MICHAEL CORRADINI
University of Wisconsin-Madison
H-index: 40
North America-United States
Top articles of MICHAEL CORRADINI
Title | Journal | Author(s) | Publication Date |
|---|---|---|---|
Progress in Fast Modular Reactor Conceptual Design | Nuclear Technology | Hangbok Choi John Bolin Oscar Gutierrez Radu Curiac Mohammad Alavi | 2024/4/7 |
Fuel performance analysis of Cr-coated Zircaloy-4 cladding during a prototypical LOCA event using BISON | Annals of Nuclear Energy | Cole Dunbar WooHyun Jung Robert Armstrong Kumar Sridharan Michael Corradini | 2024/6/1 |
US Efforts in Support of Examinations at Fukushima Daiichi-November 2022 Meeting Notes and Information Request Status | L Albright S Basu R Bunt M Cibula M Corradini | 2023/4/1 | |
MELCOR Model Development of the General Atomics Fast Modular Reactor | Cole Dunbar Jun Wang WooHyun Jung Michael Corradini | 2022/6/12 | |
Project Overview of Thermal-Hydraulic and Mechanical Behavior of Near-term ATF Design in Reflood Conditions | Transactions of the American Nuclear Society | Woo Hyun Jung Cole Dunbar Michael Corradini Kumar Sridharan David Kamerman | 2022 |
Analysis of Flow Instability Onset in a BWR Rod Bundle Geometry | P Hurley Y Liu JP Duarte M Corradini T Kozlowski | 2022/6 | |
Effect of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout | Nuclear Engineering and Design | Zehua Guo Ryan Dailey Yukun Zhou Zhongning Sun Jun Wang | 2021/2/1 |
Critical Heat Flux Studies for Innovative Accident Tolerant Fuel Cladding Surfaces | Michael Corradini Hwasung Yeom Kumar Sridharan | 2021/11/9 | |
Accident tolerant fuels (FeCrAl Cladding & Coating) performance analysis in Boiling Water Reactor (BWR) by the MELCOR 1.8. 6 UDGC | Nuclear Engineering and Design | Jun Wang Ryan Dailey Zhehua Guo Yukun Zhou Paul Humrickhouse | 2021 |
Uncertainty analysis of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout | Reliability Engineering & System Safety | Zehua Guo Ryan Dailey Tangtao Feng Yukun Zhou Zhongning Sun | 2021/9/1 |
3D-2D coupling multi-dimension simulation for the heat pipe micro-reactor by MOOSE&SAM | Yukun Zhou Jun Wang Zehua Guo Yanan He Yapei Zhang | 2021/8/1 | |
An analysis of air-water flow phenomena due to a pipe break under sub-atmospheric pressures using TRACE | Nuclear Engineering and Design | Kyoungwoo Seo Inguk Kim Ki-Jung Park Minkyu Jung Hyungi Yoon | 2021/4/1 |
Transient safety evaluation of the heat pipe microreactor–Potential energy source for hydrogen production | International Journal of Hydrogen Energy | Jun Wang Justin A Apresa Matthew Weathered Alejandro Perez Michael Corradini | 2021/11/11 |
An Experimental Study of Design and Performance for the Water-Based Reactor Cavity Cooling System | Rodolfo Vaghetto Yassin Hassan Mark Anderson Michael Corradini | 2020/7/13 | |
Quantification of the effect of Cr-coated-Zircaloy cladding during a short term station black out | Nuclear Engineering and Design | Tangtao Feng Jun Wang Yimin Zhou Ping Song Mingjun Wang | 2020/7/1 |
Direct Containment Heating | Michael L Corradini | 2020/12/17 | |
Effectiveness of Cr-coated Zr-alloy clad in delaying fuel degradation for a PWR during a station blackout event | Nuclear Technology | J Wang H Yeom P Humrickhouse K Sridharan M Corradini | 2020/8/22 |
US Effort Support to Examinations at Fukushima-Meeting Notes with Updated Information Requests (FY2020) | Nathan Andrews Sudamay Basu Randy Bunt Michael L Corradini Phil G Ellison | 2020/1/31 | |
Full-scale dryout/rewet instability tests in a BWR rod bundle and TRACE assessment | Nuclear Engineering and Design | JP Duarte P Yarsky T Zaki ML Corradini | 2020/12/15 |
US Department of Energy Severe Accident Research in the Areas of In-Vessel Core Melt Progression and Ex-Vessel Debris Coolability | MT Farmer M Corradini RO Gauntt | 2020 |
