Calculation and Measurement of the Transient Temperature in a Low- Enrichment UO$sub 2$ Fuel Rod During Large Power Excursions (open access)

Calculation and Measurement of the Transient Temperature in a Low- Enrichment UO$sub 2$ Fuel Rod During Large Power Excursions

The results of Spert I in-pile transient tests of a rodtype, low- enrichment UO/sub 2/ fuel element are presented. The tests were performed to investigate the possibility of damage to such long thermal-time-constant fuel rods when subjected to short-period power excursions, and to test the effectiveness of an instrumentation technique for measurement of UO/sub 2/ fuel temperatures within the rods. In an initial series of power excursion tests, in which the range of reactor periods was from approximately 1 sec to 7.5 msec, simultaneous measurements were made of the transient temperature at the center of the fuel rod and at the outer cladding surface. Fuel rod rupture occurred during the exponential rise of the 7.5-msec excursion. Similar short-period tests performed on a second fuel rod contain ing no internal thermocouples did not result in cladding failure, supporting the postulation that rupture of the first rod was caused by waterlogging of the UO/sub 2/ as a result of the cladding penetrations made for installation of the internal thermocouples. Calculations of the transient temperature distribution in the fuel rod were made, and the results are found to be in good agreement with the experimental data obtained on the central-UO/sub 2/ and cladding-surface …
Date: May 18, 1962
Creator: Houghtaling, J. E.; Quigley, T. M. & Spano, A. H.
Object Type: Report
System: The UNT Digital Library
Facility Availability Brookhaven Graphite Research Reactor: January 1951 - March 1962 (open access)

Facility Availability Brookhaven Graphite Research Reactor: January 1951 - March 1962

This technical report details and outlines the BGRR facility's operations and performance record over a period of twelve years. The author of this report finds that the reactor is "one of the most stable and dependable in the business." The report includes two figures.
Date: May 18, 1962
Creator: Thompson, Dudley
Object Type: Report
System: The UNT Digital Library
Gas-pressure bonding and evaluation of aluminum-clad nickel-plated uranium fuel assemblies (open access)

Gas-pressure bonding and evaluation of aluminum-clad nickel-plated uranium fuel assemblies

We are enclosing three copies of a proposal concerned with the preparation for preliminary evaluation of up to 128 Hanford CV size I and II fuel elements to determine an optimum gas-pressure-bonding cycle for the fabrication of this type of fuel element. This proposal is based on your request as outlined in your letter dated May 7, 1962, and document No. HW-72417. Included is a cost estimate of the funding required to conduct this experimental study. All of the aluminum-clad uranium fuel assemblies are to be prepared and furnished by HAPO for gas-pressure bonding at Battelle in existing equipment. To implement the proposed program we have also enclosed six copies of the BMI-AEC research agreement (Serial No. 88). The agreement provides for a six-month research period with an estimated total cost of $24,780. This sum includes $1,180 find fee as established in Contract No. W-7405-ENG-92. Receipt of two fully amounted copies of the agreement, classification guidance, and the specimens will allow us to proceed.
Date: May 18, 1962
Creator: Davis, J. E.
Object Type: Report
System: The UNT Digital Library
A Method of Estimating the Kinetic Effects of Scram Rods (open access)

A Method of Estimating the Kinetic Effects of Scram Rods

None
Date: May 18, 1962
Creator: Moore, K. V. & Gossmann, S. R.
Object Type: Report
System: The UNT Digital Library
Production test IP-338-A, Supp. A, DR-Reactor heat decay test at high outlet water temperatures (open access)

Production test IP-338-A, Supp. A, DR-Reactor heat decay test at high outlet water temperatures

This test is identical to the original except that it authorizes the performance of a trial reduction in reactor flow during a prior reactor shutdown. This trial flow reduction will be performed in the same manner as proposed for the actual test, with one exception. This is, that based upon the results of this preliminary test some changes in the timing of the different steps may be indicated. Such changes can readily be handled by making each step dependent upon the observed reactor outlet temperature during the test performance. The other significant change in the production test is the increase in the allowable bulk outlet temperature from Ti + 40 {plus_minus} 3{degrees}C{sup *}. This change is needed to obtain a reasonable extrapolation of the results of tests No. 1 and No.2 to 90{degrees}C, and is justified from a hazards standpoint by the excellent flow control achieved during test No. 1 and by the trial test that will be run prior to the performance of the actual test No. 2. Other aspects of the test basis and justification are presented in the original production test.
Date: May 18, 1962
Creator: Jones, S. S.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-1331 (open access)

Texas Attorney General Opinion: WW-1331

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether Certificates of Deposit in Banks are "Lawful Money of the United States."
Date: May 18, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History