Resource Type

Analysis of Stresses in Bellows (open access)

Analysis of Stresses in Bellows

Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date: October 15, 1964
Creator: Anderson, W. F.
System: The UNT Digital Library
Metallurgical Aspects of SRE Fuel Element Damage Episode (open access)

Metallurgical Aspects of SRE Fuel Element Damage Episode

Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.
Date: October 15, 1961
Creator: Ballif, J. L.
System: The UNT Digital Library
Corrosion and Activity Transfer in the SRE Primary Sodium System (open access)

Corrosion and Activity Transfer in the SRE Primary Sodium System

Abstract: An evaluation extending over a two-year period was made of primary system sodium and of stainless steel, zirconium, and beryllium specimens exposed in the hot and cold legs of a bypass loop in the primary system of the Sodium Reactor Experiment (SRE).
Date: October 30, 1961
Creator: Johnson, H. E.
System: The UNT Digital Library
Sodium Reactor Experiment Power Expansion Program: Heat Transfer Systems Modifications (open access)

Sodium Reactor Experiment Power Expansion Program: Heat Transfer Systems Modifications

Abstract: Under the Power Expansion Program (PEP), modifications have been made to the Sodium Reactor Experiment (SRE) facility to improve plant reliability and permit an increase in power to 30 Mwt, with a reactor coolant outlet temperature up to 1200°F.
Date: October 9, 1964
Creator: Freede, W. J. & Roberts, J. K.
System: The UNT Digital Library
Evaluation of Coolant Impurity Removal Equipment at the OMRE (open access)

Evaluation of Coolant Impurity Removal Equipment at the OMRE

Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date: October 15, 1964
Creator: Barbour, P. & Davis, W. W.
System: The UNT Digital Library
Radiolysis Products of Polyphenyl Coolants: Part 3, Omre High Boilers (open access)

Radiolysis Products of Polyphenyl Coolants: Part 3, Omre High Boilers

Abstract: The nature of the high boiling radiolysis products of OMRE coolants was studied extensively.
Date: October 15, 1964
Creator: Keen, R. T.; Orr, W. L.; Miller, L. J.; Sullivan, R. J. & Shepard, R. C.
System: The UNT Digital Library
Boiling Studies for Sodium Reactor Safety: Part 2, Pool Boiling and Initial Force Convection Tests and Analyses (open access)

Boiling Studies for Sodium Reactor Safety: Part 2, Pool Boiling and Initial Force Convection Tests and Analyses

Abstract: In fulfillment of the general objective of developing information on two-phase flow required in the safety evaluation of sodium cooled reactors, pool and forced-convection boiling of sodium were studied both experimentally and analytically.
Date: October 15, 1964
Creator: Lurie, H. & Noyes, R. C.
System: The UNT Digital Library
Design of an Experimental Bowable Fuel Element for the SRE (open access)

Design of an Experimental Bowable Fuel Element for the SRE

Abstract: An experimental bowable fuel element was developed to study temperature oscillations in the second core loading of the SRE.
Date: October 15, 1964
Creator: Peckinpaugh, C. L.
System: The UNT Digital Library