public Participation Plan'' to describe the Department of Energy's plan for involving the public in the decision-making process related to the Uranium Mill Tailings Remedial Action (UMTRA) Project. This project was authorized by Congress in the Uranium Mill Tailings Radiation Control of Act of 1978, PL95-604. The Act provides for a cooperative effort with affected states and Indian tribes for the cleanup of designated abandoned or inactive uranium mill tailings sites. The objective of the Public Information Plan of the UMTRA Project is timely and sufficient dissemination of factual information to promote understanding of the project by federal, state, and local officials, the media, special interest groups, and the general public; and thereby to encourage informed participation in the project by the public and government officials. The Uranium Mill Tailings Radiation Control Act provides for public involvement in remedial action planning, with special consideration given to landowners, Indian tribes, and the states. According to the Act, the Secretary of Energy shall hold public hearings in the states where processing sites, vicinity properties, and disposal sites are located. Public participation in the UMTRA Project will not, …

A workshop was conducted to discuss problem areas associated with developing carcinogen guidelines. Session topics included (1) definition of a carcinogen for regulatory purposes; (2) potency; (3) risk assessment; (4) uncertainties; (5) de minimis quantity; and (6) legal and regulatory issues. Separate abstracts have been prepared for individual papers. (ACR)

The viscous flow of fluids and the plastic flow of solids, such as metals, are interesting from both the practical and the theoretical points of view. Atomistic molecular dynamics simulations provide a way of visualizing and understanding these flows in a detailed microscopic way. Simulations are necessarily carried out at relatively high rates of strain. For this reason they are ideally suited to the study of nonlinear flow phenomena: normal stresses induced by shear deformation, stress rotation, and the coupling of stress with heat flow, for instance. The simulations require appropriate boundary conditions, forces, and equations of motion. Newtonian mechanics is relatively inefficient for this simulation task. A modification, Nonequilibrium Molecular Dynamics, has been developed to simulate nonequilibrium flows. By now, many high-strain-rate rheological studies of flowing (viscous) fluids and (plastic) solids have been carried out. Here I describe the new methods used in the simulations and some results obtained in this way. A three-body shear-flow exercise is appended to make these ideas more concrete.

The objective of these studies is to evaluate the technical and economic feasibility of producing specific gas products by catalytic gasification of biomass. Catalyst performance is a key factor in the feasibility of catalytic gasification processes. The results of studies designed to gain a fundamental understanding of catalytic mechanisms and causes of deactivation, and discussion of the state-of-the-art of related catalytic processes are presented. Experiments with primary and secondary catalysts were conducted in a 5-cm-diameter, continuous-wood-feed, fixed-catalyst-bed reactor. The primary catalysts used in the experiments were alkali carbonates mixed with the biomass feed; the secondary catalysts included nickel or other transition metals on supports such as alumina, silica, or silica-alumina. The primary catalysts were found to influence wood pyrolysis as well as the char/steam reaction. Secondary catalysts were used in a fixed-bed configuration to direct gas phase reactions. Results of the performance of these catalysts are presented. Secondary catalysts were found to be highly effective for conversion of biomass to specific gas products: synthesis gases and methane-rich gas. With an active catalyst, equilibrium gas composition are obtained, and all liquid pyrolysis products are converted to gases. The major cause of catalyst deactivation was carbon deposition, or coking. Loss of surface …

The radiation-measurement team of the Weapons Engineering Division at Lawrence Livermore National Laboratory (LLNL) measured neutron and gamma dose and spectra on the Little Boy replica at Los Alamos National Laboratory (LANL) in April 1983. This assembly is a replica of the gun-type atomic bomb exploded over Hiroshima in 1945. These measurements support the National Academy of Sciences Program to reassess the radiation doses due to atomic bomb explosions in Japan. Specifically, the following types of information were important: neutron spectra as a function of geometry, gamma to neutron dose ratios out to 1.5 km, and neutron attenuation in the atmosphere. We measured neutron and gamma dose/fission from close-in to a kilometer out, and neutron and gamma spectra at 90 and 30/sup 0/ close-in. This paper describes these measurements and the results. 12 references, 13 figures, 5 tables.

