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Volume 207

Number 3

Modeling Hydrogen Explosion in Level 1 PSA

Julien Beaucourt, Gabriel Georgescu

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 323-334

Technical Paper / dx.doi.org/10.1080/00295450.2020.1770530

Operator Action–Induced Two-Phase Flow Condition Resulting in Performance Degradation of Interfacing Passive System

Douglas A. Fynan, Jinhee Park

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 335-351

Technical Paper / dx.doi.org/10.1080/00295450.2020.1760704

Extension of a Level 2 PSA Event Tree Based on Results of a Probabilistic Dynamic Safety Analysis of Induced Steam Generator Tube Rupture

Sören Johst, Michael Hage, Jörg Peschke

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 352-362

Technical Paper / dx.doi.org/10.1080/00295450.2020.1766347

Mutual Integration of Classical and Dynamic PRA

Diego Mandelli, Andrea Alfonsi, Congjian Wang, Zhegang Ma, Carlo Parisi, Tunc Aldemir, Curtis Smith, Robert Youngblood

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 363-375

Technical Paper / dx.doi.org/10.1080/00295450.2020.1776030

Dynamic PRA-Based Estimation of PWR Coping Time Using a Surrogate Model for Accident Tolerant Fuel

Robby Christian, Asad Ullah Amin Shah, Hyun Gook Kang

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 376-388

Technical Paper / dx.doi.org/10.1080/00295450.2020.1777035

Dynamic PRA Methods to Evaluate the Impact on Accident Progression of Accident Tolerant Fuels

Diego Mandelli, Carlo Parisi, Nolan Anderson, Zhegang Ma, Hongbin Zhang

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 389-405

Technical Paper / dx.doi.org/10.1080/00295450.2020.1794234

Reevaluating the Current U.S. Nuclear Regulatory Commission’s Safety Goals

Vinod Mubayi, Robert Youngblood

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 406-412

Technical Paper / dx.doi.org/10.1080/00295450.2020.1775452

Technical Evaluation of the Margins Between Established Risk Goals and Health Objectives for Nuclear Power Plants

Fernando Ferrante, Stuart Lewis

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 413-423

Technical Paper / dx.doi.org/10.1080/00295450.2020.1775451

Understanding and Effectively Managing Conservatisms in Safety Analysis of Nonreactor Nuclear Facilities

Mohammad Modarres, Steven Krahn, James O’Brien

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 424-440

Technical Paper / dx.doi.org/10.1080/00295450.2020.1805258

State-of-the-Art Reactor Consequence Analyses Project: Uncertainty Analyses for Station Blackout Scenarios

S. Tina Ghosh, Hossein Esmaili, Alfred Hathaway, Nathan Bixler, Dusty Brooks, Matthew Dennis, Douglas Osborn, Kyle Ross, Kenneth Wagner

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 441-451

Technical Paper / dx.doi.org/10.1080/00295450.2021.1875737

Use of Risk Insights in the Practical Implementation of an Integrated Risk-Informed Decision-Making Framework

Fernando Ferrante, Stuart Lewis, Gareth Parry, Donald Dube, James Chapman

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 452-459

Technical Note / dx.doi.org/10.1080/00295450.2020.1782693

A Novel Approach to Realistic Conservatism in Nuclear Criticality Safety Analysis

Robert B. Hayes

Nuclear Technology / Volume 207 / Number 3 / March 2021 / Pages 460-467

Technical Note / dx.doi.org/10.1080/00295450.2020.1762472

 

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