Transient Conduction in Nuclear Reactor Fuel Plates (open access)

Transient Conduction in Nuclear Reactor Fuel Plates

None
Date: August 20, 1956
Creator: Alexander, Lloyd G.
System: The UNT Digital Library
ELECTRONIC ANALOG COMPUTER STUDY OF A NUCLEAR REACTOR STEAM PRESSURIZER (open access)

ELECTRONIC ANALOG COMPUTER STUDY OF A NUCLEAR REACTOR STEAM PRESSURIZER

None
Date: January 20, 1956
Creator: Bremer, J. W.
System: The UNT Digital Library
Transient calculation techniques (open access)

Transient calculation techniques

This paper presents a calculation of transient events in the Hanford piles due to the build up of fission product nuclides with a very large neutron absorption cross-section. In particular it was found after operation of the first major pile that Xe{sup 135} was a short lived isotope which built up in the pile, and which possessed a very large cross-section. The dynamics in number density of this isotope has a major impact on the reactivity behavior of the piles, and in particular on the start-up behavior following transient shut-downs.
Date: December 20, 1956
Creator: Brugge, R. O.; Stamp, S. R. & Worthington, J. T.
System: The UNT Digital Library
Preparation of Zirconium and Hafnium Metals by Bomb Reduction of Their Fluorides (open access)

Preparation of Zirconium and Hafnium Metals by Bomb Reduction of Their Fluorides

None
Date: January 20, 1956
Creator: Carlson, O. N.; Schmidt, F. A. & Wilhelm, H. A.
System: The UNT Digital Library
THE CALCULATION OF GAMMA HEATING IN REACTORS OF RECTANGULOID GEOMETRY (open access)

THE CALCULATION OF GAMMA HEATING IN REACTORS OF RECTANGULOID GEOMETRY

None
Date: July 20, 1956
Creator: Claiborne, H.C. & Fowler, T.B.
System: The UNT Digital Library
The Carbon Arc Image Furnace (open access)

The Carbon Arc Image Furnace

None
Date: June 20, 1956
Creator: Davis, T. P.
System: The UNT Digital Library
Examination of Ornl 1 and 2 Intermediate Heat Exchangers, Type Ihe-3 (open access)

Examination of Ornl 1 and 2 Intermediate Heat Exchangers, Type Ihe-3

Failure, which resulted in the stoppage of fluoride flow in ORNL No. 1, occurred as a NaK to fuel leak in the vicinity of the NaK inlet heater. The reaction of NaK with fuel at this point caused the deposition of nearly pure UF/ sub 3/ around the tubes and, finally, a sufficient increase in the melting point of the fuel to produce solidification. Fluorides throughout the heat exchangers were found to be depleted in uranium and to contain some potassium. Thus it would appear that stoppage of flow occurred after considerable NaK pick-up had taken place. Fluoride attack observed in these heat exchangers, with the exception of the area of failure, agreed substantially with what would be predicted from other dynamic systems. However, in those tubes near the point of failure, attack on the"tension" side of the tubes occurred to depths approximately twice those observed in "unstressed" tubes at comparable temperatures. Mass transferred particles were present in the NaK circuit of ORNL No. 1 to a maximum thickness of 15 mils. Deposit thicknesses varied markedly from header to header. (auth)
Date: July 20, 1956
Creator: DeVan, J. H. & Crouse, R. S.
System: The UNT Digital Library
The Electron Spin Resonance Spectrum of Dibenzene ChromiumCation (open access)

The Electron Spin Resonance Spectrum of Dibenzene ChromiumCation

The electron spin paramagnetic resonance of dibenzene chromium cation h a s been observed. I t s c e n t e r is a t a valhe of g = 1.98. I t shows eleven hyperfine components s e p a r a t e d by 3.5 gauss. These a r e i n t e r p r e t e d to b e eleven of the thirteen components expected to r e s u l t f r o m the interaction of the twelve equivalent protons with the unpaired electron.
Date: December 20, 1956
Creator: Feltham, Robert D.; Sogo, Power & Calvin, Melvin
System: The UNT Digital Library
OPERATING MANUAL FOR ORACLE CODE NO. 243: THE CALCULATION OF GAMMA HEATING IN REACTORS OF RECTANGULAR GEOMETRY (open access)

OPERATING MANUAL FOR ORACLE CODE NO. 243: THE CALCULATION OF GAMMA HEATING IN REACTORS OF RECTANGULAR GEOMETRY

None
Date: August 20, 1956
Creator: Fowler, T.B. & Claiborne, H.C.
System: The UNT Digital Library
A Conceptual Design of a Shield Testing and Materials Irradiation Facility (open access)

