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Journal of Nuclear Science and Technology, ISSN 0022-3131, 04/2014, Volume 51, Issue 4, pp. 493 - 513
As the most promising concept of sodium-cooled fast reactors, the Japan Atomic Energy Agency (JAEA) has selected the advanced loop-type fast reactor, so-called... 
in-vessel retention (IVR) | sodium-cooled fast reactor (SFR) | unprotected loss of flow (ULOF) | anticipated transient without scram (ATWS) | core disruptive accident (CDA) | NUCLEAR SCIENCE & TECHNOLOGY | BEHAVIOR | PROGRAM | DEBRIS
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 05/2019, Volume 127, pp. 364 - 371
•The core of sodium-cooled fast reactor is not in its most reactive configuration.•Positive compaction reactivity in Core Disruptive Accident is thought as a... 
Re-criticality | CDA | Convex core | Fast spectrum reactor | Core geometry | CODE | NUCLEAR SCIENCE & TECHNOLOGY | Nuclear energy | Analysis | Nuclear reactors
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 04/2011, Volume 48, Issue 4, pp. 556 - 566
In the Japan Sodium Cooled Fast Reactor (JSFR) design, elimination of severe power burst events in the Core Disruptive Accident (CDA) is intended as an... 
ATWS | CDA | fuel discharge | IVR | FBR | severe accident | ULOF | recriticality | FAIDUS | Severe accident | Fuel discharge | Recriticality | NUCLEAR SCIENCE & TECHNOLOGY
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 05/2016, Volume 53, Issue 5, pp. 698 - 706
The in-vessel retention (IVR) of core disruptive accident (CDA) is of prime importance in enhancing safety characteristics of sodium-cooled fast reactors... 
safety assessment | sodium-cooled fast reactor | core disruptive accident | in-vessel retention | molten core material | Molten core material | Sodium-cooled fast reactor | Core disruptive accident | Invessel retention | Safety assessment | NUCLEAR SCIENCE & TECHNOLOGY | MODEL | Penetration | Sodium | Computer simulation | Methodology | Nuclear reactors | Pools | Debris | Discharge
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 07/2015, Volume 82, pp. 80 - 85
Japan Nuclear Energy Safety Organization (JNES) is a Technical Safety Organization (TSO) for Japanese Nuclear Regulation Authority to provide technical... 
Fast reactor fuel | Code development | Fuel behavior | Core disruptive accident | NUCLEAR SCIENCE & TECHNOLOGY | Nuclear energy | Nuclear power plants | Analysis | Accidents | Modules | Accident analysis | Nuclear reactor components | Nuclear engineering | Nuclear power generation | Mathematical models | Nuclear reactors | Fuels
Journal Article
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, ISSN 1000-6931, 05/2015, Volume 49, pp. 132 - 136
Journal Article
Nuclear Technology, ISSN 0029-5450, 10/2010, Volume 172, Issue 1, pp. 1 - 15
The FUSTIN dedicated computer code has been developed to predict the transient response of pool-type fast reactor components in a core disruptive accident.... 
Numerical and experimental simulation of CDA | Mechanical consequences of CDA | Core disruptive accident in FBR | core disruptive accident in FBR | numerical and experimental simulation of CDA | NUCLEAR SCIENCE & TECHNOLOGY | mechanical consequences of CDA
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 2009, Volume 36, Issue 3, pp. 337 - 343
The SIMMER-IV computer code is a three-dimensional fluid-dynamics code coupled with a fuel-pin model and a space- and energy-dependent neutron transport... 
NUCLEAR SCIENCE & TECHNOLOGY | PROGRAM | Inner core (Geology) | Nuclear energy | Nuclear reactors | Analysis | Accidents
Journal Article
Annals of Nuclear Energy, ISSN 0306-4549, 2011, Volume 38, Issue 11, pp. 2475 - 2487
► An approach to quantify thermal and pressure loadings on RCB is presented. ► Scaling laws to determine sodium release from water experiments are proposed. ►... 
Core disruptive accident | Containment building | In-vessel sodium fire potential | Sodium cooled fast reactor | Scaling laws | NUCLEAR SCIENCE & TECHNOLOGY | METAL | SECONDARY CONTAINMENT | Nuclear reactors | Mechanical engineering | Shipments data | Accidents
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 10/2017, Volume 322, pp. 522 - 535
•Evaluation tool for the expansion phase of a SFR Core-Disruptive Accident.•Comparison of adiabatic and non-adiabatic expansions due to sodium... 
Core disruptive accident | Interface instability | Dimensional analysis | SFR | Fast-running tool | THERMODYNAMIC PROPERTIES | RAYLEIGH-TAYLOR INSTABILITY | EQUATIONS | STATE | ENTRAINMENT | SAFETY ANALYSIS | NUCLEAR SCIENCE & TECHNOLOGY | PHYSICAL TOOL | Nuclear energy | Nuclear reactors | Analysis | Accidents | Nuclear Experiment | Nuclear Theory | Physics
Journal Article
Nuclear Engineering and Design, ISSN 0029-5493, 08/2014, Volume 275, pp. 133 - 141
•We investigate local fuel–coolant interaction within a simulated molten fuel pool.•Characteristics of pressure buildup and mechanical energy release... 
