States

A Time-Shared Computer Data Collection System at the Brookhaven Graphite Research Reactor (open access)

A Time-Shared Computer Data Collection System at the Brookhaven Graphite Research Reactor

The increasing complexity of the data of nuclear physics has led to widespread interest in the possibility of utilizing a digital computer for on-line data collection. Through the combined efforts of the Instrumentation Division and the Neutron Physics group at Brookhaven such a system has been placed into operation. Several features of this system are believed to be unique and of interest to research groups centered about a major facility like a reactor or an accelerator.
Date: November 19, 1963
Creator: Chrien, R. E.; Rankowitz, S. & Spinrad, R. J.
Object Type: Report
System: The UNT Digital Library
Lens Opacification in Mice Exposed to Monoenergetic Fast Neutrons (open access)

Lens Opacification in Mice Exposed to Monoenergetic Fast Neutrons

Early effects obtained with monoenergetic fast neutrons in mice have been described elsewhere. Emphasis in this report will be placed on the late effects of lens opacification (cataractogenesis), particularly during the period soon after irradiation with low or fractionated doses of neutrons at two energy levels, or X-rays. Considerations will also be given to the influence of age at time of irradiation upon the induction of lens opacities. Both studies are continuing, with periodic slit-lamp microscope examinations, but findings to date warrant this initial report at this conference.
Date: November 19, 1963
Creator: Bateman, J. L.; Bond, V. P. & Rossi, H. H.
Object Type: Report
System: The UNT Digital Library
Feasibility of a Liquid Phase Chemonuclear Ozone Process (open access)

Feasibility of a Liquid Phase Chemonuclear Ozone Process

At the Chemonuclear Workshop held at Brookhaven National laboratory in November 1962 it was pointed out that the production of ozone from oxygen by a liquid phase fission fragment chemonuclear process appears to have reasonable economic potential. The maximum theoretical reaction yield for the formation of ozone from oxygen is a "G" value of 68 molecules for 100 ev based on heat of reaction data. The authors felt a "G" value of 15 to be reasonable for this study. the reactor system chosen has liquid oxygen as its moderator and the operating pressure and temperature were selected so as to allow boiling of the oxygen-ozone mixture. The total plant investment cost is estimated to be in the range of $100,000,000. Other system designs will be considered in the future.
Date: November 19, 1963
Creator: Cagnetta, J. P.; Goellner, D. & Steinberg, M.
Object Type: Report
System: The UNT Digital Library
Unusual incident -- Radioiodine release to atmosphere Purex Plant -- September 2, 1963 (open access)

Unusual incident -- Radioiodine release to atmosphere Purex Plant -- September 2, 1963

This report briefly describes the circumstances involving the accidental release of Iodine 131 into the atmosphere from the Purex Plant at Hanford in September, 1963.
Date: September 19, 1963
Creator: Warren, J. H.
Object Type: Report
System: The UNT Digital Library
Problems contributing to reduced neptunium shipments FY-1963 (open access)

Problems contributing to reduced neptunium shipments FY-1963

None
Date: June 19, 1963
Creator: unknown
Object Type: Report
System: The UNT Digital Library
A preliminary study of production of tungsten-rhenium alloys in N-Reactor (open access)

A preliminary study of production of tungsten-rhenium alloys in N-Reactor

Feasibility and cost data are supplied for the production of tungsten-rhenium alloys from tungsten targets in the N-Reactor. The two types of target elements assumed were: (a) tungsten containing 90 a/o tungsten-186, 9 a/o tungsten-184 and 1 a/o tungsten-183 and 182, and (b) tungsten of natural isotopic composition (28.4 a/o tungsten-186, 30.6 a/o tungsten-184, 14.4 a/o tungsten 183, and 26.4 tungsten-182). It is assumed that the average thermal neutron capture cross section for the tungsten-186 is 32 barns.
Date: November 19, 1963
Creator: Riches, J. W. & Pierick, E. G.
Object Type: Report
System: The UNT Digital Library
Potential problems in U-233 production (open access)

Potential problems in U-233 production

Interaction of {alpha} particles with elements of low atomic number leads to the emission of neutrons by the ({alpha}, n) reaction. The light element content may become one of the limiting factors in the production of U-233 acceptable for projected uses. Neutron production by the ({alpha}, n) reaction was calculated as functions of U-232 and light element contents.
Date: November 19, 1963
Creator: Kofoed, R. J.
Object Type: Report
System: The UNT Digital Library
Study of Hanford production capability through fiscal year 1973 (open access)