A Conceptual Design of a Shield Testing and Materials Irradiation Facility

A conceptual design is presented for a test reactor facility to be used for shielding experiments and component irradintions necessary for airframe development for the nuclear airplane program. To meet both requirements a modified swimming-pool reactor is used, with a dry irradintion cell of 320 cu ft of useful volume provided for component testing, while shielding experiments are performed in the pool in the usual manner. A BSR-type core is operated at 1 MW to provide a fest neutron flux in the irradiation cell of 10/sup 12/n/cm/sup 2/ sec at the core face and 10/sup 11/at a distance of 4 feet. The irradiation-cell facility is designed to avoid the need of remote operations in making up service connections to the experimental piece. The reactor is contained in a cylindrical building designed for 6 psi internal pressure to meet the conditions of the maximum credible accident. The estimated cost of the facility, including the reactor and the fabrication cost for an initial fuel charge, is 874,000. (auth)
Date: November 20, 1956
Creator: Frankfort, J.H.
System: The UNT Digital Library
Energy Transfer Between Modified Maxwell Distributions (open access)

Energy Transfer Between Modified Maxwell Distributions

S>A convenient modified form of Maxwell distribution is chosen. The modified expressions for the energy transfer from the ions to the electrons in a plasma and the bremsstrahlung from the electrons are calculated. Using the expressions some possible steady-state conditions for the ion and electron gases are derived and compared with those for the usual Maxwell distributions. (anth)
Date: September 20, 1956
Creator: Greyber, H. D.
System: The UNT Digital Library
Measurement of Thermal Conductivity of Uranium Oxide. Final Report (open access)

Measurement of Thermal Conductivity of Uranium Oxide. Final Report

None
Date: September 20, 1956
Creator: Hedge, J. C. & Fieldhouse, I. B.
System: The UNT Digital Library
Past exposure problems in room 242, 234-5 Building (open access)

Past exposure problems in room 242, 234-5 Building

None
Date: June 20, 1956
Creator: Helgeson, G.L.
System: The UNT Digital Library
HRT HEAT EXCHANGERS--CLEANING RUNS PERFORMED AT Y-12 (open access)

HRT HEAT EXCHANGERS--CLEANING RUNS PERFORMED AT Y-12

None
Date: March 20, 1956
Creator: Holz, P P
System: The UNT Digital Library
A comparison of monthly slug ruptures at C-Pile (open access)

A comparison of monthly slug ruptures at C-Pile

This memorandum provides a comparison of monthly slug ruptures at the Hanford C-Pile.
Date: June 20, 1956
Creator: Jaech, J. L.
System: The UNT Digital Library
Statistical Quality Control Quarterly Report for the Analytical Chemistry Division, January - March, 1956 (open access)

Statistical Quality Control Quarterly Report for the Analytical Chemistry Division, January - March, 1956

None
Date: April 20, 1956
Creator: Kelley, M. T.
System: The UNT Digital Library
HRT Leak Detection System (open access)

HRT Leak Detection System

All HRT process piping and equipment is contained in a large tank and flanged connections with stainless steel ring gaskets are used where needed to permit the removal of values and items of equipment. Underwater remote maintenance is to be employed and special provisions are required for indicating and locating leaks at all mechanical joints in the process system. Each joint is monitored and a signal is given when a leak occurs. The valve operator stems are sealed with stainless steel bellows and a means of detecting a leak in the bellows has been included. (auth)
Date: April 20, 1956
Creator: Kuster, J.E.
System: The UNT Digital Library
Neutron Activation Analysis (open access)

Neutron Activation Analysis

None
Date: July 20, 1956
Creator: Leddicotte, G. W. & Reynolds, S. A.
System: The UNT Digital Library
Use of Nitrogen as Inert Gas Backing in Welding Austenitic Stainless Steels (open access)

Use of Nitrogen as Inert Gas Backing in Welding Austenitic Stainless Steels

None
Date: August 20, 1956
Creator: Leonard, W. J.
System: The UNT Digital Library
A Bev High Current Accelerator (open access)

A Bev High Current Accelerator

This report addresses a bev high current acceleration.
Date: June 20, 1956
Creator: Livingston, Robert S.
System: The UNT Digital Library
FUEL MELTING EXPERIMENT-IRRADIATION REQUEST ORNL-MTR-28, PHASE A (open access)

FUEL MELTING EXPERIMENT-IRRADIATION REQUEST ORNL-MTR-28, PHASE A

None
Date: June 20, 1956
Creator: Neill, F H
System: The UNT Digital Library
Hrt Critical Concentration as a Function of Temperature (open access)

Hrt Critical Concentration as a Function of Temperature

None
Date: June 20, 1956
Creator: Nestor, C. W. Jr.
System: The UNT Digital Library
EXAMINATION OF THE NORTH CAROLINA STATE COLLEGE REACTOR CORE (open access)

EXAMINATION OF THE NORTH CAROLINA STATE COLLEGE REACTOR CORE

None
Date: July 20, 1956
Creator: Olsen, A.R. & Richt, A.E.
System: The UNT Digital Library
NUCLEAR CHARACTERISTICS OF TWO-REGION SLURRY REACTORS (open access)

NUCLEAR CHARACTERISTICS OF TWO-REGION SLURRY REACTORS

None
Date: December 20, 1956
Creator: Rosenthal, M.W. & Tobias, M.
System: The UNT Digital Library