NUCLEAR SCIENCE & TECHNOLOGY | CORE DISRUPTIVE ACCIDENT | REACTOR
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 01/2019, Volume 56, Issue 1, pp. 111 - 122
The self-leveling of debris beds is a critical phenomenon to be clarified in the safety assessment of material relocation and decay heat-removal phases in... 
empirical model | mixed particles | Sodium-cooled fast reactor | core-disruptive accident | self-leveling | fuel debris | experimental data | NUCLEAR SCIENCE & TECHNOLOGY | CORE DISRUPTIVE ACCIDENT | DEBRIS
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 03/2015, Volume 79, pp. 182 - 189
Criticality and recriticality considerations in heavy liquid metal fast reactors (HLMFRs) after a hypothetical core meltdown accident are discussed. Although... 
Disassembly phase | Heavy liquid metal reactor | Recriticality | Bethe–Tait model | Hypothetical core disruptive accidents | Bethe-Tait model | NUCLEAR SCIENCE & TECHNOLOGY | Analysis | Models | Nuclear reactors
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 11/2017, Volume 101, pp. 224 - 234
Under a hypothetical core meltdown and relocation scenario in Sodium cooled Fast Reactor (SFR), there may be a chance for reactor main vessel failure if the... 
Post Accident Heat Removal (PAHR) | Hypothetical core meltdown scenario | Decay heat removal in SFR | Sodium cooled Fast Reactors (SFR) | SODIUM | DESIGN | CATCHER | NUCLEAR SCIENCE & TECHNOLOGY | DISRUPTIVE ACCIDENT | FUEL | COOLED FAST-REACTOR | FAST BREEDER REACTOR | Models | Numerical analysis | Analysis | Business relocation | Nuclear reactors | Accidents
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 11/2015, Volume 52, Issue 11, pp. 1448 - 1459
As the most promising concept of sodium-cooled fast reactors, the Japan Atomic Energy Agency has selected the advanced loop-type fast reactor, so-called Japan... 
material-relocation phase | sodium-cooled fast reactor | in-vessel retention (IVR) | unprotected loss of flow (ULOF) | recriticality | core-disruptive accident (CDA) | NUCLEAR SCIENCE & TECHNOLOGY | CORE DISRUPTIVE ACCIDENT | IN-VESSEL RETENTION
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 05/2018, Volume 55, Issue 5, pp. 530 - 538
The SIMMER code has been developed to analyze event progression during core disruptive accidents (CDAs) in sodium-cooled fast reactors. One of the key... 
safety analysis | Sodium-cooled fast reactor (SFR) | core disruptive accident (CDA) | solid-liquid flow model | multi-phase | multi-component | SIMMER code | solid–liquid flow model | IN-VESSEL RETENTION | DISRUPTIVE ACCIDENT | REACTOR | PARTICLE BED | NUCLEAR SCIENCE & TECHNOLOGY | DYNAMIC-BEHAVIOR | POOL
Journal Article
Nuclear Engineering and Technology, ISSN 1738-5733, 04/2015, Volume 47, Issue 3, pp. 240 - 252
In the original licensing application for the prototype fast-breeder reactor, MONJU, the event progression during an unprotected loss of flow (ULOF), which is... 
Core disruptive accident (CDA) | In-vessel retention (IVR) | Sodium-cooled fast reactor (SFR) | SAS4A | SIMMER-III/IV | Unprotected loss of flow (ULOF) | SAFETY ANALYSIS | NUCLEAR SCIENCE & TECHNOLOGY | 원자력공학
Journal Article
Journal of Nuclear Science and Technology, ISSN 0022-3131, 09/2016, Volume 53, Issue 9, pp. 1409 - 1416
In the present Korean sodium-cooled fast reactor (SFR) program, early dispersion of the molten metal fuel within a subchannel is suggested as an inherent... 
sodium-cooled fast reactor (SFR) | Hypothetical core disruptive accident (HCDA) | dispersion of molten metal fuel | metal fuel | severe accident | NUCLEAR SCIENCE & TECHNOLOGY | BEHAVIOR | Nuclear safety | Nuclear engineering | Strategy | Coolants | Boiling | Dispersion | Melts | Fragmentation
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 11/2019, Volume 117, p. 103086
Journal Article
Progress in Nuclear Energy, ISSN 0149-1970, 09/2018, Volume 108, pp. 188 - 203
During severe accidents at Nuclear Power Plants (NPPs), fuel-coolant interaction (FCI) is a critical event in which the melt released from the core region... 
Fuel-coolant interaction | Jet-breakup | Severe accident | Solidification effects | Nuclear reactor | Fragmentation | MOLTEN-METAL DROPLET | CORE DISRUPTIVE ACCIDENT | STEAM EXPLOSIONS | QUENCHING TESTS | SODIUM POOL | STAINLESS-STEEL | NUCLEAR SCIENCE & TECHNOLOGY | COOLANT INTERACTIONS | THERMAL-STRESS | SIZE DISTRIBUTION | INTERFACE TEMPERATURES
Journal Article
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