The authors report here on latest results from an investigation of the form of the neutral current coupling in the inclusive channels {nu}{sub {mu}} + N {yields} {nu}{sub {mu}} + hadrons and {bar {nu}}{sub {mu}} + N {yields} {bar {nu}}{sub {mu}} + hadrons. The experiment was conducted by the Caltech-Fermilab group in October 1974. The data were taken in the Fermilab narrow band beam set to a mean secondary hadron energy of {+-} 170 GeV. The distributions of total energy, observed in the target calorimeter, for charged current events in which the muon momentum was measured, shown in figure 1, reflect the dichromatic structure of the beam, with average energies for neutrinos from pion and kaon decay of 50 and 150 GeV, respectively. The two main sources of background present in the data sample come from cosmic ray interactions. and from neutrinos (and anti-neutrinos) which are produced by decays before momentum and sign selection has occurred (wide-band background). Both backgrounds are measured and empirically subtracted from the data. The first (cosmic rays) is measured in an off-beam gate. The second (wide-band) is measured by closing a slit at the entrance to the decay pipe. Thus, the data sample contains beam …

The nondestructive assay of plutonium is important as a safeguard tool in accounting for stategic nuclear material. Several nondestructive assay techniques, e.g., calorimetry and spontaneous fission assay detectors, require a knowledge of plutonium and americium isotopic ratios to convert their raw data to total grams of plutonium. This paper describes a nondestructive technique for calculating plutonium-238, plutonium-240, plutonium-241 and americium-241 relative to plutonium-239 from measured peak areas in the high resolution gamma-ray spectra of solid plutonium samples. Gamma-ray attenuation effects have been minimized by selecting sets of neighboring peaks in the spectrum whose components are due to the different isotopes. Since the detector efficiencies are approximately the same for adjacent peaks, the accuracy of the isotopic ratios are dependent on the half-lives, branching intensities and measured peak areas. The data presented describes the results obtained by analyzing gamma-ray spectra in the energy region from 120 to 700 keV. The majority of the data analyzed was obtained from plutonium material containing 6% plutonium-240. Sample weights varied from 0.25 g to approximately 1.2 kg. The methods have also been applied to plutonium samples containing up to 23% plutonium-240 with weights of 0.25 to 200g. Results obtained by gamma-ray spectroscopy are compared to …

The use of ultrasonic methods in nondestructive testing depends on the interpretation of the scattering of sound waves by flaws. The theory of elastic waves and their scattering in non-uniform media is developed in detail from first principles, and in generality. Both integral equation and differential methods are discussed, with emphasis on the former. General methods for defining scattering cross sections are presented, and conservation theorems are noted. The Born Approximation to the integral equation is presented, and computed results for several experimental situations are discussed. Several corrections to papers in the literature are made, and in particular the exact scattering of a transverse wave by a spherical flaw is compared with the Rayleigh (long wave) limit.

A high temperature amplifier for use in geothermal well logging was developed. This development was based on the use of ceramic vacuum tubes as the active circuit element, since these tubes have the capability to operate in the high ambient temperature environment. The primary goal of this program was to design, build, and deliver a prototype amplifier capable of continuous operation in a 250/sup 0/C environment. A development program designed to meet this goal covered four phases. These phases were (1) development of the basic circuit configuration with conventional, low cost glass envelope vacuum tubes; (2) modification of the circuitry to accommodate the ceramic vacuum tubes; (3) a 1000-hour duration temperature cycle (48 hours at 260/sup 0/C and 2 hours at 20/sup 0/C); and (4) development of a prototype, deliverable amplifier. The following sections discuss the high temperature amplifier development program. Section 2 describes the amplifier performance, including design requirements, circuit design, development program, and the prototype amplifier. Section 3 presents test results from two breadboard models, one with conventional glass tubes and one with ceramic tubes, and the prototype amplifier. Section 4 describes the operation of the prototype amplifier. Circuit equations used for analysis and tube characteristics are contained …

An experimental program was conducted to determine the operating characteristics of full length (65 feet) single and multi-tube once-through steam generator test sections subjected to radiant heat flux levels commensurate with commercial solar tower receiver application. Absorbed heat flux levels ranging from 0.15 to 0.71 Btu/in./sup 2/-sec (0.25 to 1.16 MW/m/sup 2/) were achieved in a horizontal facility utilizing graphite radiant heater arrays. Steam exit temperatures ranged from 625 F (two-phase) to 1380 F at pressures of 1000 to 2300 psia. Wall temperature profiles and fluid pressure losses were obtained and compared with an existing computer model.

Perhaps the most important design consideration is the heat generated by the spent fuel assemblies or the high-level waste being placed in the repository. The sensitivity of repository design to this heat is reflected by the definition of temperature and thermochemical criteria. To assure environmental and occupational safety, limits may be placed on such parameters as spent fuel or waste temperature, canister temperature, rock temperature, strength-to-stress ratio of the excavated openings, surface uplift or subsidence, temperature increase in an aquifer, and temperature increase at or near the surface of the earth. Appropriate criteria are chosen to accomplish ready retrievability, to retard canister corrosion, to suppress the rate of nuclide leaching, to control the buoyant forces that drive potential nuclide migration, to assure mine safety, to assure formation stability, and to control the thermal and thermomechanical impact on the environment. Other major concerns in the location and design of a waste repository are the presence and effect of groundwater within the repository host rock and the surrounding strata. Additional groundwater considerations include its effect on canister integrity, its potential as a source of hydrogen, and its effect on the repository operational environment. Two types of retrieval are considered: operational verification and …

This report presents a physical description of a reference deep-geologic repository located in a granite host rock at a depth of about 1500 meters. Two reference repository designs are described in this report. One is designed to accept wastes from a lightwater reactor (LWR) strategy in which no reprocessing occurs, and the spent fuel itself is considered a waste form. The second is designed to accept wastes from an LWR strategy with reprocessing in which uranium and plutonium are recycled.

None

None

None

The behavior of dielectric droplets and gas bubbles in electrostatic levitation, positioning, and control devices for laser-fusion target applications is studied. Because of the exacting tolerance requirements for the sphericity of laser fusion targets, there is concern over the electric field induced elongation effect which may exist in some or all of these schemes. These proposed tolerances suggest upper limits on the axis ratio ..gamma..: ..gamma.. - 1 < 10/sup -3/, which may severely limit the maximum allowable electric field in certain electrostatic levitation schemes. Calculations of the deformation of bubbles in cryogenic hydrogen were undertaken by Bliss, but only for large deformations up to ..gamma.. approximately 2. These calculations are extended down to very small deformations, that is: 10/sup -4/ < ..gamma.. - 1 < 10/sup -1/, for droplets of cryogenic liquid hydrogen (n - H/sub 2/) and bubbles in liquid hydrogen at its triple point. Also, the effect of pressure on the deformation has been explored. Further, approximate explicit analytic expressions for ..gamma..(E) have been obtained for the limit of small deformations.

The feasibility of photochemically fractionating the actinides in nuclear waste processing has been evaluated on a preliminary basis. The data indicate that there are potentially useful photo-redox reactions. However, there is a serious lack of data on photochemical parameters for the solutions conditions which exist in nuclear waste processing. The problem areas relevant to photochemical processing are identified. The experimental areas which must be investigated in order to further evaluate the photochemistry are defined. A research and development program is required to determine whether these photochemical reactions can be successfully modified and adapted into a functional actinide fractionating process.

Experimental research on emergency direct in-vessel air cleaning systems for the LMFBR is described. Results which characterize the aerosol from 1 lb sodium pool fires made in a 90 m/sup 3/ chamber are presented. The effective use of turbulent agglomeration to enhance aerosol sedimentation is described. The composition of the aerosol as determined by atomic absorption and chemical tests is discussed. Results from small scale sodium aerosol scavenging tests are presented, anticipating large-scale powder dispersal tests to be conducted in the chamber. Plans for testing the sonic agglomeration characteristics of sodium aerosols are discussed.

Twelve papers are included, and separate abstracts were prepared for nine; all were selected for ERDA Energy Research Abstracts (ERA) and one for Energy Abstracts for Policy Analysis (EAPA). The others appeared previously as: ERA 1: 8408, ERA 1: 8402, and ERA 1: 8409. (MHR)

A description and interpretation of the atomic spectrum of neptunium are given. Wavelengths were measured for 6096 spectrum lines in the range 3793 to 38,812 cm/sup -1/ (26,353 to 2575 A), of which 2526 were classified as transitions between 329 odd levels and 130 even levels of neutral neptunium (Np I). The data are presented in five tables.

The purpose of this study was to investigate the movement and hydrologic stability of the domes, to identify the domes which appear suitable for further study and consideration, and to outline the additional information needed to evaluate these domes. The growth of the interior salt domes appears to have slowed with geologic time and to have halted altogether. The Bullard, Whitehouse, and Keechi domes probably are not subject to significant dissolution at the present time. However, caprock found at Bullard and Whitehouse indicates that salt dissolution occurred at some period during the past 50 million years since Wilcox was deposited. It is recommended that shallow water wells be drilled and tested. (DLC)

A light, rugged monitor has been developed for special nuclear materials (SNM) searches at material-access and protection-area exits. This monitor accepts gamma-ray pulses from a NaI(Tl) detector, integrates for a preset counting interval (typically 0.3 s), and produces an audible alarm whenever the counts in the interval exceed the trip level that is a preset multiple of the stored background count. Because the monitor is silent except when the alarm is operating, personnel with little special training can conduct more effective searches in a noisy and distracting environment than they can with conventional audible monitoring of individual radiation counts. The monitor is also more sensitive than conventional monitors that provide audible indication of the count rate.

