Results 81 to 90 of about 1,365 (205)

MELCOR 1.8.1 calculations of ISP31: The CORA-13 experiment

, 1993
The MELCOR code was used to simulate one of GRS`s (a reactor research group in Germany) core degradation experiments conducted in the CORA out-of-pile test facility.
Martinez, G. M., Thompson, S. L., Gross, R. J.   +2 more
core   +1 more source

Implementation of patient-reported outcome measures and patient-reported experience measures in melanoma clinical quality registries: a systematic review. [PDF]

BMJ Open, 2021
Blood Z, Tran A, Caleo L, Saw R, Dieng M, Shackleton M, Soyer HP, Arnold C, Mann GJ, Morton RL.   +9 more
europepmc   +1 more source

MELCOR 1.8.2 Assessment: IET direct containment heating tests

, 1993
MELCOR is a fully integrated, engineering-level computer code, being developed at Sandia National Laboratories for the USNRC, that models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRS.
Kmetyk, L. N.
core   +1 more source

Distinctive physical insights driven from machine learning modelling of nuclear power plant severe accident scenario propagation. [PDF]

Sci Rep, 2023
Hossny K, Villanueva W, Wang HD.
europepmc   +1 more source

Influence of Concrete Properties on Molten Core-Concrete Interaction: A Simulation Study

Advances in Materials Science and Engineering, 2016
In a severe nuclear power plant accident, the molten core can be released into the reactor pit and interact with sacrificial concrete. In this paper, a simulation study is presented that aims to address the influence of sacrificial concrete properties on
Jin-yang Jiang, Ying-jun Yu, Hong-yan Chu, Wei Sun, Yun Gao   +4 more
doaj   +1 more source

MELCOR 1.8.2 assessment: The DF-4 BWR Damaged Fuel experiment

, 1993
MELCOR is a fully integrated, engineering-level computer code being developed at Sandia National Laboratories for the USNRC, that models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRs.
Tautges, T. J.
core   +1 more source

Station Black-Out Analysis with MELCOR 1.8.6 Code for Atucha 2 Nuclear Power Plant

Science and Technology of Nuclear Installations, 2012
A description of the results for a Station Black-Out analysis for Atucha 2 Nuclear Power Plant is presented here. Calculations were performed with MELCOR 1.8.6 YV3165 Code.
Analia Bonelli, Oscar Mazzantini, Martin Sonnenkalb, Marcelo Caputo, Juan Matias García, Pablo Zanocco, Marcelo Gimenez   +6 more
doaj   +1 more source

Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor

Nuclear Engineering and Technology, 2016
Hydrogen release during severe accidents poses a serious threat to containment integrity. Mitigating procedures are necessary to prevent global or local explosions, especially in large steel shell containments.
Mehdi Dehjourian, Reza Sayareh, Mohammad Rahgoshay, Gholamreza Jahanfarnia, Amir Saied Shirani   +4 more
doaj   +1 more source

Effect of Stabilized Martensite on the Long-Term Performance of Superelastic NiTi Endodontic Files. [PDF]

Materials (Basel), 2023
Sánchez P, Vidi B, Mena-Alvarez J, Gil J, Rico C, Aragoneses JM.   +5 more
europepmc   +1 more source

ITER Water Cooled Lithium Lead Test Blanket System transient thermal-hydraulic analysis

Nuclear Fusion
The planned experimental activities of the ITER Test Blanket Module (TBM) program will be a key step in understanding the physics and technologies required for tritium breeding blankets, which are essential for achieving tritium self-sufficiency in a ...
Tommaso Glingler, Gianfranco Caruso, Danilo Nicola Dongiovanni, Salvatore D’Amico, Italo Ricapito, Paul Wouters, Francesca Fantini, Joelle Elbez-Uzan, Sandrine Rosanvallon, Matteo D’Onorio   +9 more
doaj   +1 more source