9 Matching Results

Search Results

Advanced search parameters have been applied.
in creator/contributor: "McLaughlin, D. W."  
Results: 1 - 9
open access

Pattern Selection and Competition in Near-Integrable Systems

Description: Pattern selection and competition in certain near-integrable systems are discussed. These systems provide models for controlled studies of low dimensional attractors in high (infinite) dimensional systems. Four examples from damped, driven pendulum rings are summarized in the order of increasing spatial complexity of their chaotic attractors. These examples illustrate the use of numerical and analytical techniques from soliton mathematics to study properties of chaotic attractors. In particular… more
Date: January 1, 1986
Creator: Bishop, A. R. & McLaughlin, D. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Design Criteria for Irradiated Vessels Task 6.0 Summary Report

Description: Abstract: This technical report presents design criteria to prevent the brittle fracture of ferritic reactor vessels that cold occur as a result of the rise in NDT caused by fast neutron irradiation. The criteria require that maximum principal stress in the vessel does not exceed 18 percent of yield stress at temperatures below NDT + 60 degree F. Under certain conditions the allowable stress may be based on the irradiated yield stress. A discussion of brittle fracture and an explanation of the … more
Date: September 29, 1961
Creator: McLaughlin, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effect of Radiation Damage on SM-1, SM-1A and PM-2A Reactor Vessels

Description: Report describing the status of the SM-1, SM-1A, and PM-2A reactors, specifically regarding the effects "of irradiation on nil-ductility transition temperature and the associated problem of brittle fracture." (p. iii)
Date: October 14, 1961
Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A.; Coombe, J. R.; Kelleman, R. W.; Bobe, P. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Stress Analysis of the SM-1A Reactor Vessel

Description: This report presents the stress analysis performed on the SM-1A reactor vessel and cover as part of the Program for Engineering Support and Development of Army Pressurized Water Reactor Power Plants.
Date: unknown
Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A. & Aitken, C. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Stress and Fatigue Analysis of the SM-1 Primary System

Description: A preliminary analysis of the SM-1 primary system showed it-was safe from strain cycling damage with the possible exception of steam generator tube sheet and primary pump casing. These are recommended for further analysis. (auth)
Date: March 31, 1962
Creator: Chittum, R. A.; Knipe, R. K. & McLaughlin, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Stress Analysis of the SM-1A Reactor Vessel

Description: The stress analysis performed on the SM-lA reactor vessel and cover is presented. The msximum combined stress (51,360 psi in compression) occurs in the vessel cover during a 50 deg F/hr transient. A fatigue analysis of these stresses indicated that they could be applied safely at least 2500 times, and since the vessel is expected to receive less than 900 cycles, it should not suffer any fatigue damage. (auth)
Date: March 30, 1962
Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A. & Aitken, C. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Stress Analysis of the PM-2A Reactor Vessel

Description: The stress analysis performed on the PM-2A reactor vessel and cover is discussed. The maximum combined stress (51,000 psi) occurred in the studs after reaching steady-state conditions. A fatigue analysis indicated that this stress could be safely applied 2500 times, and since the studs do not approach 2500 cycles from initial stud tightening to steady-state conditions, they should not suffer any fatigue damage. (auth)
Date: May 14, 1962
Creator: Rowekamp, B. J.; McLaughlin, D. W.; Chittum, R. A. & Aitken, C. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen