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MELCOR computer code manuals

https://doi.org/10.2172/50939
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What this work says

Outgoing claims: the papers this work cites, builds on, or argues with.

inferredcites →https://doi.org/10.1016/s0029-5493(01)00400-9openalex-snapshot
Applicability of Phebus FP results to severe accident safety evaluations and management measures
inferredcites →https://doi.org/10.1201/9780429294532-23openalex-snapshot
TABLE 8.1
inferredcites →https://doi.org/10.1201/9781482286779-12openalex-snapshot
REVIEW OF B9+ BENCHMARK RESULTS
inferredcites →https://doi.org/10.13182/nt89-a27696openalex-snapshot
MELCOR Analysis of the Three Mile Island Unit 2 Accident
inferredcites →https://doi.org/10.2172/28419openalex-snapshot
TMI-2 analysis using SCDAP/RELAP5/MOD3.1
inferredcites →https://doi.org/10.2172/604326openalex-snapshot
CONTAIN assessment of the NUPEC mixing experiments. Supplement 1
inferredcites →https://doi.org/10.2172/95189openalex-snapshot
CONTAIN assessment of the NUPEC mixing experiments

What points at this work

Incoming claims: where this work appears in other papers’ reference lists and arguments.

inferred← citeshttps://doi.org/10.2139/ssrn.4570921openalex-extracted
inferred← citeshttps://doi.org/10.2139/ssrn.4717866openalex-extracted
Retention Analysis of Aerosol Inside Narrow Channels of the Containment
inferred← citeshttps://doi.org/10.1002/9781118043462.ch10openalex-snapshot
PRA STUDIES OF NUCLEAR POWER PLANTS
inferred← citeshttps://doi.org/10.1002/zamm.20010811539openalex-snapshot
Numerical simulation of large scale hydrogen explosions in complex geometries
inferred← citeshttps://doi.org/10.1007/0-306-47811-0_7openalex-snapshot
Current Status of Core Degradation and Melt Progression in Severe LWR Accidents
inferred← citeshttps://doi.org/10.1007/978-0-85729-410-4_48openalex-snapshot
Level 2 PSA for the VVER 440/213 Dukovany Nuclear Power Plant
inferred← citeshttps://doi.org/10.1007/978-3-642-11990-3_11openalex-snapshot
Safety and Risk of Light Water Reactors and their Fuel Cycle Facilities
inferred← citeshttps://doi.org/10.1007/978-3-642-28381-9_9openalex-snapshot
Bewertung der Risikostudien und verbessertes (neues) Sicherheitskonzept für LWRs
inferred← citeshttps://doi.org/10.1007/978-3-642-55116-1_10openalex-snapshot
Assessment of Risk Studies and Severe Nuclear Accidents
inferred← citeshttps://doi.org/10.1007/s42967-021-00157-yopenalex-snapshot
Multi-dimensional Simulation of Phase Change by a 0D-2D Model Coupling via Stefan Condition
inferred← citeshttps://doi.org/10.1016/b978-0-08-056033-5.00048-3openalex-snapshot
Core Concrete Interaction
inferred← citeshttps://doi.org/10.1016/b978-0-12-803581-8.11727-8openalex-snapshot
Molten Core Concrete Interaction
inferred← citeshttps://doi.org/10.1016/b978-0-12-818190-4.00017-6openalex-snapshot
Engineering-level system code for severe accident analysis: MELCOR
inferred← citeshttps://doi.org/10.1016/b978-0-323-91152-8.00017-xopenalex-snapshot
Dynamic probabilistic risk assessment (PRA): Theory, tools, and applications for uncertainty quantification
inferred← citeshttps://doi.org/10.1016/b978-008042835-2/50028-xopenalex-snapshot
ADAM
inferred← citeshttps://doi.org/10.1016/j.anucene.2012.08.001openalex-snapshot
A survey of dynamic methodologies for probabilistic safety assessment of nuclear power plants
inferred← citeshttps://doi.org/10.1016/j.anucene.2013.03.025openalex-snapshot
Applications of results from the Phébus-FP programme in the US regulatory process
inferred← citeshttps://doi.org/10.1016/j.anucene.2013.04.019openalex-snapshot
Analysis of hydrogen control in severe accidents of CANDU6
inferred← citeshttps://doi.org/10.1016/j.anucene.2015.11.024openalex-snapshot
Severe accident analysis of plant-specific spent fuel pool to support a SFP risk and accident management
inferred← citeshttps://doi.org/10.1016/j.anucene.2017.01.009openalex-snapshot
Numerical simulation of MCCI based on MPS method with different types of concrete
inferred← citeshttps://doi.org/10.1016/j.anucene.2018.12.029openalex-snapshot
Effects of the operating strategies of filtered containment venting system on Cesium-137 releases during severe accidents
inferred← citeshttps://doi.org/10.1016/j.anucene.2019.02.013openalex-snapshot
Optimization of hydrogen mitigation systems in CPR1000 during a refueling outage
inferred← citeshttps://doi.org/10.1016/j.anucene.2019.107205openalex-snapshot
Analysis of loss of cooling and loss of coolant severe accident scenarios in VVER-1000/V446 spent fuel pool
inferred← citeshttps://doi.org/10.1016/j.anucene.2020.107525openalex-snapshot
Three-dimensional numerical study on the effect of sidewall crust thermal resistance on transient MCCI by improved MPS method
inferred← citeshttps://doi.org/10.1016/j.anucene.2020.107626openalex-snapshot
An online operator support tool for severe accident management in nuclear power plants using dynamic event trees and deep learning
inferred← citeshttps://doi.org/10.1016/j.anucene.2020.108018openalex-snapshot
Application of a severe accident code to the sensitivity and uncertainty analysis of hydrogen production in the WWER1000/V446
inferred← citeshttps://doi.org/10.1016/j.anucene.2023.109747openalex-snapshot
Research on the Performance Enhancement of Accident Tolerant Fuel for Eliminating Core Melting Based on Isaa
inferred← citeshttps://doi.org/10.1016/j.anucene.2023.110207openalex-snapshot
Investigation of aerosol transportation phenomena in pool scrubbing by combining bubble plume measurements and single-bubble mass transfer analysis
inferred← citeshttps://doi.org/10.1016/j.anucene.2025.111187openalex-snapshot
Applicability analysis of passive containment heat remove system calculation model based on integrated code
inferred← citeshttps://doi.org/10.1016/j.energy.2018.05.123openalex-snapshot
Safety research of IVR-ERVC for advanced water cooled reactor
inferred← citeshttps://doi.org/10.1016/j.fusengdes.2016.01.041openalex-snapshot
Recent development and application of a new safety analysis code for fusion reactors
inferred← citeshttps://doi.org/10.1016/j.fusengdes.2020.111906openalex-snapshot
Application of virtual reality technology in nuclear device design and research
inferred← citeshttps://doi.org/10.1016/j.fusengdes.2021.112713openalex-snapshot
Hydrogen explosion mitigation in DEMO vacuum vessel pressure suppression system using passive recombiners
inferred← citeshttps://doi.org/10.1016/j.fusengdes.2022.113095openalex-snapshot
Development of an object-oriented, thermal-hydraulics model for ARC FLiBe loop safety assessment
inferred← citeshttps://doi.org/10.1016/j.ijmultiphaseflow.2017.01.013openalex-snapshot
Drift-flux model for upward two-phase cross-flow in horizontal tube bundles
inferred← citeshttps://doi.org/10.1016/j.ijpvp.2003.08.001openalex-snapshot
Experimental models of medium break loss of coolant accidents with and without steam generator tube rupture
inferred← citeshttps://doi.org/10.1016/j.jaerosci.2021.105800openalex-snapshot
An improved sectional model to simulate multi-component aerosol dynamics in a containment of pressurized water reactor
inferred← citeshttps://doi.org/10.1016/j.jenvrad.2019.03.024openalex-snapshot
Tellurium behaviour in the Fukushima Dai-ichi Nuclear Power Plant accident
inferred← citeshttps://doi.org/10.1016/j.jenvrad.2020.106356openalex-snapshot
Uncertainties in atmospheric dispersion modelling during nuclear accidents
inferred← citeshttps://doi.org/10.1016/j.net.2015.06.016openalex-snapshot
Raim – A model for iodine behavior in containment under severe accident condition
inferred← citeshttps://doi.org/10.1016/j.net.2019.04.017openalex-snapshot
System dynamics simulation of the thermal dynamic processes in nuclear power plants
inferred← citeshttps://doi.org/10.1016/j.net.2019.05.005openalex-snapshot
A flammability limit model for hydrogen-air-diluent mixtures based on heat transfer characteristics in flame propagation
inferred← citeshttps://doi.org/10.1016/j.net.2020.07.040openalex-snapshot
Improved prediction model for H2/CO combustion risk using a calculated non-adiabatic flame temperature model
inferred← citeshttps://doi.org/10.1016/j.net.2021.02.028openalex-snapshot
Research on rapid source term estimation in nuclear accident emergency decision for pressurized water reactor based on Bayesian network
inferred← citeshttps://doi.org/10.1016/j.net.2021.06.039openalex-snapshot
CSPACE for a simulation of core damage progression during severe accidents
inferred← citeshttps://doi.org/10.1016/j.net.2021.10.001openalex-snapshot
Interfacing between MAAP and MACCS to perform radiological consequence analysis
inferred← citeshttps://doi.org/10.1016/j.net.2022.09.001openalex-snapshot
Assessment of the core-catcher in the VVER-1000 reactor containment under various severe accidents
inferred← citeshttps://doi.org/10.1016/j.net.2023.08.021openalex-snapshot
PASTELS project - overall progress of the project on experimental and numerical activities on passive safety systems
inferred← citeshttps://doi.org/10.1016/j.net.2023.11.025openalex-snapshot
Strategic analysis on sizing of flooding valve for successful accident management of small modular reactor
inferred← citeshttps://doi.org/10.1016/j.net.2023.12.005openalex-snapshot
Performance evaluation of an improved pool scrubbing system for thermally-induced steam generator tube rupture accident in OPR1000
inferred← citeshttps://doi.org/10.1016/j.net.2024.04.018openalex-snapshot
ACE surrogate Model–Based uncertainty and sensitivity analysis methods for severe accident codes
inferred← citeshttps://doi.org/10.1016/j.nme.2016.08.010openalex-snapshot
Safety insights from forensics evaluations at Daiichi
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2006.04.030openalex-snapshot
Considerations on ex-vessel corium behavior: Scenarios, MCCI and coolability
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2006.08.002openalex-snapshot
A detailed chemistry model for transient hydrogen and carbon monoxide catalytic recombination on parallel flat Pt surfaces implemented in an integral code
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2006.09.002openalex-snapshot
Improvements in a CFD code for analysis of hydrogen behaviour within containments
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2008.06.012openalex-snapshot
VVER-1000/V320 decay heat analysis involving TVS-M and TVSA fuel assemblies
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2009.11.029openalex-snapshot
An approach to numerical simulation and analysis of molten corium coolability in a boiling water reactor lower head
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2010.02.006openalex-snapshot
Accident management following loss-of-coolant accidents during cooldown in a Westinghouse two-loop PWR
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2013.08.022openalex-snapshot
Sensitivity study on severe accident core melt progression for advanced PWR using MELCOR code
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2014.03.011openalex-snapshot
Post-test calculation of the QUENCH-17 bundle experiment with debris formation and bottom water reflood using thermal hydraulic and severe fuel damage code SOCRAT/V3
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2015.02.021openalex-snapshot
CFD simulations in the nuclear containment using the DES turbulence models
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2015.09.031openalex-snapshot
Influence of the wet-well nodalization of a BWR3 Mark I on the containment thermal-hydraulic response during an SBO accident
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2015.12.033openalex-snapshot
Three-dimensional all-speed CFD code for safety analysis of nuclear reactor containment: Status of GASFLOW parallelization, model development, validation and application
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2016.02.040openalex-snapshot
Numerical simulation of 2D ablation profile in CCI-2 experiment by moving particle semi-implicit method
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2017.05.030openalex-snapshot
Core degradation simulation of the PHEBUS FPT3 experiment using COMPASS code
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2018.05.001openalex-snapshot
Development of a multi-compartment containment code for advanced PWR plant
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2018.09.022openalex-snapshot
Validation of the MELCOR input model for a CANDU PHWR containment analysis by benchmarking against integrated leakage rate tests
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2019.04.006openalex-snapshot
CTF-R: A novel residual-based thermal hydraulic solver
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2020.110678openalex-snapshot
Quantification of the effect of Cr-coated-Zircaloy cladding during a short term station black out
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2020.110965openalex-snapshot
40th Anniversary of the first international topical meeting on nuclear reactor thermal-hydraulics: Highlights of thermal-hydraulics research in the past four decades
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2021.111061openalex-snapshot
Development of severe accident mitigation technology and analysis for SMART
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2021.111370openalex-snapshot
High-temperature creep deformation evaluation in CANDU pressure tubes under a station black-out
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2023.112231openalex-snapshot
Investigation on the effect of polydisperse spray droplets distribution on aerosol particles removal efficiency
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2023.112562openalex-snapshot
Investigating the effect of spray system on the containment condition of VVER1000/V446 NPP during LBLOCA and TLOFW accidents
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2023.112895openalex-snapshot
Effectiveness re-evaluation on the intentional primary system depressurization during Zion-like Westinghouse PWR station blackout considering pressure dependence of radionuclides release
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2025.113925openalex-snapshot
Maximizing accuracy in severe accident simulations: An In-depth analysis of sampling methods for MELCOR code during station black-out in WWER-1000
inferred← citeshttps://doi.org/10.1016/j.nucengdes.2026.114771openalex-snapshot
Experimental study of decontamination factor in pool scrubbing with two-phase flow evolution
inferred← citeshttps://doi.org/10.1016/j.pnucene.2004.09.017openalex-snapshot
Implementation of a database management system for the comprehensive use of severe accident risk information
inferred← citeshttps://doi.org/10.1016/j.pnucene.2007.06.002openalex-snapshot
Review of research on flow instabilities in natural circulation boiling systems
inferred← citeshttps://doi.org/10.1016/j.pnucene.2009.06.007openalex-snapshot
The effective convectivity model for simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part I: Physical processes, modeling and model implementation
inferred← citeshttps://doi.org/10.1016/j.pnucene.2009.09.016openalex-snapshot
Simulation of corium concrete interaction in 2D geometry
inferred← citeshttps://doi.org/10.1016/j.pnucene.2013.03.002openalex-snapshot
Comparison of LWR and SFR in-containment source term: Similarities and differences
inferred← citeshttps://doi.org/10.1016/j.pnucene.2013.12.002openalex-snapshot
Revising the Emergency Management Requirements for new generation reactors
inferred← citeshttps://doi.org/10.1016/j.pnucene.2015.06.002openalex-snapshot
Gas-cooled reactor thermal hydraulic analyses with MELCOR
inferred← citeshttps://doi.org/10.1016/j.pnucene.2015.11.005openalex-snapshot
