Results 31 to 40 of about 1,365 (205)

Assessment of Cesium Compound Behavior during Simultaneous Failure of Reactor Pressure Vessels and Spent Fuel Pools Using Modified ART Mod 2: Fukushima Daiichi Accident Simulation

Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021
To support the regional strategy development of ASEAN NPSR using scientific research, Modified ART Mod 2 has been used to assess the fission product release from RPVs and SFPs independently. However, the Fukushima Accident suggested the possibility of simultaneous release from RPV and SFP which indicated the necessity of re‐evaluation of the maximum ...
Wasin Vechgama, Kampanart Silva, Sheng Fang   +2 more
wiley   +1 more source

Best-Estimate for System Codes (BeSYC): A New Software to Perform Best-Estimate Plus Uncertainty Analyses with Thermal-Hydraulic and Safety System Codes for Both Fusion and Fission Scenarios

Applied Sciences, 2021
The development and the validation of old and new software in relevant DEMO reactor conditions have been exploited in the latest years within the EUROfusion Consortium.
Bruno Gonfiotti, Michela Angelucci, Bradut-Eugen Ghidersa, Xue Zhou Jin, Mihaela Ionescu-Bujor, Sandro Paci, Robert Stieglitz   +6 more
doaj   +1 more source

Identification of hydrogen flammability in steam generator compartment of OPR1000 using MELCOR and CFX codes

Nuclear Engineering and Technology, 2019
The MELCOR code useful for a plant-specific hydrogen risk analysis has inevitable limitations in prediction of a turbulent flow of a hydrogen mixture. To investigate the accuracy of the hydrogen risk analysis by the MELCOR code, results for the turbulent
Joongoo Jeon, Yeon Soo Kim, Wonjun Choi, Sung Joong Kim   +3 more
doaj   +1 more source

Performing a multi-unit level-3 PSA with MACCS

Nuclear Engineering and Technology, 2021
MACCS (MELCOR Accident Consequence Code System), WinMACCS, and MelMACCS now facilitate a multi-unit consequence analysis. MACCS evaluates the consequences of an atmospheric release of radioactive gases and aerosols into the atmosphere and is most ...
Nathan E. Bixler, Sung-yeop Kim
doaj   +1 more source

Simulation of a severe accident at a typical PWR due to break of a hot leg ECCS injection line using MELCOR code.

Brazilian Journal of Radiation Sciences, 2019
The aim of this work was to simulate a severe accident at a typical PWR, initiated with a break in Emergency Core Cooling System line of a hot leg, using the MELCOR code.
Seung Min Lee, Nelbia da Silva Lapa, Gaianê Sabundjian   +2 more
doaj   +1 more source

Vessel Failure Analysis of a Boiling Water Reactor During a Severe Accident

Frontiers in Energy Research, 2022
In a postulated severe accident, the thermo-mechanical loads from the corium debris that has relocated to the lower head of the reactor pressure vessel (RPV) can pose a credible threat to the RPV’s structural integrity.
H. D. Wang, Y. L. Chen, W. Villanueva
doaj   +1 more source

Analysis of the Effect of Severe Accident Scenario on Debris Properties in Lower Plenum of Nordic BWR Using Different Versions of MELCOR Code

Science and Technology of Nuclear Installations, 2019
Nordic Boiling Water Reactors (BWRs) employ ex-vessel debris coolability as a severe accident management strategy (SAM). Core melt is released into a deep pool of water where formation of noncoolable debris bed and ex-vessel steam explosion can pose ...
Sergey Galushin, Pavel Kudinov
doaj   +1 more source

MELCOR-To-MELCOR Coupling Method in Severe Accident Analysis Involving Core and Spent Fuel Pool

Journal of Energy : Energija, 2023
A lot of effort has been spent to prevent the occurrence of SA in nuclear plant and to develop Severe Accidents (SA) Management to mitigate the consequences of a SA. Those consequences are mainly related to limit the release of fission product to the environment.
Lopez, Hector, Petruzzi, Alessandro, Giannotti, Walter, De Luca, Domenico   +3 more
openaire   +2 more sources

Uncertainty and Sensitivity Analysis of the In-Vessel Hydrogen Generation for Gen-III PWR and Phebus FPT-1 with MELCOR 2.2

Energies, 2021
In this study, uncertainty and sensitivity analyses were performed with MELCOR 2.2.18 to study the hydrogen generation (figure-of-merit (FoM)) during the in-vessel phase of a severe accident in a light water reactor.
Piotr Darnowski, Piotr Mazgaj, Mateusz Włostowski   +2 more
doaj   +1 more source

Studies on Key Effect Factors of Natural Circulation Characteristics for Advanced PWR Reactor Cavity Flooding System

Science and Technology of Nuclear Installations, Volume 2020, Issue 1, 2020., 2020
In order to enhance the ability of severe accident mitigation for Pressurised Water Reactor (PWR), different kinds of severe accident mitigation strategies have been proposed. In‐Vessel Retention (IVR) is one of the important severe accident management means by External Reactor Vessel Cooling. Reactor cavity would be submerged to cool the molten corium
Dekui Zhan, Xinhai Zhao, Shaoxiong Xia, Peng Chen, Huandong Chen, Han Zhang   +5 more
wiley   +1 more source