The present backlog of irradiated reactor fuel leads to projections that no fuel out of the reactor less than 10 years need be reprocessed prior to the year 2000. The only radioiodine present in such aged fuel is /sup 129/I (half-life 1.6 x 10/sup 7/ y). The /sup 131/I initially present in the fuel decays to insignificance in the first few hundred days post-reactor. The /sup 129/I content of irradiated fuel is about 1 Ci per gigawatt-year of electricity generated (Ci/GW(e)-y). The US EPA has specified, in 40 CFR 190, a release limit for /sup 129/I of 5 mCi/GW(e)-y. Thus a retention factor (RF) of 200 for /sup 129/I at the fuel reprocessing plant (FRP) is required. Experience indicates that RF values obtained under actual FRP operating conditions can average as little as 10% of experimentally determined RF values. Therefore processes theoretically capable of achieving RF values of up to 10/sup 4/ have been investigated. The US EPA has also specified in 40 CFR 90 a thyroid dose limit of 75 mrem/y for a member of the general public. This dose limit could be readily met at a typical FRP site with an RF value of about 10 or less. …

The dissolution of plutonium dioxide in nitirc acid (HNO/sub 3/) at high hydrofluoric acid (HF) concentrations has been investigated. Dissolution rate curves were obtained using 12M HNO/sub 3/ and HF at concentrations varying from 0.05 to 1.0 molar. The dissolution rate increased with HF concentration up to 0.2M and then decreased at higher concentrations. There was very little plutonium dissolved at 0.7 and 1.0M HF because of the formation of insoluble PuF/sub 4/. Various oxidizing agents were added to 12M HNO/sub 3/-1M HF dissolvent to oxidize Pu(IV) to Pu(VI) and prevent the formation of PuF/sub 4/. Ceric (Ce(IV)) and silver (Ag(II)) ions were the most effective in dissolving PuO/sub 2/. Although these two oxidants greatly increased the dissolution rate, the rates were not as rapid as those obtained with 12M HNO/sub 3/-0.2M HF.

Experiments were performed on the PDX tokamak to study plasma heating and ..beta.. scaling with higher power, near-perpendicular neutral beam injection. The data taken during these experiments were analyzed using a time-dependent data interpretation code (TRANSP) to study the transport and thermal confinement scaling over a wide range of plasma parameters. This study focuses on results from experiments with D/sup 0/ injection into H/sup +/ plasmas using graphite rail limiters, a = 40 to 44 cm, R = 143 cm, I/sub p/ = 200 to 480 kA, B/sub T/ = 0.7 to 2.2 T, and typically anti n/sub e/ = 2.5 to 4.2 x 10/sup 13/ cm/sup -3/. The results of this study indicate that for both ohmic and neutral beam heated discharges the energy flow out of the plasma is dominated by anomalous electron losses, attributed to electron thermal conduction. The ion conduction losses are well described to electron thermal conduction. The ion conduction losses are well described by neoclassical theory; however, the total ion loss influences the power balance significantly only at high toroidal fields and high plasma currents.

Mathematical models and numerical methods for a two-dimensional porous body simulation of steady state and transient thermal-hydraulics conditions in LMFBR subassemblies resulting in the TWIST computer code are presented. Comparison of calculated results to steady state and transient out-of-pile sodium experiments show good agreement for cross-assembly temperature distributions for a wide range of heat transfer and flow conditions.

This report covers work done during FY 1983 by the staff of the Energy Division and its subcontractors and by colleagues in other Oak Ridge National Laboratory divisions working on Energy Division projects. The work can be divided into four areas: (1) analysis and assessment, (2) models and data systems, (3) research to improve the efficiency of energy use and to improve electric power transmission and distribution, and (4) research utilization. Support came principally from the US Department of Energy (DOE), the US Nuclear Regulatory Commission, and the US Department of Defense, but also from a number of other agencies and organizations. Analysis and assessment included work on (a) environmental issues, including those deriving from the preparation of environmental impact statements; (b) energy and resource analysis; and (c) emergency preparedness. The models and data systems area involved research on evaluating and developing energy, environment, and engineering simulation models and on devising large data management systems, evaluating user data requirements, and compiling data bases. Research on improving the efficiency of energy use was focused primarily on the buildings and electricity sectors. A major effort on heat pump technology, which includes both heat-activated and electrically driven systems, continues. An important aspect of …

This report documents a review, performed by the Pacific Northwest Laboratory (PNL), of the Transamerica Delaval, Inc. (TDI) Diesel Generator Owner's Group Program Plan. This report was prepared as part of the technical support PNL is providing to the US Nuclear Regulatory Commission (NRC), Division of Licensing, on matters pertaining to the reliability of TDI diesel generators as emergency power sources for safety-related nuclear systems. The report presents the comments and conclusions reached by PNL, with the advice and counsel of five diesel engine consultants, on the principal elements of the Owners' Group Plan: Generic Problem Resolution, Design Review/Quality Revalidation, and Engine Testing and Inspection. Also included are PNL's comments on the related issues of Surveillance and Maintenance, and Administrative Controls. The conclusions drawn from PNL's evaluation of these issues form the basis for two additional topics addressed in the report: Critical Elements Required to Establish Diesel Engine Operability and Reliability, and Considerations for Interim Licensing.