A new method to study the transient feasibility of IVR-ERVC strategy
inferred← citeshttps://doi.org/10.1016/j.pnucene.2016.01.005openalex-snapshot
Considerations for severe accident management under extended station blackout conditions in nuclear power plants
inferred← citeshttps://doi.org/10.1016/j.pnucene.2017.05.021openalex-snapshot
Impact of probabilistic risk assessment and severe accident research in reducing reactor risk
inferred← citeshttps://doi.org/10.1016/j.pnucene.2017.06.003openalex-snapshot
MELCOR severe accident analysis for a natural circulation small modular reactor
inferred← citeshttps://doi.org/10.1016/j.pnucene.2018.03.004openalex-snapshot
Analysis of Design Extension Conditions in a heavy water research reactor
inferred← citeshttps://doi.org/10.1016/j.pnucene.2018.11.004openalex-snapshot
Spatial temperature distribution of fuel assembly pre-simulation for a new simple core degradation experiment
inferred← citeshttps://doi.org/10.1016/j.pnucene.2019.01.002openalex-snapshot
Safety analysis of a small modular reactor using fully ceramic micro-encapsulated fuel
inferred← citeshttps://doi.org/10.1016/j.pnucene.2019.03.019openalex-snapshot
A sensitivity study on cut frequency of FFTBM for quantitative assessment of thermal-hydraulic modeling by MELCOR code
inferred← citeshttps://doi.org/10.1016/j.pnucene.2019.03.042openalex-snapshot
Analysis of hydrogen risk and its mitigation systems in CPR1000 during shutdown conditions
inferred← citeshttps://doi.org/10.1016/j.pnucene.2019.103140openalex-snapshot
Machine-learning based error prediction approach for coarse-grid Computational Fluid Dynamics (CG-CFD)
inferred← citeshttps://doi.org/10.1016/j.pnucene.2020.103370openalex-snapshot
Study the effects of various parameters on hydrogen production in the WWER1000/V446
inferred← citeshttps://doi.org/10.1016/j.pnucene.2020.103509openalex-snapshot
MELCOR simulation of the SBLOCA induced severe accident for the SMR in a floating nuclear power plant
inferred← citeshttps://doi.org/10.1016/j.pnucene.2020.103513openalex-snapshot
An assessment of radiological source terms for loss of cooling and coolant accidents of a PWR spent fuel pool
inferred← citeshttps://doi.org/10.1016/j.pnucene.2021.103871openalex-snapshot
Plant-specific assessment of the natural circulation-induced creep rupture characteristics in the RCS pressure boundary during the SBO accident
inferred← citeshttps://doi.org/10.1016/j.pnucene.2021.103874openalex-snapshot
Development of a lumped-parameter code for efficient assessment of in-vessel melt retention strategy of LWRs
inferred← citeshttps://doi.org/10.1016/j.pnucene.2021.103903openalex-snapshot
Study on the influence of droplet agglomeration on the removal of aerosol by spray system
inferred← citeshttps://doi.org/10.1016/j.pnucene.2022.104556openalex-snapshot
Bootstrapped artificial neural network model for uncertainty analysis in MELCOR simulation of severe accident
inferred← citeshttps://doi.org/10.1016/j.pnucene.2023.104609openalex-snapshot
Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1
inferred← citeshttps://doi.org/10.1016/j.psep.2022.04.008openalex-snapshot
Analysis of the gases distribution during a severe accident by coupling the MELCOR and FLUENT in WWER1000 containment
inferred← citeshttps://doi.org/10.1016/j.ress.2009.10.008openalex-snapshot
Development of a code-agnostic computational infrastructure for the dynamic generation of accident progression event trees
inferred← citeshttps://doi.org/10.1016/j.ress.2012.09.002openalex-snapshot
Online scenario labeling using a hidden Markov model for assessment of nuclear plant state
inferred← citeshttps://doi.org/10.1016/j.ress.2013.02.028openalex-snapshot
A probabilistic model for online scenario labeling in dynamic event tree generation
inferred← citeshttps://doi.org/10.1016/j.ress.2020.107099openalex-snapshot
A framework for verifying Dynamic Probabilistic Risk Assessment models
