Critical Flow of Liquid Metals (open access)

Critical Flow of Liquid Metals

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Date: January 15, 1965
Creator: Isbin, H. S.
System: The UNT Digital Library
Evaluation of fuel elements from SNAP 2 development reactor core (open access)

Evaluation of fuel elements from SNAP 2 development reactor core

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Date: January 15, 1965
Creator: Olson, P.S.
System: The UNT Digital Library
Fuel development contribution to work statement, FY-1965 (open access)

Fuel development contribution to work statement, FY-1965

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Date: January 15, 1965
Creator: Freed, M.S.
System: The UNT Digital Library
Irradiation Processing Department Monthly Report: December 1964 (open access)

Irradiation Processing Department Monthly Report: December 1964

This document details activities of the irradiation processing department during the month of December, 1964. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; trips; and Financial Operation.
Date: January 15, 1965
Creator: Hanford Atomic Products Operation. Irradiation Processing Department.
System: The UNT Digital Library
A PROGRAM OF BASIC RESEARCH ON MECHANICAL PROPERTIES OF REACTOR MATERIALS. Annual Summary Report for the Period Ending October 31, 1964 (open access)

A PROGRAM OF BASIC RESEARCH ON MECHANICAL PROPERTIES OF REACTOR MATERIALS. Annual Summary Report for the Period Ending October 31, 1964

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Date: January 15, 1965
Creator: Chambers, R H; Trozera, T A & White, J L
System: The UNT Digital Library
RECOVERY OF STRONTIUM FROM STORED PUREX WASTE BY LEAD SULFATE CARRIER PRECIPITATION--PILOT PLANT STUDIES (open access)

RECOVERY OF STRONTIUM FROM STORED PUREX WASTE BY LEAD SULFATE CARRIER PRECIPITATION--PILOT PLANT STUDIES

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Date: January 15, 1965
Creator: Richardson, G.L.
System: The UNT Digital Library
SNAP 10A reactor nuclear analysis (open access)

SNAP 10A reactor nuclear analysis

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Date: January 15, 1965
Creator: Dayes, A.R.; Flynn, W.A. & Hawley, J.P.
System: The UNT Digital Library
SODIUM-HEATED STEAM GENERATOR DEVELOPMENT. Quarterly Progress Report, October-December 1965 (open access)

SODIUM-HEATED STEAM GENERATOR DEVELOPMENT. Quarterly Progress Report, October-December 1965

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Date: January 15, 1965
Creator: unknown
System: The UNT Digital Library
Advanced, Graphite-Matrix, Dispersion-Type Fuel Systems And Research on Graphite. Quarterly Progress Report for the Period Ending February 14, 1965 (open access)

Advanced, Graphite-Matrix, Dispersion-Type Fuel Systems And Research on Graphite. Quarterly Progress Report for the Period Ending February 14, 1965

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Date: February 15, 1965
Creator: Bokros, J. C.; Goeddel, W. V.; Lonsdale, H. K.; Price, R. J.; White, J. L. & Zumwalt, L. R.
System: The UNT Digital Library
ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. Quarterly Progress Report, October 1-December 1964 (open access)

ARMY GAS-COOLED REACTOR SYSTEMS PROGRAM. Quarterly Progress Report, October 1-December 1964

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Date: February 15, 1965
Creator: unknown
System: The UNT Digital Library
THE COMPRESSIBILITY OF GASEOUS MIXTURES OF HELIUM-NITROGEN AND HELIUM- DEUTERIUM AT HIGH PRESSURES (open access)

THE COMPRESSIBILITY OF GASEOUS MIXTURES OF HELIUM-NITROGEN AND HELIUM- DEUTERIUM AT HIGH PRESSURES

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Date: February 15, 1965
Creator: Cramer, J.D.
System: The UNT Digital Library
METHODS FOR CALCULATION OF THE ELK RIVER REACTOR FUEL INVENTORY (open access)

METHODS FOR CALCULATION OF THE ELK RIVER REACTOR FUEL INVENTORY

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Date: February 15, 1965
Creator: Kennedy, M.L.; Ho, C. & Kendrick, E.D.
System: The UNT Digital Library
REPETITIVELY PULSED ACCELERATOR BOOSTERS (open access)

REPETITIVELY PULSED ACCELERATOR BOOSTERS

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Date: February 15, 1965
Creator: Beyster, J.R. & Russell, J.L.
System: The UNT Digital Library
Technical feasibility of using uranium oxide fuels at Hanford (open access)

