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Fabrication of hot die sized Diffusion Bonded Fuel Elements for Supplement ``A`` to Production Test IP-546-A

Description: Production Test IP-546-A. consisting of 20 charges for the purpose of irradiating the first hot die sized fuel elements was charged in C-Reactor July 27, 1963. A second tests PT-IP-616-A containing a total of 19 charges had been charged on two separate outages; 13 land 6 tubes on September 28, 1963 and October 30, 1963, respectively. Fabrication of test quantities was becoming more routine and additional irradiation tests were planned. This report summarizes the fabrication of hot die sized fue… more
Date: October 5, 1964
Creator: Strand, C. A.
open access

GETR graphite irradiation capsules: H-4, 5, 6 equivalent N Reactor exposure

Description: A program for the irradiation of samples-of N-Reactor graphite has been in progress since November 30 1961, in the General Electric Test Reactor (GETR). The basic purpose of the program is to achieve an exposure to the samples equivalent to 20 years of operation of N-Reactor and to relate the physical distortion of the samples to the expected behavior of the N-Reactor moderator stack. Theoretical studies to relate sample exposure in the GETR to exposure in N-Reactor have been underway since the… more
Date: March 5, 1964
Creator: Helm, J. W.
open access

Hanford contribution for the eighteenth high temperature fuels committee meeting, May 19--21, 1964

Description: Metallic thorium uranium fuel elements continue to show excellent irradiation performance in high temperature pressurized water coolant. Volume expansion measurements made after 2.1{times}10{sup 20} fissions/cm{sup 3} (6200 MWD/T) at fuel temperatures above 500 C shows no indication of fission gas-in-duced swelling. Analysis of fuel swelling data from tubular elements shows apparent effect of geometry (restraint) on both low temperature volume expansion and the temperature at which accelerated … more
Date: May 5, 1964
Creator: Last, G. A.
open access

Increased coolant flow H Reactor: PITA IP-27-I, Part 1. Supplement A

Description: Purpose of this supplement is to increase the maximum allowable liquid level in the near downcomer for single downcomer operation. The required clearance between the downcomer lid and liquid level is reduced from 24 inches to 18 inches in the near downcomer, providing bulk outlet temperature is maintained less than 93 C.
Date: February 5, 1964
Creator: Spicka, R. E.
open access

Operating history

Description: This document provides the Hanford Production Reactors operating histories from January 1, 1961 through November 30, 1969. The raw log sheets are provided.
Date: March 5, 1964
Creator: Newell, L. J.
open access

Post-irradiation measurements of PT-546 fuel elements

Description: Early in December 1963 eighteen natural uranium columns were discharged from C Reactor. Fifteen (15) of these columns contained alternately charged HDS (test) and AlSi (control) fuel elements in the downstream half (positions 1--16); two columns were charged full length with HDS material; and one column was charged full length with AlSi material. All canned pieces were nominally C5NS dimensions except that the HDS pieces were slightly longer than the standard AlSi pieces. Uranium fabrication hi… more
Date: January 5, 1964
Creator: Bloomstrand, R. R.
open access

Status of development work on the hot die size fuel element growth problem

Description: Because of the unexpected growth behavior of hot die size fuel elements during irradiation, it was necessary to re-evaluate the plans for hot die size irradiation testing and redirect the development effort. Tests were initiated to determine the cause of the growth, and plans were made to incorporate findings into subsequent irradiation tests. This report summarizes work done to determine the cause of the unexpected growth and the status of irradiation tests designed to measure improvements in … more
Date: November 5, 1964
Creator: Strand, C. A.
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