Results 61 to 70 of about 1,365 (205)
International Journal of Energy Research, Volume 2024, Issue 1, 2024.The integrity of containment buildings in nuclear power plants is crucial for preventing the release of radioactive materials during severe accidents. This study investigates the effect of the uncertainty in temperature‐dependent strength of concrete on the internal pressure capacity of prestressed concrete containment vessel (PCCV).
Sangwoo Lee +6 more
wiley +1 more source
Science and Technology of Nuclear Installations, 2017 The integral Phébus tests were probably one of the most important experimental campaigns performed to investigate the progression of severe accidents in light water reactors. In these tests, the degradation of a PWR fuel bundle was investigated employing
Bruno Gonfiotti, Sandro Paci
doaj +1 more source
Analysis of Ex‐Vessel Debris Coolability of Boiling Water Reactors
International Journal of Energy Research, Volume 2024, Issue 1, 2024.To evaluate the effectiveness of the wet cavity strategy, the authors developed a stochastic evaluation method that considers the uncertainties of the molten material conditions ejected from reactor pressure vessels. This study analyzed the probability of ex‐vessel debris coolability under the wet cavity strategy.
Toshinori Matsumoto +3 more
wiley +1 more source
Loss of Liquid Lithium Coolant in an Accident in a DONES Test Cell Facility
Energies, 2021 A Demo-Oriented early NEutron Source (DONES) facility for material irradiation with nuclear is currently being designed. DONES aims to produce neutrons with fusion-relevant spectrum and fluence by means of D–Li stripping reactions occurring between a ...
Danilo Nicola Dongiovanni +1 more
doaj +1 more source
MELCOR analysis of the TMI-2 accident [PDF]
, 1990 This paper describes the analysis of the Three Mile Island-2 (TMI-2) standard problem that was performed with MELCOR. The MELCOR computer code is being developed by Sandia National Laboratories for the Nuclear Regulatory Commission for the purpose of ...
Boucheron, E.A.
core
Integration of DICE and MELCOR for dynamic event tree analysis: Case study for RCS failure phenomena
Nuclear Engineering and TechnologyDynamic Event Tree Analysis enhances NPP safety assessment by systematically introducing stochastic variability into deterministic simulations and explicitly representing operator actions, system availability, and temporal dependencies.
Dohun Kwon, Gyunyoung Heo
doaj +1 more source
EnergiesIn the WCLL-BB liquid blanket concept, among the postulated accidental scenarios to be investigated regarding the PbLi system, a loss of liquid metal is one of the most crucial for safety purposes.
Francesco Galleni +3 more
doaj +1 more source
Uncertainty and Sensitivity Analysis of a Dry Cask for Spent Nuclear Fuel
Energies, 2022 Nuclear safety relies to a good extent on thoroughly validated codes. However, code predictions are affected by uncertainties that need to be quantified for a more accurate evaluation of safety margins.
Michela Angelucci +3 more
doaj +1 more source
MELCOR Verification, Benchmarking, and Applications experience at BNL [PDF]
, 1992 This paper presents a summary of MELCOR Verification, Benchmarking and Applications experience at Brookhaven National Laboratory (BNL), sponsored by the US Nuclear Regulatory Commission (NRC).
Madni, I.K.
core +2 more sources
Source term uncertainty analysis: probabilistic approaches and applications to a BWR severe accident
Mechanical Engineering Journal, 2015 A suite of methods has been established to quantitatively estimate uncertainties existed in source term analysis during a nuclear reactor severe accident.
Xiaoyu ZHENG +3 more
doaj +1 more source