Technical feasibility of using uranium oxide fuels at Hanford

The use of uranium oxide fuel and the dispensing with metallic fuel elements in the Hanford production reactors have been contemplated in the past but have not been examined in any detail. This report reviews the technical feasibility of using oxide fuel and discusses the reactor limitations and changes in plutonium and isotope production. These results are based on preliminary calculations and a research and development program would be required to establish the validity of the calculated values. The research and development program is estimated to require $3.6 million over a three-year period. Technical aspects of using oxide are discussed in general for N, K, and the smaller reactors. The variations in uranium-to-graphite weight ratio and operating conditions vary the limitations encountered with each reactor type with an oxide fuel cycle. Plutonium separation and uranium oxide recycle on site have been examined, and a technical review of the limitations and the additional process requirements are presented.
Date: February 15, 1965
Creator: unknown
System: The UNT Digital Library
TEMPERING BEHAVIOR OF TWO PRESSURE-VESSEL STEELS (open access)

TEMPERING BEHAVIOR OF TWO PRESSURE-VESSEL STEELS

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Date: February 15, 1965
Creator: Ferrill, D.A.; DiNuzzo, L.J. & Oberdick, R.H.
System: The UNT Digital Library
Tungsten Cladding of Tungsten-Uranium Dioxide (W-UO2) Composites by Deposition from Tungsten Hexafluoride (WF6) (open access)

Tungsten Cladding of Tungsten-Uranium Dioxide (W-UO2) Composites by Deposition from Tungsten Hexafluoride (WF6)

A program is being conducted to develop a process for cladding tungsten and tungsten cermet fuels with tungsten deposited from the vapor state by the hydrogen reduction of tungsten hexafluoride. Early work was performed using recrystallized, high purity, commercial tungsten as the substrate material. Temperatures in the range 660 to 12950F (350 to 1700°C) and pressures from 10 to 350 mm Hg were investigated. Hydrogen to WF 6 ratios of 10: 1 to 150: 1 were utilized. Efforts were directed toward optimizing deposition process parameters to attain control of qualities such as coating thickness, uniformity, density, impurity content, and surface quality. Substrate penetration methods have been investigated in the interest of completely eliminating the interface between the fueled substrate and cladding. In addition, the effects of process parameters and post-cladding heat treatments on the fuel retention properties of clad composites at 4500 degrees F (2480 degrees C) in hydrogen for 2 hours have been evaluated. As a result of work performed during the first phase of the program it has been shown that the rate of deposition of tungsten from WF 6 and the uniformity of the deposit can be varied in a predictable and reproducible manner by exercising control …
Date: February 15, 1965
Creator: Lamartine, J.T. & Hoppe, A.W.
System: The UNT Digital Library
USE OF NEUTRON ACTIVATION ANALYSIS IN SCIENTIFIC CRIME DETECTION. 12- Month Summary Report for the Period November 1, 1963-October 31, 1964 (open access)

USE OF NEUTRON ACTIVATION ANALYSIS IN SCIENTIFIC CRIME DETECTION. 12- Month Summary Report for the Period November 1, 1963-October 31, 1964

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Date: February 15, 1965
Creator: Bryan, D.E. & Guinn, V.P.
System: The UNT Digital Library
THE DENSITY-FLOW REGIME OF FRANKLIN D. ROOSEVELT LAKE (open access)

THE DENSITY-FLOW REGIME OF FRANKLIN D. ROOSEVELT LAKE

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Date: March 15, 1965
Creator: Jaske, R.T.
System: The UNT Digital Library
DETERMINATION OF PHASE EQUILIBRIA IN THE SYSTEM BeO-ThO$sub 2$. Second Quarterly Report (open access)

DETERMINATION OF PHASE EQUILIBRIA IN THE SYSTEM BeO-ThO$sub 2$. Second Quarterly Report

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Date: March 15, 1965
Creator: Otto, Henry E.
System: The UNT Digital Library
The Interpretation of Nuclear Excitation Functions at High Energy: Ericson Fluctuations (open access)

The Interpretation of Nuclear Excitation Functions at High Energy: Ericson Fluctuations

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Date: March 15, 1965
Creator: Gibbs, W. R.
System: The UNT Digital Library
Operational report on the Purex Plant Thorium Process Test (open access)

Operational report on the Purex Plant Thorium Process Test

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Date: March 15, 1965
Creator: Duckworth, J. P.; Harlow, D. G. & Herrington, C. C.
System: The UNT Digital Library
PROMETHIUM ISOTOPIC POWER DATA SHEETS (open access)

PROMETHIUM ISOTOPIC POWER DATA SHEETS

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Date: March 15, 1965
Creator: Van Tuyl, H.H.
System: The UNT Digital Library
PURIFICATION OF STRONTIUM-90 FROM MAGNESIUM (open access)

PURIFICATION OF STRONTIUM-90 FROM MAGNESIUM

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Date: March 15, 1965
Creator: Bray, L.A.
System: The UNT Digital Library
Reactor and Materials Technology Department Monthly Report February 1965 (open access)

Reactor and Materials Technology Department Monthly Report February 1965

This report details activities of the Reactor and Materials Technology Department for the month of February 1965.
Date: March 15, 1965
Creator: Albaugh, F. W.
System: The UNT Digital Library