The ATA provides an electron beam pulse of 70-ns duration at a 1-Hz rate. Our present optical diagnostics technique involve the imaging of the visible light generated by the beam incident onto the plant of a thin sheet of material. It has already been demonstrated that the light generated has a sufficiently fast temporal reponse in performing beam diagnostics. Notwithstanding possible beam emittance degradation due to scattering in the thin sheet, the observation of beam spatial profiles with relatively high efficiencies has provided data complementary to that obtained from beam wall current monitors and from various x-ray probes and other electrical probes. The optical image sensor consists of a gated, intensified television system. The gate pulse of the image intensifier can be appropriately delayed to give frames that are time-positioned from the head to the tail of the beam with a minimum gate time of 5-ns. The spatial correlation of the time frames from pulse to pulse is very good for a stable electron beam; however, when instabilities do occur, it is difficult to properly assess the spatial composition of the head and the tail of the beam on a pulse-to-pulse basis. Multiple gating within a pulse duration becomes desirable …

The goal of this project is to optimize the reaction conditions for upgrading coal liquids. Our results for this quarter are summarized: Last quarter we found that H/sub 2/S aids in the HDN process. During this quarter, we have undertaken an H/sub 2/S concentration study on this reaction and found a direct correlation between the amount of added H/sub 2/S and the reduction in nitrogen content. For comparison, we also used H/sub 2/O and Na/sub 2/S as additives; however, neither appears to be as effective as H/sub 2/S in the HDN process. We initiated syntheses of some organometallic molybdenum cluster complexes (Mo/sub 2/(OAc)/sub 4/ and cluster complexes Mo/sub 2/(allyl)/sub 4/) and have reacted these complexes with an alumina support. Preliminary tests reveal that these complexes have, as expected, less hydrogenation activity than the activated CoMo catalyst. However, we have not yet tested them for HDN activities. We began experiments on the addition of added Bronsted acids (C/sub 3/FCOOH) to the reaction system. So far, the results have been promising and indicate a direct correlation between the amount of added acid and the amount of HDN activity. 3 references, 1 figure, 2 tables.

This first quarterly report documents technical progress during the period 31 December 1983 through 30 March 1984. The technical effort is 17 months in duration and is divided into two major technical tasks: Task VII, Hardware Fabrication and PDU Modifications, and Task VIII, Performance Testing. The design of test hardware and process development unit modifications had been previously completed as part of Task VI of the current contract. Task VII involves the fabrication of test hardware and modification of an existing 1-ton/h hydroliquefaction PDU at Rockwell's facilities for use as a hydrogasifier test facility. During this report period, fabrication of the test hardware and modifications to the PDU were initiated. Test hardware fabrication is now approximately 80% complete and should be completed by the end of May 1984. PDU modifications are progressing well and should be completed by the end of June 1984. The completed test hardware fabrication and PDU modifications will allow the conduct of short duration (1 to 2 h) hydrogasification tests along with preburner assembly performance evaluation tests in order to fulfill the test program objectives. Separate supplies of hydrogen, oxygen, methane, carbon monoxide, and water (for steam generation) are provided for this purpose. The modified facility …

This report describes calculations and analysis performed in an attempt to provide a new estimate for the yield of the Hiroshima weapon. Newly discovered meteorological data was adapted for use in one- and two-dimensional hydrodynamic codes, and a series of calculations was then run for different values of yield. The objective was to determine what yield produced an overpressure record which could best be correlated with an actual trace measured at a parachute-dropped canister. Altitude of the bomb and canister-carrying aircraft at drop time was also a variable parameter. The analysis provides an estimate of 16.6 + 0.3 kt for the yield of the Hiroshima weapon. A drop altitude of near 35,500 feet is shown to be consistent with the signal time-of-arrival. This yield value is within the range of other estimates, but the drop altitude is higher than that previously assumed to be reasonable.