Results 81 to 90 of about 1,865 (177)
Worst‐Case Accident Analysis of Accident Tolerant Fuel in NuScale Using RELAP5/MOD3‐Based Code
International Journal of Energy Research, Volume 2024, Issue 1, 2024.Research in nuclear engineering focusses on improving the safety of light water reactors (LWRs), driven by accidents like Fukushima in 2011. The severity of this accident was a result of active cooling system failures and cladding material oxidation resulting in hydrogen explosions.
Willem Zuidersma +3 more
wiley +1 more source
SCDAP/RELAP5/MOD 3.1 code manual: Interface theory. Volume 1
, 1995 The SCDAP/RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, core, fission product released during a ...
Berna, G. A. +2 more
core +1 more source
Developmental assessment of the SCDAP/RELAP5 code [PDF]
, 1997 The development and assessment of the late-phase damage progression models in the current version (designated MOD3.2) of the SCDAP/RELAP5 code are described.
Slefken, L. J. +2 more
core
, 1993 Members of the International Code Assessment Program (ICAP) have assessed the US Nuclear Regulatory Commission (USNRC) advanced thermal-hydraulic codes over the past few years in a concerted effort to identify deficiencies, to define user guidelines, and
Schultz, R. R.
core +1 more source
Decay Heat Removal and Transient Analysis in Accidental Conditions in the EFIT Reactor
Science and Technology of Nuclear Installations, 2008 The development of a conceptual design of an industrial-scale transmutation facility (EFIT) of several 100 MW thermal power based on accelerator-driven system (ADS) is addressed in the frame of the European EUROTRANS Integral Project. In normal operation,
Giacomino Bandini +5 more
doaj +1 more source
Analysis of nuclear safety in diversification of Westinghouse fuel assemblies at WWER-1000
Ядерна фізика та енергетика, 2019 The research presents an analysis of the known results in modeling the maximum design accident (MDA) using the code RELAP5/V3.2 with Westinghouse fuel assemblies’ (WFA) diversification in WWER-1000 reactors.
V. I. Skalozubov +4 more
doaj +1 more source
Atom Indonesia, 2019 In order to anticipate station blackout, the use of safety system based on passive features is highly considered in advanced nuclear power plant designs, especially after the Fukushima Dai-ichi nuclear power station accident.
A.R. Antariksawan +7 more
doaj +1 more source
Design and thermal-hydraulic simulations of SBO and LOCA on a Nuward-like SMR using RELAP5
, 2023 LAUREA MAGISTRALEIl seguente elaborato tratta in fase introduttiva dei parametri di progettazione dell’E-SMR (modello di un piccolo reattore modulare proposto da un consorzio di aziende nell'ambito del progetto ELSMOR ai sensi del trattato Euratom dell ...
LAMPERTI, ALESSIO
core
Study of thermal-hydraulic phenomena in hot leg break LOCA of PWR systems
, 2011 The present work cope with the execution of two post tests analysis relative to experiments executed in two different Integral test facilities. The aim of the work is to understand if the Thermal-Hydraulic system code utilized, has the capability to ...
MATTEOLI, CAMILLA
core
Analysis of Density Wave Oscillations in Helically Coiled Tube Once-Through Steam Generator
Science and Technology of Nuclear Installations, 2016 Helically coiled tube Once-Through Steam Generator (H-OTSG) is one of the key equipment types for small modular reactors. The flow instability of the secondary side of the H-OTSG is particularly serious, because the working condition is in the range of ...
Junwei Hao +7 more
doaj +1 more source