UNT Libraries Government Documents Department - 1,229 Matching Results

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DMM: A Multigroup, Multiregion, One-Space-Dimensional Computer Program Using Neutron Diffusion Theory. Part 1 - The Theory

Description: DMM is a program using one-space-dimensional multigroup diffusion theory to calculate the reactivity or critical conditions and flux distribution of a multiregion reactor. Calculations of fission-produced xenon and samarium and time variation due to production and depletion of isotopes are an essential part of this program. The adjoint fluxes may also be computed, and the program includes the calculation of the nuclear constaants from fairly simple input combined with a library of cross section… more
Date: December 31, 1960
Creator: Leshan, Edward J. & Kavanagh, Deveroux L.
Item Type: Refine your search to only Report
open access

DMM: A MULTIGROUP, MULTIREGION ONE-SPACE-DIMENSIONAL COMPUTER PROGRAM USING NEUTRON DIFFUSION THEORY. PART II. DMM PROGRAM DESCRIPTION

Description: Operating instructions are presented for DMM, a Remington Rand 1103A program using one-space-dimensional multigroup diffusion theory to calculate the reactivity or critical conditions and flux distribution of a multiregion reactor. Complete descriptions of the routines and problem input and output specifications are also included. (D.L.C.)
Date: December 31, 1960
Creator: Kavanagh, D.L.; Antchagno, M.J. & Egawa, E.K.
Item Type: Refine your search to only Report
open access

[Hanford weekly teletype report]: Supplement report for week ending June 12

Description: This document contains information about flooding of the Columbia River. It focuses attention on the following; increased elevation due to rainfall, seepage which destabilized the constructed dike, flooding of cellars, evacuation of people to emergency shelters, tug boat collision damage to power lines, and the washout of the Van Giesen Street Bridge on Yakima River.
Date: December 31, 1960
Item Type: Refine your search to only Report
open access

ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM SUMMARY REPORT ON MATERIALS FOR THE GCRE-II

Description: Investigatiors were made of various materials for development of metal- canned and semi-homogeneous GCRE-II fuel element concepts. The materials were studied for application to development of fuels, grapanite, silicon-silicon carbide coatings, metal claddings, carburization barrier coatings, and graphite joining. A survey of the literature showad that uranium carbide fuels are superior to other types for the applications described and that refractory metal or metal carbide fuel coatings appear … more
Date: December 30, 1960
Creator: Carpenter, R. & Del Grosso, A.
Item Type: Refine your search to only Report
open access

PT-IP-385-C, E-N reactivity matching measurement

Description: The projected E-N load at H Reactor will require a complete change in the type of charge placed in most flattened zone process tubes. Objective of this test is to determine the reactivity of the proposed E-N charge relative to the known natural uranium charge reactivity.
Date: December 30, 1960
Creator: Carter, R. D.
Item Type: Refine your search to only Report
open access

REACTOR FUEL WASTE DISPOSAL PROJECT-PERMEABILITY OF ROCK SALT AND CREEP OF UNDERGROUND SALT CAVITIES. Final Report

Description: A study was made of two problems of salt-cavity storage, namely, seepage of wastes out of formations and closure of cavities due to plastic flow of salt. The results indicate that both problems are negligible; bedded salt is more impermeable than dome salt. Kerosene was found to be nonreactive with dome salt whereas brine solutions showed some interaction. It is concluded that storage of radioactive wastes in salt cavities is feasible. (D.L.C.)
Date: December 30, 1960
Creator: Reynolds, T.D. & Gloyna, E.F.
Item Type: Refine your search to only Report
open access

Analysis of E-N loadings

Description: Three E-N loaded tubes were dissolved, sampled and analyzed, starting November 9, 1960. The results of these analyses and an explanation of the methods used are the subject of this report. Each tube loading received an identification code in each facility in which it was processed. All of these codes are listed for future reference. Each batch of slugs was dissolved in a preflushed dissolver. When complete solution was indicated by a leveling off of the specific gravity, two 1 ml samples were t… more
Date: December 28, 1960
Creator: Zimmer, W. H.
Item Type: Refine your search to only Report
open access

Optimization Studies on Paste-Fueled Fast Reactors

Description: The reference design is an unmoderated, sodium-cooled reactor using a paste fuel of uranium monocarbide in sodium. The core is a cylinder 5 ft in diameter and 5 ft in height. An 18-in. thick breeding blanket surrounds the core, and an 18-in. thick graphite reflector surrounds the blanket. Various changes were made in the reference core to uncover any possible modifications for cost reductions and to evaluate the consequences of certain design modifications which might occur. Cases were studied … more
Date: December 28, 1960
Creator: Zetterbaum, J. M. & Kerlin, T. W.
Item Type: Refine your search to only Report
open access

Aerodynamic Re-Entry Analysis. Task 2. Thermoelectric Generator Summary Report

Description: An analytical trajectory and aerothermodynamic analysis of a satellite containing a Task 2 thermoelectric generator was completed. A 300-statute mile circular polar orbit was used for this analysis and the launch was assumed to be from Vandenberg Air Force Base. Results of this study show that upon natural decay from a successful mission, the radio-cerium fuel will burn up in space at high altitude, thus only a very minor amount of radio cerium will be released to the stratosphere. A complete a… more
Date: December 27, 1960
Creator: Oehrli, R.
Item Type: Refine your search to only Report
open access