Study of Hanford production capability through fiscal year 1973

A letter dated June 3, 1963 to W, E. Johnson, General Manager, Hanford Atomic Products Operation, from J. E. Travis, Manager, Richland Operations Office requested an updated study on the expected life of existing production reactors similar to Sections II, III and IV of document HW-59000. This study covers the ten year period to FY 1973 as the previous study document covered the ten year period FY 1958 to Fy 1968. In Section II, production has been forecast for the existing plant with no improvements beyond the current program for installation of zirconium process tubes in the K Reactors. Section III contains estimates of additional production from the six smaller reactors made possible through overboring the process channels and retubing with zirconium plus the associated water plant expansions. Section IV presents our analysis of the assurance which can reasonably be assigned to the predictions of Sections II and.III. The production forecasts have been prepared from the same base as the current production studies and have been developed within the technical limits listed later in the report,
Date: June 19, 1963
Creator: Greninger, A. B.
Object Type: Report
System: The UNT Digital Library
Production Test-IP-610-A: Evaluation of induction heat treated fuel cores (open access)

Production Test-IP-610-A: Evaluation of induction heat treated fuel cores

The objective of this test is to evaluate the irradiation dimensional stability of uranium fuel cores produced by an induction heat treating process.
Date: November 19, 1963
Creator: Hladek, K. L.
Object Type: Report
System: The UNT Digital Library
Physics study of Po{sup 210} production capabilities in N Reactor (open access)

Physics study of Po{sup 210} production capabilities in N Reactor

The production of Po{sup 210} by irradiating Bi{sup 209} has been proposed as a possible use of N Reactor. The purpose of this study was to make an estimate of the production rates for various exposure times and flux levels. The production rate was calculated for the three flux levels of: (1) 5.0 {times} 10{sup 13} neutrons/cm{sup 2}/second, which is about the average flux level expected in the N Reactor graphite moderator; (2) 6.74 {times} 10{sup 13} neutrons/cm{sup 2}/second, which is the estimated flux level in the 68 empty process tubes on the top and bottom of the N Reactor core; (3) 7.5 {times} 10{sup 13} neutrons/cm{sup 2}/second, which is the estimated flux level present in a flux trap made by removing a column of fuel. In addition to the above calculations, an estimate was made of the fuel enrichment needed to support a column of bismuth in the core of the reactor; and the percentage loss in the Pu production was calculated for the reactor.
Date: November 19, 1963
Creator: Dieterich, R. A.
Object Type: Report
System: The UNT Digital Library
COSMOTRON CURRENT MARKER (open access)

COSMOTRON CURRENT MARKER

Modifications consisted of redesigning the feedback loop and shielding the toroid to minimize capacitive pickup and of insulating the core from the magnet buss. A system analysis is presented, and system controls and operation are described. Operational properties of the redesigned loop and tests on the insulation between the grounded Faraday shield and the magnet buss and core are discussed. (D.C.W.)
Date: June 19, 1963
Creator: Kovarik, V.J.
Object Type: Report
System: The UNT Digital Library
STRUCTURAL ANALYSIS OF ZIRCALOY FUEL-ELEMENT CONTAINERS FOR THE NS SAVANNAH REACTOR (open access)

STRUCTURAL ANALYSIS OF ZIRCALOY FUEL-ELEMENT CONTAINERS FOR THE NS SAVANNAH REACTOR

Structural evaluations were made of the 15% cold-worked Zircaloy fuel- element containers proposed for the NS Savannah reactor. These evaluations, which are consistent with the Navy Code, permitted the sizing of components so that under conservative loading conditions both stress and deflection limitations would be met. The necessary design modifications were specified for the fuel- element container assembly. (auth)
Date: August 19, 1963
Creator: Shobe, L.R.
Object Type: Report
System: The UNT Digital Library
Radiobiological Basis for the Whole Body Radiation Syndrome (open access)

