10th International Conference on 
Structural Mechanics in Reactor Technology


 

DIVISION S: RESEARCH FOR REGULATORY NEEDS AND
STANDARDS DEVELOPMENT


(The papers with links are those received by the SMiRT 10 Secretariat at the time the Transactions went to press)


S01: US-NRC Mechanical and Electrical Equipment Research

Valve and Piping System Test Results and Effects on Regulatory Standards
Robert Steele, Jr.

Effects of Blowdown Flows on Isolation Valve Operability
Keven G. DeWall
Seismic Qualification of Equipment in Operating Nuclear Power Plants
Tsun-Yung Chang, Newton R. Anderson

S02: Containment Leak Integrity Research

Reduction of BWR Containment Leakage Rate Test Duration
Toshinhiko Kobayashi, Tomomi Satou, Yoshihiro Naruse, Takahiro Konno
Testing to Determine the Leakage Behavior of Inflatable Seals Subject to Severe Accident Loadings
M.B. Parks
Severe Accident Testing of a Personnel Airlock
D.B. Clauss, M.B. Parks, J.T. Julien, S.W. Peters
Review of Public Comments on Proposed Seismic Design Criteria
A.J. Philippacopoulos, S.K. Shaukat, N.C. Chokshi, G. Bagchi

S03: US-NRC Seismic Research

The U.S. Nuclear Regulatory Commission Seismic Safety Research Program
R.M. Kenneally, D.J. Guzy, A.J. Murphy

Comparison Studies of HCLPF Capacities Determined by CDFM and Fragility Analysis Methods
Robert C. Murray
The Proposed Soil-Structure Interaction Licensing Criteria Resolution of USI A-40, "Seismic Design Criteria"
N.C. Chokshi, Syed K. Shaukat, Newton R. Anderson
A Comparative NRC/CEA Research Project on Earthquake Ground Motion on Soil Sites: Overview
A.J. Murphy, Bagher Mohammadioun
Consideration of Seismic Events in Severe Accidents
R.M. Kenneally, N.C. Chokshi,
G. Bagchi, T.Y. Chang, J.T. Chen, D.C. Jeng, G. Kelly, A.J. Murphy, L. Rieter

S04: Piping Research

NRC Piping Design Research
Dan Guzy

Seismic Fragility Pipe Testing
Vincent DeVita
High-Level Seismic Tests of Piping at the HDR
C.A. Kot, M.G. Srinivasan, B.J. Hsieh, J.F. Costello
High Level Vibration Test of Nuclear Power Piping - Overall Plan, Input Motion Development and Analysis
C.H. Hofmayer, J.R. Curreri, Y.J. Park, W.Y. Kato, J.F. Costello, H.T. Tang, S. Kawakami
Seismic Fatigue Evaluation of Rod Hung Systems
S.J. Elder, J.P. Conoscente, B.N. Sumodobila, S.P. Harris

S05: Materials Evaluation Research

Application of Degraded Piping Program Results to Leak-Before-Break and In-Service Flaw Assessment Criteria
G.M. Wilkowski, J. Ahmad, G. Karmer, C.W. Marschall
Development of Acceptance Standards for Flaws Detected by In-Service Inspection of PWR Components
B. Barthelet, J. Heliot, H. Chevanne
Completed Research for Improved Codes and Standards on Steam Generator Tube Inspection and Plugging
R.J. Kurtz, J. Muscara

S06: Materials: Radiation Embrittlement and Inservice Flaw Assessment

Radiation Embrittlement of PWR Vessel Supports
R.D. Cheverton, G.C. Robinson, W.E. Pennell, R.K. Nanstad
Radiation-Induced Temperature Shift of the ASME KIc Curve
R.K. Nanstad, F.M. Haggag, S.K. Iskander
Correlation Between Measured Mechanical and Microphysical Parameters for an Irradiated Pressure Vessel Material
W.B. Waeber, G. Solt, P. Tipping, F. Frisius, O.M. Mercier

 

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