inferred← citeshttps://doi.org/10.1016/j.ress.2021.107770openalex-snapshot
Uncertainty analysis of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout
inferred← citeshttps://doi.org/10.1016/s0029-5493(99)00052-7openalex-snapshot
Experiments and computational models for aerosol behaviour in the containment
inferred← citeshttps://doi.org/10.1016/s0029-5493(99)00328-3openalex-snapshot
Experimental and analytical study on aerosol behavior in WIND project
inferred← citeshttps://doi.org/10.1016/s0149-1970(03)90004-7openalex-snapshot
A state-of-the-art review of the reactor lower head models employed in three representative U.S. severe accident codes
inferred← citeshttps://doi.org/10.1080/00221689709498391openalex-snapshot
Passive decay heat removal in advanced nuclear reactors
inferred← citeshttps://doi.org/10.1080/00223131.2015.1044262openalex-snapshot
An integrated approach to source term uncertainty and sensitivity analyses for nuclear reactor severe accidents
inferred← citeshttps://doi.org/10.1080/00223131.2015.1072065openalex-snapshot
Release of radioactive materials from high active liquid waste in small-scale hot test for boiling accident in reprocessing plant
inferred← citeshttps://doi.org/10.1080/00223131.2016.1273145openalex-snapshot
Effectiveness and adverse effects of in-vessel retention strategies under a postulated SGTR accident of an OPR1000
inferred← citeshttps://doi.org/10.1080/00223131.2022.2100837openalex-snapshot
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations
inferred← citeshttps://doi.org/10.1080/00295450.2018.1464838openalex-snapshot
Potential Recovery Actions from a Severe Accident in a PWR: MELCOR Analysis of a Station Blackout Scenario
inferred← citeshttps://doi.org/10.1080/00295450.2025.2542015openalex-snapshot
Advances in Thermal Hydraulics in the Dutch PIONEER Program
inferred← citeshttps://doi.org/10.1080/00295639.2020.1861862openalex-snapshot
A Newly Developed Suppression Pool Model Based on the ISAA Code
inferred← citeshttps://doi.org/10.1080/00295639.2022.2108643openalex-snapshot
Identifying Thermodynamic Mechanisms Affecting Reactor Pressure Vessel Integrity During Severe Nuclear Accidents Simulated by Laser Heating at the Laboratory Scale
inferred← citeshttps://doi.org/10.1080/12460125.2020.1854426openalex-snapshot
A decision-support approach to severe accident management in nuclear power plants
inferred← citeshttps://doi.org/10.1080/18811248.1998.9733887openalex-snapshot
A Real-Time Prediction Technique of Severe Accident Progression in Containment for Emergency Response
inferred← citeshttps://doi.org/10.1080/18811248.2002.9715185openalex-snapshot
Enhancement of Cesium Release from Irradiated Fuel at Temperature above 2,800 K
inferred← citeshttps://doi.org/10.1080/18811248.2002.9715258openalex-snapshot
Decrease of Cesium Release from Irradiated UO2Fuel in Helium Atmosphere under Elevated Pressure of 1.0 MPa at Temperature up to 2,773K
inferred← citeshttps://doi.org/10.1080/18811248.2008.9711920openalex-snapshot
Development of Systematic Models for Aerosol Agglomeration and Spray Removal under Severe Accident Conditions
inferred← citeshttps://doi.org/10.1080/18811248.2011.9711682openalex-snapshot
Outcome of VEGA Program on Radionuclide Release from Irradiated Fuel under Severe Accident Conditions
inferred← citeshttps://doi.org/10.1088/0029-5515/47/7/s06openalex-snapshot
Safety analysis of the US dual coolant liquid lead–lithium ITER test blanket module
inferred← citeshttps://doi.org/10.1088/0029-5515/55/12/123008openalex-snapshot
Thermohydraulic responses of a water-cooled tokamak fusion DEMO to loss-of-coolant accidents
inferred← citeshttps://doi.org/10.1088/1742-6596/2685/1/012043openalex-snapshot
Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part I: sensitivity studies.
inferred← citeshttps://doi.org/10.1088/1742-6596/2685/1/012044openalex-snapshot
Towards a more realistic MELCOR model for a dry cask for spent nuclear fuel. Part II: application.
inferred← citeshttps://doi.org/10.1109/fareastcon.2018.8602779openalex-snapshot
Numerical Simulation of Induction Heating for Molten Pool Heat Transfer Experiments in Slice Geometry
inferred← citeshttps://doi.org/10.1109/iyce.2013.6604147openalex-snapshot
Design basis reconstitution of VVER 440/V213 - containment issues
inferred← citeshttps://doi.org/10.1115/1.4054685openalex-snapshot
Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment
inferred← citeshttps://doi.org/10.1155/2012/209420openalex-snapshot
Severe Accident Simulation of the Laguna Verde Nuclear Power Plant
inferred← citeshttps://doi.org/10.1155/2012/735719openalex-snapshot
An Evaluation Methodology Development and Application Process for Severe Accident Safety Issue Resolution
inferred← citeshttps://doi.org/10.1155/2015/238723openalex-snapshot
Improved Modelling and Assessment of the Performance of Firefighting Means in the Frame of a Fire PSA
inferred← citeshttps://doi.org/10.11606/t.85.2018.tde-10092018-153236openalex-snapshot
Método para aplicação da metodologia Best Estimate Plus Uncertainty (BEPU) em um Relatório Final de Análise de Segurança (RFAS) de uma planta genérica
inferred← citeshttps://doi.org/10.1243/1748006xjrr125openalex-snapshot
Consideration of human actions in combination with the probabilistic dynamics method Monte Carlo dynamic event tree
inferred← citeshttps://doi.org/10.1299/mej.15-00032openalex-snapshot
Source term uncertainty analysis: probabilistic approaches and applications to a BWR severe accident
inferred← citeshttps://doi.org/10.13164/eeict.2022.220openalex-snapshot
Investigation of the hydrogen production by the FeCrAl nuclear fuel cladding using MELCOR 2.2
inferred← citeshttps://doi.org/10.13182/fst01-a11963361openalex-snapshot
Accident Doses Analysis of the Sombrero Inertial Fusion Energy Power Plant Design
inferred← citeshttps://doi.org/10.13182/nse05-a2506openalex-snapshot
Modeling PSA Problems—I: The Stimulus-Driven Theory of Probabilistic Dynamics
inferred← citeshttps://doi.org/10.13182/nt13-40openalex-snapshot
A Reassessment of Low Probability Containment Failure Modes and Phenomena in a Long-Term Station Blackout
inferred← citeshttps://doi.org/10.1360/csb-2025-5492openalex-snapshot
Development and application of the modular severe accident analysis program MOSAP
inferred← citeshttps://doi.org/10.17146/tdm.2019.21.3.5630openalex-snapshot
Need of a Next Generation Severe Accident Code
inferred← citeshttps://doi.org/10.20868/upm.thesis.53129openalex-snapshot
Development and validation of key aerosol models for source term predictions in sodium-cooled fast reactors during beyond design basis accidents
inferred← citeshttps://doi.org/10.2172/1004364openalex-snapshot
Accident source terms for boiling water reactors with high burnup cores.
inferred← citeshttps://doi.org/10.2172/1010412openalex-snapshot
Accident source terms for light-water nuclear power plants using high-burnup or MOX fuel.
inferred← citeshttps://doi.org/10.2172/1044967openalex-snapshot
Sodium Fast Reactor Safety and Licensing Research Plan – Volume II
inferred← citeshttps://doi.org/10.2172/1044972openalex-snapshot
Sodium Fast Reactor Safety and Licensing Research Plan – Volume I
inferred← citeshttps://doi.org/10.2172/1048709openalex-snapshot
Validation of SCALE for High Temperature Gas-Cooled Reactors Analysis
inferred← citeshttps://doi.org/10.2172/1055601openalex-snapshot
Fukushima Daiichi accident study: status as of April 2012
inferred← citeshttps://doi.org/10.2172/1179443openalex-snapshot
Regulatory Technology Development Plan Sodium Fast Reactor. Mechanistic Source Term Development
inferred← citeshttps://doi.org/10.2172/1471700openalex-snapshot
A Case Study on Severe Accident Water Addition and Water Management for a MARK I Containment
inferred← citeshttps://doi.org/10.2172/1495192openalex-snapshot
Plant-Level Scenario-Based Risk Analysis for Enhanced Resilient PWR – SBO and LBLOCA
inferred← citeshttps://doi.org/10.2172/1777257openalex-snapshot
Risk-Informed Analysis for an Enhanced Resilient PWR with ATF, FLEX, and Passive Cooling
inferred← citeshttps://doi.org/10.2172/1777262openalex-snapshot
Evaluation of the Benefits of ATF, FLEX, and Passive Cooling System for an Enhanced Resilient PWR Model
inferred← citeshttps://doi.org/10.2172/1777266openalex-snapshot
Risk-Informed ATF and FLEX Analysis for an Enhanced Resilient BWR Under Design-Basis and Beyond-Design-Basis Accidents
inferred← citeshttps://doi.org/10.2172/1827046openalex-snapshot
Integration Roadmap for Multi-Scale, Multi-Physics Mass Accountancy in Molten Salt Reactors
inferred← citeshttps://doi.org/10.2172/910732openalex-snapshot
NGNP Point Design - Results of the Initial Neutronics and Thermal-Hydraulic Assessments During FY-03, Rev. 1
inferred← citeshttps://doi.org/10.2172/921148openalex-snapshot
Development of design and simulation model and safety study of large-scale hydrogen production using nuclear power.
