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When burns are produced by a total radiant exposure of 5 cal/cm(sup 2), burn severity decreases with thermal pulses of longer duration. Maximum damage results from a pulse simulating that of a 20 KT weapon, the shortest pulse investigated; 40 KT and l00 KT weapon pulses show similar effects; and the 1000 KT pulse produces less damage. Burn severity is nearly the same from 10 cal/ cm(sup 2) whether the thermal pulse simulates 20 KT, 40 KT, 100 KT, or 1000 KT weapons. Less damage is caused by 10 cal/cm(sup 2) when it is delivered with a l0,000 KT simulated pulse. There is surprisingly little difference in the range of severity of burns from l5 cal/ cm(sup 2) when the thermal pulse simulates 100, 1000, and 10,000 KT weapons. Most of the burns from radiant exposures of 20 cal/ cm2 show complcte destruction of the full thickness of dermis. If there is a difference due to the type of thermal pulse, it is that the l00 KT pulse results in less dannage than does either the 1000 or l0,000 KT pulse. When the radiant exposure is sufficient to produce some dermal damage but not great enough to destroy the full …

A direct means of monitoring and indicating the neutron flux in a reactor core is required to maintain neutron-flux equilibrium and to eliminate hot spots, flux peaking and flux oscillations. This report presents operating specification for an in-core flux monitor. The specifications are based upon the recognized requirements and operating characteristics for Hanford reactors and are presents as the criteria for development, application, and evaluation of prototype in-core flux monitor systems.

A series of cutaneous burns was produced on swine by exploding 150 mgm of magnesium powder at distances of 20 and 25 cm from the animal. This provided 20 cal/cm/sup 2/ at exposure times of 0.7 and 2 to 3 sec and 16 cal/cm/sup 2/ at an exposure time of 0.7 sec respectively. The effect of placing green and khaki poplin fabrics untreated and treated with fire-retardant material L-S 123P, in contact with and separated 5 and 10 mm from skin was studied. Burns were evaluated both by surface appearance and by microscopic examination. All the fabrics reduced the severity of the burns. As the amount of separation increased, the severity of the burns decreased if the fabric remained intact. The knaki fabric with its higher reflectance gave more protection than the green fabric at 16 cal/cm/sup 2/ at 0.7 sec exposure time and 20 cal/cm/sup 2/ at 2 to 3 sec exposure time, but not at 20 cal/cm/sup 2/ at 0.7 sec exposure. The fire- retardant treated material gave more protection than the untreated material if it persisted longer during the exposure. If both persisted during the exposure but flaming or flaring occiirred, the untreated fabric gave more protection …

Discussions are given of the characteristics of fission-source plate, graphite reactor, and pool-type reactor facilities applicable to development studies of minimum weight shielding materials. Advantages of a proposed SNAP dual-purpose shielding facility are described in terms of a disk-shaped fission-source plate, reactor, and building. A program for the study of advanced shielding materials is discussed for materials and configuations to be evaluted with the fission-source plate, the testing of the prototype at high-power levels, and full-power tests on the actual reactor.

This document details activities of the Fuels Preparation Department during the month of July 1961. (FI)

This planning report is provided to describe the lead time, approximate costs, and major decisions and approvals required to enter a production program for the 500 watt SNAP 10A nuclear space power system.

This document details activities of the Fuels Preparation Department during the month of July 1962.

The objective of the production test detailed in this report is to authorize testing in the 1706-KE single-pass facility to measure the corrosion of aluminum-clad fuel elements in process water containing 0.20 ppm of Quachrom Glucosate added in place of dichromate and to compare this corrosion to corrosion in normal process water. Tubes SP-5 and SP-6 will be run with 0.20 ppm of Quachrom Glucosate and no dichromate; tests will be made at both pH 6.6 and 7.0. Simultaneous comparison corrosion measurements will be made in two regular tubes, 4561-KE and 4660-KE, supplied with normal process water. The use of SP-1 and SP-2 as additional control tubes is authorized, but not planned. Effluent-activity samples will be taken. Premature discharge and special pick-up are authorized.