An equilibrium analysis has been made of the fission-product cesium in the primary coolant loop of the high-temperature gas-cooled reactor (HTGR). The species distributions that result at equilibrium have been calculated for various conditions of reactor operation. The cesium species considered were the monomer, dimer, oxides, hydroxides, and the hydride. The effect of cesium sorption isotherms on graphite also was included in the analysis. During normal reactor operations, the abundant species of cesium were calculated to be elemental cesium, Cs, and the monomeric hydroxide, CsOH. Under most conditions of steam ingress, the abundant species was calculated to be CsOH. Cesium adsorbed onto graphite was stable under all steam-ingress conditions considered. Thermal transients above 1500/sup 0/K were required for equilibrium transport of cesium from the core to the coolant. The analysis was carried out using the complex equilibrium code QUIL, designed and written with special emphasis on features that make it applicable to the fission-product problem.

The construction of an Intersecting Storage Accelerator Facility (ISA or ISABELLE) at Brookhaven National Laboratory is proposed. ISABELLE will permit the exploration of proton-proton collisions at center-of-mass energies continuously variable from 60 to 400 GeV and with luminosities of 10/sup 32/ to 10/sup 33/ cm/sup -2/ sec/sup -1/ over the entire range. An overview of the physics potential of this machine is given, covering the production of charged and neutral intermediate vector bosons, the hadron production at high transverse momentum, searches for new, massive particles, and the energy dependence of the strong interactions. The facility consists of two interlaced rings of superconducting magnets in a common tunnel about 3 km in circumference. The proton beams will collide at eight intersection regions where particle detectors will be arranged for studying the collision processes. Protons of approximately 30 GeV from the AGS will be accumulated to obtain the design current of 10A prior to acceleration to final energy. The design and performance of existing full-size superconducting dipoles and quadrupoles is described. The conceptual design of the accelerator systems and the conventional structures and buildings is presented. A preliminary cost estimate and construction schedule are given. Possible future options such as proton-antiproton, proton-deuteron …

Begun in 1970, the Amchitka Radiobiological Program is a continuing program to collect biological and environmental samples for radiometric analyses. This report is an account of the program for Calendar Year 1975. Results of analyses for samples collected in August 1975 have been added to the tables that summarize the results of analyses of samples collected from 1970 to 1975 and include analyses for gamma-emitting radionuclides in air filters, freshwater, birds, lichens, marine algae, marine invertebrates, fish, aufwuchs, and freshwater moss and plants; strontium-90 (/sup 90/Sr) in rats, birds, and soil; /sup 239/ /sup 240/Pu in sand, soil, marine algae and fish; and tritium (/sup 3/H) in seawater, freshwater, and biological organisms. Monitoring of background radiation with survey instruments was added to the Laboratory's program in 1974 and the results of the 1974 and 1975 surveys are included in this report. It is concluded from the results of analyses of samples collected between September 1969 and August 1975 as reported in this and the five previous progress reports, that there were no radionuclides of Milrow or Cannikin origin in the water, plants, or animals of Amchitka Island.

Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T.

Highly accurate finite difference schemes are developed for Laplace&#x27;s equation with the Dirichlet boundary condition on general bounded regions in R/sup n/. A second order accurate scheme is combined with a deferred correction or Richardson extrapolation method to increase the accuracy. The Dirichlet condition is approximated by a method suggested by Heinz-Otto Kreiss. A convergence proof of his, previously not published, is given which shows that, for the interval size h, one of the methods has an accuracy of at least O(h/sup 5/./sup 5/) in L/sub 2/. The linear systems of algebraic equations are solved by a capacitance matrix method. The results of our numerical experiments show that highly accurate solutions are obtained with only a slight additional use of computer time when compared to the results obtained by second order accurate methods.

The stability of dissipative trapped-particle modes in the presence of a self-consistent lower-hybrid pump is analyzed theoretically. The pump can either be a single coherent wave or a spectrum of turbulent waves. Corresponding dispersion relations modified by the pump are derived and conditions for excitation and suppression of the modes are also discussed.

The report is a synoptic review of data collected over the past twenty years on the chemistry of Lake Michigan. Changes in water quality and sediment chemistry, attributable to cultural and natural influences, are considered in relation to interacting processes and factors controlling the distribution and concentration of chemical substances within the Lake. Temperature, light, and mixing processes are among the important natural influences that affect nutrient cycling, dispersal of pollutants, and fate of materials entering the Lake. Characterization of inshore-offshore and longitudinal differences in chemical concentrations and sediment chemistry for the main body of the Lake is supplemented by discussion of specific areas such as Green Bay and Grand Traverse Bay. Residues, specific conductance, dissolved oxygen, major and trace nutrients, and contaminants are described in the following context: biological essentiality and/or toxicity, sources to the Lake, concentrations in the water column and sediments, chemical forms, seasonal variations and variation with depth. A summary of existing water quality standards, statutes, and criteria applicable to Lake Michigan is appended.