inferred← citeshttps://doi.org/10.2172/966945openalex-snapshot
Development and application of the dynamic system doctor to nuclear reactor probabilistic risk assessments.
inferred← citeshttps://doi.org/10.2172/984120openalex-snapshot
Accident source terms for pressurized water reactors with high-burnup cores calculated using MELCOR 1.8.5.
inferred← citeshttps://doi.org/10.2172/989877openalex-snapshot
Methodology Using MELCOR Code to Model Proposed Hazard Scenario
inferred← citeshttps://doi.org/10.2495/978-1-84564-062-0/05openalex-snapshot
Enhancement of nuclear power plant safety by condensation-driven passive heat removal systems
inferred← citeshttps://doi.org/10.2495/risk140041openalex-snapshot
The principle of Defence-in-Depth in the perspective of Probabilistic Safety Analyses in the wake of Fukushima
inferred← citeshttps://doi.org/10.32469/10355/75003openalex-snapshot
Simulation of multiple-component charged aerosol evolution
inferred← citeshttps://doi.org/10.32918/nrs.2016.4(72).02openalex-snapshot
Analysis of Severe Accidents in Spent Fuel Pool of Fukushima Daiichi NPP Using MELCOR 1.8.6 Computer Code
inferred← citeshttps://doi.org/10.3327/jnst.39.759openalex-snapshot
Decrease of Cesium Release from Irradiated UO2 Fuel in Helium Atmosphere under Elevated Pressure of 1.0 MPa at Temperature up to 2,773 K.
inferred← citeshttps://doi.org/10.3389/fenrg.2018.00003openalex-snapshot
Review on Core Degradation and Material Migration Research in Light-Water Reactors
inferred← citeshttps://doi.org/10.3389/fenrg.2018.00043openalex-snapshot
Accident Process and Core Thermal Response During a Station Blackout Initiated Study for Small Modular Reactor
inferred← citeshttps://doi.org/10.3389/fenrg.2024.1332476openalex-snapshot
Development of a fully implicit ODE-solver for containment analysis code
inferred← citeshttps://doi.org/10.3389/fenrg.2024.1436245openalex-snapshot
Coupling of the best-estimate system code and containment analysis code and its application to TMLB’ accident
inferred← citeshttps://doi.org/10.3390/en14206640openalex-snapshot
MHD R&D Activities for Liquid Metal Blankets
inferred← citeshttps://doi.org/10.5516/net.2009.41.5.617openalex-snapshot
INVESTIGATIONS ON THE RESOLUTION OF SEVERE ACCIDENT ISSUES FOR KOREAN NUCLEAR POWER PLANTS
inferred← citeshttps://doi.org/10.5516/net.2009.41.7.929openalex-snapshot
SIMULATION OF CORE MELT POOL FORMATION IN A REACTOR PRESSURE VESSEL LOWER HEAD USING AN EFFECTIVE CONVECTIVITY MODEL
inferred← citeshttps://doi.org/10.5516/net.2010.42.4.339openalex-snapshot
ASSESSMENT OF CFD CODES USED IN NUCLEAR REACTOR SAFETY SIMULATIONS
inferred← citeshttps://doi.org/10.5772/intechopen.87697openalex-snapshot
Nuclear Power Plants - The Processes from the Cradle to the Grave
inferred← citeshttps://doi.org/10.5772/intechopen.92200openalex-snapshot
Calculation of the Dose for Public Individuals Due to a Severe Accident at the Angra 2 Nuclear Plant, Brazil
inferred← citeshttps://doi.org/10.58837/chula.the.2021.465openalex-snapshot
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Editorial review for independent work. ICSAC — the Institute for Complexity Science and Advanced Computing — runs a structured editorial panel for researchers publishing outside journals, and publishes on CiteStamp rails. Submission is free and goes through ORCID: icsacinstitute.org/submit.