The purpose of this report is to transmit revised goal exposure plans for normal production material. These plans supersede previous recommendations. Inherent in these plans are the assumptions: (1) The plant must produce a product containing six percent Pu-240, and (2) product blending capabilities are such that there are no restrictions, other than economic, on Pu-240 buildup at an individual reactor. Due to recent assessed changes in metal performance and conversion of DR Reactor to bumper natural material, revision of recommended goal exposure plans is called for. During the past year a significant shift in the relative metal performance between reactor types occurred. You may have observed the low rupture frequency at the C and K reactors compared to the rupture frequency at the old reactors. Based on the observed experience, goal exposures should be raised for C and K material and lowered for old reactor material. The goal exposure plans recommended herein are based on present, July 1962, assessed rupture performance and the latest conversion tables, incremental metal costs and burnout cost data. The current reactor optimization program was used to determine optimum goal exposures.

This report describes the use of a target containing polarized protons in a particle-scattering experiment. Positive pions of 246-MeV kinetic energy were scattered from the polarized protons. The parameter P that was measured is equivalent to that determined by analyzing the recoil-proton polarization in scattering from an unpolarized target. It has been measured to a higher accuracy than heretofore achieved in pion-proton scattering, at an energy and at angles inconvenient for double-scattering techniques.

This report details activities of the N-Reactor Department during the month of July 1963.

Large scale self-support fuel usage at the K Reactors began in mid-1963. With the advent of the new fuel element concept, self-support development work in different areas was required. One such area was that of the supports, or rails, used on the elements. The initial self-support rail design on the elements, in order to meet production commitments, was only slightly modified from previous test models. These rails were identified as ``bridge rails.`` Development of the self-supports has continued and the first major modification, the ``arch-rails,`` of the original design is now ready for reactor testing.

Brief summaries are presented on the following presentations: welding for low voltage operation, welding techniques at Mound, welding/joining at Sandia, Ultrasonic`s plastic assemblies of detonator components, laser welding bridge-wires, laser safety in the Biorad industrial environment, nondestructive testing at Mound, thermal cycle data and evaluation, thermal cycle nondestructive testing, corrosion of detonator electrode and bridge-wire, and corrosion studies and fabrication of bridge-wire at Sigmund Cohn.

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period. Data are given in table form. Information given includes: TISR number; request number; material; piece number; operating time; CMK absorbed; charge date; location; exposure to date; discharge, date and times; and shipping data.

An equilibrium theory of the length of intense electron bunches circulating in a storage ring is presented. The consequence of electrical interaction with various resonant structures is expressed in terms of quadratures over the impedance of the structures, and impedance functions for a variety of elements are evaluated. It is shown that elements having resonances at high frequency can, above transition, cause bunches to increase in length with increasing current. The parametric dependence of the bunch lengthening is found to be in good agreement with observations, and numerical estimates, which are in substantial agreement with experiment, are presented.

An air-operated semiautomatic wire former was designed and built at Mound Laboratory to form specific types of electrodes to be molded in plastic parts. Use of the semiautomatic wire former eliminates the sliding action of tooling on the surface of the electrode wire to be formed and properly aligns the crimped electrode surfaces to within required tolerance ranges. These are difficulties which are characteristic of conventional wire forming tooling. Interchangeable tooling is provided with the semiautomatic wire former for forming electrode wires in one plane; secondary tooling was designed and bulit for forming electrode wires in two planes; and a special series of tooling was designed for forming more complex wire forms.

A contract was awarded in June 1976 for the installation of a solar space heating and domestic hot water system at 2400 Watteroon Trail, Louisville, Kentucky. The overall philosophy used was to install both a liquid and a hot air system retrofitted to the existing office and combined warehouse building. The 1080 sq ft office space is heated first and excess heat is dumped into the warehouse. The two systems offered a unique opportunity to measure the performance and compare results of both air and liquid at one site. The two systems are described in detail and information on the data acquisition system is included.