Radiobiological Basis for the Whole Body Radiation Syndrome

Data are presented that show a marked species difference in the degree of damage and in the course of events seen in the bone marrow and peripheral blood after a given dose of radiation. The data taken together indicate strongly, but do not prove, that the picture seen results primarily from damage to the stem cell population. This damage to the stem cells is manifested later in the more mature differentiating cells of the marrow, and in the peripheral blood. The picture seen results both from death of stem cells, and also injury leading to reduced proliferative capacity, with later death of the injured stem cell and all of its progeny. Thus the picture seen is a result of both quantitative and qualitative changes resulting directly from the exposure of the stem cells, and species differences relative to sensitivity and time course of events appear to depend to a large degree on differential sensitivity of the bone marrow stem cell populations to death and injury. (auth)
Date: July 19, 1963
Creator: Bond, V.P. & Fliedner, T.M.
Object Type: Article
System: The UNT Digital Library
SNAP-8 Corrosion Program. Quarterly Progress Report for Period Ending August 31, 1963 (open access)

SNAP-8 Corrosion Program. Quarterly Progress Report for Period Ending August 31, 1963

None
Date: December 19, 1963
Creator: Savage, H. W.; Compere, E. L.; Huntley, W. R. & Taboada, A.
Object Type: Report
System: The UNT Digital Library
SPECIFICATIONS FOR FUEL ASSEMBLIES FOR CORE I OF THE EXPERIMENTAL GAS- COOLED REACTOR (open access)

SPECIFICATIONS FOR FUEL ASSEMBLIES FOR CORE I OF THE EXPERIMENTAL GAS- COOLED REACTOR

None
Date: May 19, 1963
Creator: Coobs, J.H.; Wick, E.A.; Evans, R.M. & Tolson, G.M.
Object Type: Report
System: The UNT Digital Library
PRELIMINARY PLANS FOR USE OF HOUGH-POWELL BUBBLE DENSITY MEASUREMENTS (open access)

PRELIMINARY PLANS FOR USE OF HOUGH-POWELL BUBBLE DENSITY MEASUREMENTS

The use of bubble density measurements to eliminate obviously wrong mass assignments is described. The process is traced through each of the four computer programs of the Hough-Powell system. (D.C.W.)
Date: February 19, 1963
Creator: Strand, R.C.
Object Type: Report
System: The UNT Digital Library
Selection of material, number and distribution of poison wires for the anticriticality poison system (open access)

Selection of material, number and distribution of poison wires for the anticriticality poison system

None
Date: November 19, 1963
Creator: Call, D.W. & Parker, G.E.
Object Type: Report
System: The UNT Digital Library
Measurement of the Shutdown Reactivity in Subcritical Configurations (open access)

Measurement of the Shutdown Reactivity in Subcritical Configurations

None
Date: January 19, 1963
Creator: Rothman, A. B.
Object Type: Report
System: The UNT Digital Library
Investigation of beryllium fracture properties in order to predict safety margin of reactor component (open access)

Investigation of beryllium fracture properties in order to predict safety margin of reactor component

None
Date: March 19, 1963
Creator: Kallin, I. N.
Object Type: Report
System: The UNT Digital Library
Advanced Materials Program for January and February 1963 (open access)

Advanced Materials Program for January and February 1963

This report explains details of the Advanced Materials Program. The purpose of this program is to develop improved alloys for nuclear powerplant structural applications in the 16000F to 2000F range and for advanced applications at temperatures to 2400F or above.
Date: April 19, 1963
Creator: United States. Department of Energy.
Object Type: Report
System: The UNT Digital Library
Investigation of beryllium fracture properties in order to predict safety margin of reactor component (open access)

Investigation of beryllium fracture properties in order to predict safety margin of reactor component

None
Date: March 19, 1963
Creator: Kallin, I. N.
Object Type: Report
System: The UNT Digital Library
Radiological Hazards Comparison of SNAP 9A to SNAP 10A (open access)

Radiological Hazards Comparison of SNAP 9A to SNAP 10A

None
Date: November 19, 1963
Creator: Willis, C. A.
Object Type: Report
System: The UNT Digital Library
SNAP fuel temperature peaking with cusps in coolant channel (open access)

SNAP fuel temperature peaking with cusps in coolant channel

Reactor Fuel Elements--temperature peaking in SNAP due to surrounding rods; systems for nuclear auxiliary power (SNAP)--reactor fuel temperataure peaking due to surrounding fuel rods; temeprature--calculations of peaking of, in SNAP fuel due to sourround fuel rods.
Date: July 19, 1963
Creator: Treuenfels, E. W.
Object Type: Report
System: The UNT Digital Library
Trip Report Industrial Health Survey of Mound Laboratory (open access)

Trip Report Industrial Health Survey of Mound Laboratory

None
Date: March 19, 1963
Creator: Davis, C. E.
Object Type: Report
System: The UNT Digital Library