DISPERSION STRENGTHENING OF IRON-ALUMINUM BASE ALLOYS: A FEASIBILITY STUDY

Description: The feasibility of improving the mechanical properties at 1700 to 1800 deg F of oxidation-resistant Fe-Al-Cr alloys by means of a refractory dispersion was explored. A literature search was conducted, preliminary experimental determinations of properties of the alloy and its oxides were carried out, and certain mathematical relations between dispersion charaeteristics and metallurgical variables were derived. The results indicate that the alloys can be strengthened sufficiently by using a dispe… more
Date: December 27, 1960
Creator: King, B.
Item Type: Refine your search to only Report
open access

Final Report on the Pinot Experiment

Description: The Pinot Project was designed to provide some indication of the extent to which gases from a confined underground explosion in oil shale would migrate parallel to the bedding planes. At 0800 on Aug. 2, 1960, 946 lb of nitromethane was fired in shot hole No. 1. There was no visible damage to the mine adit or to any structure associated with cation of the extent to which gases from a confined underground explosion in oil shale would migrate parallel to the bedding planes. At 0800 on Aug. 2, 1960… more
Date: December 27, 1960
Creator: Adelman, F. L.; Bacigalupi, C. M. & Momyer, F. F.
Item Type: Refine your search to only Report
open access

Loading and operating conditions for NIN-1 and NIE-1 elements in the KER loops under PT-IP-377-A

Description: This document provides the loading and operating conditions for eight 16-inch or five 24-inch elements, either natural NIN-1 or .947% enriched NIE-1, in any of the four KER loops. The loadings are tabulated; operating conditions for either charge in KER 2, 3, 4, or 1 are given in figures.
Date: December 23, 1960
Creator: Kratzer, W. K.
Item Type: Refine your search to only Report
open access

A CORROSION STUDY OF WELDED STAINLESS STEEL FUEL ELEMENTS

Description: Fuel element corrosion studies designed to and in selecting and evaluating SM-2 fuel element welding techniques are discussed. Tests on type 347 ss plate type fuel elements welded by the selected tungsten inert gas technique showed good corrosion integrity of specimens under a variety of conditions including a 500-hr test under simulated SM-2 conditions of flow and coolant chemistry. (auth)
Date: December 22, 1960
Creator: Bergen, C. R.
Item Type: Refine your search to only Report
open access

Chemical Processing Department Monthly Report: November 1960

Description: This report, from the Chemical Processing Department at HAPO for November 1960, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; and special separation processing and auxiliaries operation.
Date: December 21, 1960
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Item Type: Refine your search to only Report
open access

In-Pile Corrosion Test Loops for Aqueous Homogeneous Reactor Solutions

Description: An in-pile corrosion test loop is described which is used to study the effect of reactor radiation on the corrosion of materials of construction and the chemical stability of fuel solutions of interest to the Aqueous Homogeneous Reactor Program at ORNL. Aqueous solutions of uranyl sulfate are circulated in the loop by means of a 5-gpm canned-rotor pump, and the pump loop is designed for operation at temperatures to 300 ts C and pressures to 2000 psia while exposed to reactor radiation in beam-h… more
Date: December 21, 1960
Creator: Savage, H.C.; Jenks, G.H. & Bohlmann, E.G.
Item Type: Refine your search to only Report
open access

Temperature Distribution, Moderator and Reflector Reactor Core

Description: Studies were made to determine revised moderator coolant flow requirements in the EGCR core for the latest design. The temperature distribution in the graphite columns was also determined. The total moderator coolant flow was calculated to be 24,024 lb/hr and 31,020 lb/hr for full power and maximum anticipated power, respectively. It was concluded that the maximum moderator temperature (1220 deg F average over the cross section), at full power operation, occurs near the peak heat flux at a loca… more
Date: December 21, 1960
Creator: Cheng, F.
Item Type: Refine your search to only Report
open access

Burnout Heat Fluxes for Low-Pressure Water in Natural Circulation

Description: Twenty-nine experimental determinations of burn-out heat flux were made with water flowing by natural circulaion through electrically heated vertical tubes with and without internal twisted tapes and through rectangular cross sections of three aspect ratios. Heated lengths varied from 10 to 33 in., system pressure at the testsection flow exit from 14.7 to 26.3 psia, inlet subcooling from 36 to 170 deg F, and burn-out heat flux from 13,000 to 218,500 Btu/hr/sq ft. Tests were made with both unres… more
Date: December 20, 1960
Creator: Gambill, W. R. & Bundy, R. D.
Item Type: Refine your search to only Report
open access

Optimum canning conditions for four-inch I & E fuel elements

Description: Because of difficulties in charging eight-inch fuel elements in bowed process tubes in the upper parts of the old reactors, IPD has requested that four-inch I & E fuel elements be provided for these tubes early in CY1961. Approximately 30,000 fuel elements of this design, Model OVN, will be required per year. Since most of these fuel elements will be charged in the upper fringe zones, they will be in-reactor for an extended period of time. For this reason, the quality of this material should be… more
Date: December 20, 1960
Creator: Strand, C. A.
Item Type: Refine your search to only Report
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