Results 101 to 110 of about 1,365 (205)
This report documents the results from MELCOR calculations of the Long-Term Station Blackout Accident Sequence, with failure to depressurize the reactor vessel, at the Peach Bottom (BWR Mark I) plant, and presents comparisons with Source Term Code ...
Madni, I. K.
core +1 more source
Metal ion-regulated assembly of designed modular protein cages. [PDF]
Aupič J +5 more
europepmc +1 more source
Progress in MELCOR development and assessment
MELCOR models the progression of severe accidents in light water reactor nuclear power plants. Recent efforts in MELCOR development to incorporate CORCON-Mod3 models for core-concrete interactions, new models for advanced reactors, and improvements to ...
Smith, R. C. +6 more
core
Uncertainty and sensitivity analysis for small PWR station blackout accidents
Based on the ASTRUM method, an uncertainty analysis of hydrogen production and severe accident process under severe accident conditions of small pressurized water reactors was conducted with respect to the input parameters.
Youwu Xu, Yuqing Chen, Qin Hao, Wei Wang
doaj +1 more source
Development of NPP Krško Model for MELCOR Code
U radu se modelira nuklearna elektrana Krško u programu MELCOR, opisuju se podaci i vrši se proračun akcidenta gubitka izmjeničnog napajanja. Rezultati se uspoređuju s referentnim rezultatima modela elektrane u programu MAAP. Analizira se odziv elekrane
Rep, Ivan
core
Quantitative Model for Reversibly Photoswitchable Sensors. [PDF]
Adelizzi B +4 more
europepmc +1 more source
MELCOR 1.8.1 assessment: PNL Ice Condenser Aerosol Experiments
The MELCOR code was used to simulate PNL`s Ice Condenser Experiments 11-6 and 16-11. In these experiments, ZnS was injected into a mixing chamber, and the combined steam/air/aerosol mixture flowed into an ice condenser which was l4.7m tall. Experiment 11-
Gross, R. J.
core +1 more source
Designed folding pathway of modular coiled-coil-based proteins. [PDF]
Aupič J +7 more
europepmc +1 more source
Independent assessment of MELCOR as a severe accident thermal-hydraulic/source term analysis tool
MELCOR is a fully integrated computer code that models all phases of the progression of severe accidents in light water reactor nuclear power plants, and is being developed for the US Nuclear Regulatory Commission (NRC) by Sandia National Laboratories ...
Eltawila, F., Madni, I. K.
core
A MELCOR model of Fukushima Daiichi Unit 3 accident
A MELCOR model of the Fukushima Daiichi Unit 3 accident was developed. The model is based on publicly available information, and the MELCOR input file is published as electronic supplementary data with this paper.
Sevón, Tuomo; id_orcid
core +1 more source

