Research Catalog

Title

Severe accidents and other topics in the RPV design, 2000 : presented at the 2000 ASME Pressure Vessels and Piping Conference, Seattle, Washington, July 23-27, 2000 / sponsored by the Pressure Vessels and Piping Division ; principal editor, Surender Bhandari ; contributing editors, Kenneth K. Yoon, Dominique Moinereau.

Publication

New York : American Society of Mechanical Engineers, ©2000.

Items in the Library & Off-site

Details

Additional Authors

• Bhandari, Surender.
• Yoon, K. K. (Kenneth K.)
• Moinereau, Dominique.
• American Society of Mechanical Engineers. Pressure Vessels and Piping Division.
• Pressure Vessels and Piping Conference (2000 : Seattle, Wash.)

Description

vi, 233 pages : illustrations; 28 cm.

Series Statement

PVP ; vol. 403

Uniform Title

PVP (Series) ; vol. 403.

Subject

• Nuclear pressure vessels > Accidents > Congresses
• Nuclear pressure vessels > Evaluation > Congresses
• Nuclear pressure vessels > Reliability > Congresses
• Nuclear pressure vessels > Accidents
• Nuclear pressure vessels > Evaluation
• Nuclear pressure vessels > Reliability

Genre/Form

Conference papers and proceedings.

Bibliography (note)

• Includes bibliographical references and index.

Contents

• Reactor Pressure Vessel Under Accident and Severe Accident Conditions -- Introduction / Surender Bhandari, S. K. Gupta -- EU Research on Severe Accidents: Achievements of FP-4 and Prospects for FP-5 / A. Zurita, G. Van Goethem -- RUPTHER 18: Failure of a Notched Tube Under Axial Thermal Gradient and Internal Pressure Loading / L. Le Ber, P. Mongabure, L. Nicolas, S. Bhandari, C. Messelier-Gouze -- Analysis of Possibility of Pressure Tube Cold Pressurisation During ECCS Injection for a Small Break LOCA / D. Mukhopadhyay, S. K. Gupta, V. Venkat Raj -- Analysis of the Thermal Hydraulic Consequences Following Common Mode Pump Seizure in a Nuclear Power Plant / B. Chatterjee, S. K. Gupta, H. S. Kushwaha, V. Venkat Raj -- Comparison of the Predictions Relying on Coupled/Uncoupled Damage-Viscoplasticity Models for Creep Tests Analyses / L. Nicolas, P. Mongabure, L. Le Ber, J. Devos, S. Bhandari, C. Messelier-Gouze -- Thermal Analysis of Severe Channel Damage Caused by a Stagnation Channel Break in a PHWR / D. Mukhopadhyay, P. Majumdar, G. Behera, S. K. Gupta, V. Venkat Raj -- Mechanical Consequences of Pump Shaft Seizure in a Nuclear Power Plant / B. Chatterjee, S. K. Gupta, H.S. Kushwaha, V. Venkat Raj -- Severe Channel Damage Assessment for a Loss of Coolant Accident in a 220 MWe Pressurised Heavy Water Reactor / G. Sreenivas Rao, H. G. Lele, S. K. Gupta, V. Venkat Raj -- Effect of Reactor Internals on Structural Integrity Assessment of PFBR Main Vessel Under CDA / P. Chellapandi, S. C. Chetal, S. B. Bhoje.
• Reactor Pressure Vessel Assessments: Deterministic Approach -- Introduction / Surender Bhandari, Dominique Moinereau, Kenneth K. Yoon -- PWR Vessel Integrity and Life Management in French Nuclear Plants / G. Bezdikian, D. Moinereau, F. Champigny, C. Faidy -- Elastic-Plastic Finite Element Analyses for the Integrity Evaluation of Nuclear Reactor Vessel Under Pressurized Thermal Shock Transients / S. M. Lee, J. B. Choi, Y. J. Kim, Y. W. Park, M. J. Jhung, C. R. Pyo -- EDF/MPA Collaborative Program on WPS Effect: Experimental Results / G. Barbier, U. Eisele, W. Lefevre -- Evaluation of Pressurised Thermal Shock in a Reactor Pressure Vessel for the Case of Emergency Coolant Injection / H. G. Lele, S. K. Gupta, H. S. Kushwaha, V. Venkat Raj -- Application of Statistically-based KIC/KIA Fracture Toughness Models to PTS Assessments of Reactor Pressure Vessels / B. R. Bass, T. L. Dickson, P. T. Williams -- Three-Dimensional Assessment of Flaws in a French PWR Vessel Submitted to a Severe Overcooling Transient: the Effect of Cladding in a PTS Analysis / D. Moinereau, G. Bezdikian, C. Faidy -- Reactor Pressure Vessel Assessments: Probabilistic and General Aspects -- Introduction / Surender Bhandari, Dominique Moinereau, Kenneth K. Yoon -- A Probabilistic Fracture Mechanics Analysis for PTS Evaluation of Kori Unit 1 RPV / S. G. Jung, H. S. Kim, T. E. Jin, C. H. Jang, I. S. Jeong.
• Deterministic and Probabilistic Assessments of the Reactor Pressure Vessel Structural Integrity with a User-friendly Software / M. Persoz, S. Hugonnard-Bruyere, V. Venturini, E. Meister -- Validation of a Linear-Elastic Fracture Methodology for Postulated Flaws Embedded in the Wall of a Nuclear Reactor Pressure Vessel / T. L. Dickson, B. R. Bass, P. T. Williams -- The Effect of Reference Flaw Sizes on the P-T Limit Curves for Pressurized Water Reactors / C. H. Jang, I. S. Jeong, J. H. Park -- LBB Investigation of PFBR Steam Generator / P. Chellapandi, S. C. Chetal, S. B. Bhoje -- Analysis of the Influence of the Loading Applied During the Cooling Phase of WPS Tests / M. P. Valeta, C. Sainte-Catherine, G. Barbier, W. Lefevre, S. Bhandari -- Evaluation of RTNDT Toughness Determination Methodology Using a New Approach / C. Brillaud, S. Saillet, Y. Grandjean, B. Houssin -- Role of Cladding in Rpv Safety Analyses -- Introduction / Surender Bhandari -- Overview of the Role of Cladding in RPV Safety Analyses / D. Lidbury, S. Bhandari, M. Bieth, E. Keim, J. Sharples -- State-of-the-Art Review of Cladding Material Data / J. K. Sharples, D. P. G. Lidbury, M. G. Horsten, R. Pelli -- Evaluation of Manufacturing and Inspection Program on RPV Cladding / E. Keim, E. Capurro, A. Popov -- Evaluation of Inspection Procedures for the Cladding Zone of the Pressure Vessel / M. Bieth, L. Fabbri, J. L. Monjaret, R. Martinez-Ona, C. Cueto-Felgueroso, A. Popov.
• Evaluation of the Potential Role of Cladding in RPV Safety Analyses / S. Bhandari, C. Cueto-Felgueroso, H. Grebner, M. Horsten, E. Keim, R. Pelli, A. Popov, J. Sievers.

ISBN

• 0791818845
• 9780791818848

LCCN

00710285

OCLC

• ocm44872998
• 44872998
• SCSB-9318131

Owning Institutions

Princeton University Library