ORNL ceramic information meeting trip report, October 1--3, 1956 (open access)

ORNL ceramic information meeting trip report, October 1--3, 1956

The meeting was opened by Leo Brewer, who spoke on a ``Self-Purifying Reactor.`` This is a reactor with theoretically designed-in separations processes, involving calculations to show that it is possible to vaporize many fission products away from fuels. The reactor would be analogous to a graphite rod impregnated with a uranium or thorium compound, vapor-coated with zirconium, and cooled by liquid metal. The fission products will vaporize when the rod gets hot enough, and will be carried out of the pile in a flow of helium. The details of what will happen to the rest of the pile at these temperatures, and of the materials of construction required to handle the situation are yet to be worked out. Remarks were heard from representatives of BMI, GE, Lockland, ANL, ORNL, KAPL, AEC and MCW on properties of uranium oxides and other refractory oxides.
Date: October 25, 1956
Creator: O`Leary, W. J.
System: The UNT Digital Library
The Constitution of Delta-Phase Alloys of the System Uranium-Molybdenum-Titanium (open access)

The Constitution of Delta-Phase Alloys of the System Uranium-Molybdenum-Titanium

None
Date: September 25, 1956
Creator: Saller, H. A.; Rough, F. A.; Bauer, A. A. & Doig, J. R.
System: The UNT Digital Library
THE ELECTRICAL PROPERTIES OF URANIUM OXIDES (open access)

THE ELECTRICAL PROPERTIES OF URANIUM OXIDES

None
Date: September 25, 1956
Creator: Willardson, R.K.; Moody, J.W. & Goering, H.L.
System: The UNT Digital Library
Routine 107 basin inlet samples (open access)

Routine 107 basin inlet samples

None
Date: August 25, 1956
Creator: Reid, D. L.
System: The UNT Digital Library
Final Physics Report for the Engineering Test Reactor (open access)

Final Physics Report for the Engineering Test Reactor

This report is a summary of the physics design work performed on the Engineering Test Reactor. The ETR presents computational difficulties not found in other reactors because of the large number of experimental holes in the core. The physics of the ETR depends strongly upon the contents of the in-core experimental facilities. In order to properly evaluate the reactor' taking into account the experiments in the core, multi-region, two-dimensional calculations are required. These calculations require .the use of a large computer such as the Remington Rand Univac and are complex and expensive enough to warrant a five-stage program: 1. In the early stages of design, only preliminary two-dimensional calculations were performed .in order to obtain a rough idea of the general behavior of the reactor and its critical mass with tentative experiments in place. 2. A large amount of work was carried out in which the reactor was approximated as one with a uniform homogeneous core. With this model, detailed studies were carried out to investigate the feasibility and to obtain general design data on such points as the design and properties of the gray and black �control rods, the design of the beryllium reflector, gamma and neutron heating, the …
Date: June 25, 1956
Creator: Wolfe, I. B.
System: The UNT Digital Library
Final Physics Report for the Engineering Test Reactor (open access)

Final Physics Report for the Engineering Test Reactor

This volume continues with discussions of shielding provided for the heat exchanger building, concrete biological shield, top area and bottom area shielding, canal shielding, water shielding requirements during fuel element exchanges, and supplementary shielding requirements.
Date: June 25, 1956
Creator: Cegelski, W. & Machell, W.
System: The UNT Digital Library
Uranium Alloys for High-Temperature Application (open access)

Uranium Alloys for High-Temperature Application

None
Date: June 25, 1956
Creator: Saller, H. A.; Dickerson, R. F. & Murr, W. E.
System: The UNT Digital Library
EFFICIENCY OF FUEL SYSTEM ENTRAINMENT SEPARATOR DURING NORMAL OPERATION. HRT Report 11 A (7c)b. Work Period: September 27, 1955-November 25, 1955 (open access)

EFFICIENCY OF FUEL SYSTEM ENTRAINMENT SEPARATOR DURING NORMAL OPERATION. HRT Report 11 A (7c)b. Work Period: September 27, 1955-November 25, 1955

None
Date: May 25, 1956
Creator: Haubenreich, P.N.; Kolb, J.O.; Van Winkel, R. & Haynes, T.E.
System: The UNT Digital Library
Flow test: CG-482 ``DR type`` rear pigtail with B, D, DR and F pile fittings (open access)

Flow test: CG-482 ``DR type`` rear pigtail with B, D, DR and F pile fittings

This letter transmits the data from the 189-D Hydraulics Laboratory flow test on three CG-482 rear pigtails. The tests were run with a standard B, D, Dr and F rear nozzle and rear Parker fitting over the range of flows and temperatures anticipated for early CG-558 operation. The data from the test are given. All three pigtails gave essentially identical results. For comparison the results of previous tests with present rear pigtails are also plotted.
Date: May 25, 1956
Creator: Bell, K. J.
System: The UNT Digital Library
HRT MODIFIED PRESSURIZER DESIGN (open access)

HRT MODIFIED PRESSURIZER DESIGN

None
Date: May 25, 1956
Creator: Michelson, C.
System: The UNT Digital Library
PRESSURE SHELL STRESS ANALYSIS HRR (open access)

PRESSURE SHELL STRESS ANALYSIS HRR

None
Date: May 25, 1956
Creator: Lawrence, M.C.
System: The UNT Digital Library
ESTIMATE OF THE COST OF PRODUCING NITROGEN 15 BY CHEMICAL EXCHANGE: DETERMINATION OF MINIMUM COST NITROX SYSTEM (open access)

ESTIMATE OF THE COST OF PRODUCING NITROGEN 15 BY CHEMICAL EXCHANGE: DETERMINATION OF MINIMUM COST NITROX SYSTEM

None
Date: April 25, 1956
Creator: Klima, B.B.
System: The UNT Digital Library
[Cladding of uranium tubes] (open access)

[Cladding of uranium tubes]

None
Date: January 25, 1956
Creator: McBride, C. C.
System: The UNT Digital Library
The Hermex process for metal decontamination by mercury processing (open access)

The Hermex process for metal decontamination by mercury processing

None
Date: January 25, 1956
Creator: Morrison, B. H. & Blanco, R. E.
System: The UNT Digital Library