This tour of Lawrence Livermore Laboratory's Standards and Calibrations Laboratory is intended as a guide to the capabilities of and services offered by this unique laboratory. Described are the Laboratory's ability to provide radiation fields and measurements for dosimeters, survey instruments, spectrometers, and sources and its available equipment and facilities. The tour also includes a survey of some Health Physics and interdepartmental programs supported by the Standards and Calibrations Laboratory and a listing of applicable publications.

The Johns Hopkins University Applied Physics Laboratory and the Center for Metropolitan Planning and Research support the Division of Geothermal Energy, U.S. Department of Energy, in the development of geothermal energy in the Eastern United States. In this role, many tools have been developed to assist in the analysis of the economics of the application of geothermal energy. This report documents one computer program that has proved useful.

The use of gamma-ray strength function systematics to calculate neutron capture cross sections and capture gamma-ray spectra is discussed. The ratio of the average capture width, GAMMA/sub ..gamma../-bar, to the average level spacing, D/sub obs/, both at the neutron separation energy, can be derived from such systematics with much less uncertainty than from separate systematics for values of GAMMA/sub ..gamma../-bar and D/sub obs/. In particular, the E1 gamma-ray strength function is defined in terms of the giant dipole resonance (GDR). The GDR line shape is modeled with the usual Lorentzian function and also with a new energy-dependent, Breit-Wigner (EDBW) function. This latter form is further parameterized in terms of two overlapping resonances, even for nuclei where photonuclear measurements do not resolve two peaks. In the mass ranges studied, such modeling is successful for all nuclei away from the N = 50 closed neutron shell. Near the N = 50 shell, a one-peak EDBW appears to be more appropriate. Examples of calculated neutron capture excitation functions and capture gamma-ray spectra using the EDBW form are given for target nuclei in the mass-90 region and also in the Ta-Au mass region. 20 figures.

A computer model of a piezoresistive gauge subject to shock loading is developed. The time-dependent two-dimensional response of the gauge is calculated. The stress and strain components of the gauge are determined assuming elastic-plastic material properties. The model is compared with experiment for four cases. An ytterbium foil gauge in a PPMA medum subjected to a 0.5 Gp plane shock wave, where the gauge is presented to the shock with its flat surface both parallel and perpendicular to the front. A similar comparison is made for a manganin foil subjected to a 2.7 Gp shock. The signals are compared also with a calibration equation derived with the gauge and medium properties accounted for but with the assumption that the gauge is in stress equilibrium with the shocked medium.

Two NbTi and two Cu wires were irradiated with 14.8 MeV neutrons at 4.2 K to fluences of 6 to 8 x 10/sup 20/ n/m/sup 2/, using RTNS-II. Electrical resistances of Cu were monitored during irradiation. Magnetoresistances were measured in fields up to 12.4 T before and after irradiation and after isochronal annealing up to 273 K. Critical currents of NbTi were measured after irradiation, in feilds up to 10 T. The initial rate of increase of resistivity of the Cu was found to be 2.23 x 10/sup -31/ (..cap omega..-m)/(n/m/sup 2/). This rate could be predicted from fission reactor irradiations using damage energy scaling. The maximum observed change in the NbTi critical was a decrease of 3% at 4 T. At 6, 8, and 10 T there were no significant changes.

The results of fully dynamic computer simulations of collision cascades show an abrupt decrease in defect production efficiency beginning at energies about 10 times the minimum threshold energy in agreement with experimental results on resistivity damage rates at 4.2 K. A detailed analysis of the time development of a typical cascade reveals that this drop in efficiency is primarily due to recombination by defect transport during the cascade cooling phase. This transport is an order of magnitude larger than that predicted from equilibrium transport theory.