Results 81 to 90 of about 1,536,451 (138)
Liquid metal cooled fast reactor thermal hydraulic research development: A review. [PDF]
Heliyon, 2023 Agbevanu KT +3 more
europepmc +1 more source
RELAP5 code study of ROSA/LSTF experiment on a PWR station blackout (TMLB') transient
Mechanical Engineering Journal, 2014 RELAP5 code post-test analysis was performed on one of abnormal transient tests conducted with the ROSA/large scale test facility (LSTF) simulating a PWR station blackout (SBO) transient with the TMLB' scenario in 1995.
Takeshi TAKEDA, Hideo NAKAMURA
doaj +1 more source
, 2001 The Reactor Excursion and Leak Analysis Program with 3D capability1 (RELAP5-3D) is a reactor system analysis code that has been developed at the Idaho National Engineering and Environmental Laboratory (INEEL) for the U. S. Department of Energy (DOE). The
Riemke, Richard Allan
core
An open time-series simulated dataset covering various accidents for nuclear power plants. [PDF]
Sci Data, 2022 Qi B +5 more
europepmc +1 more source
Nuclear Engineering and TechnologyThe main purposes of start-up tests in nuclear power plants (NPPs) are to ensure safe and reliable operation, verify system functionality, comply with regulatory requirements, optimize performance, and establish a foundation for ongoing plant operation ...
Navid Vahman, Reza Akbari
doaj +1 more source
International Building Code: 2009 [PDF]
, 2009 Manual describing best practices for constructing buildings that meet safety and energy requirements; appropriate building materials and use; and related issues: "This comprehensive building code establishes minimum regulations for building systems using
International Code Council
core
An Interpretable Time Series Data Prediction Framework for Severe Accidents in Nuclear Power Plants. [PDF]
Entropy (Basel), 2023 Fu Y, Zhang D, Xiao Y, Wang Z, Zhou H.
europepmc +1 more source
A review of the application of artificial intelligence to nuclear reactors: Where we are and what's next. [PDF]
Heliyon, 2023 Huang Q +6 more
europepmc +1 more source
Simulation of a TRIGA Reactor Core Blockage Using RELAP5 Code
Science and Technology of Nuclear Installations, 2015 Cases of core coolant flow blockage transient have been simulated and analysed for the TRIGA IPR-R1 research reactor using the RELAP5-MOD3.3 code. The transients are related to partial and to total obstruction of the core coolant channels.
Patrícia A. L. Reis +4 more
doaj +1 more source
Implementation of the RRC-KI Neutron Flux Correction Methodology in the RELAP5-3D Code [PDF]
, 2003 The International Atomic Energy Agency has sponsored a program, “Accident Analysis and its Associated Training Programme for RBMK-1000 Kursk-1 NPP (Phase II)”. Under the auspices of this program, Reactor Research Centre “Kurchatov Institute” (RRC-KI) has
Fisher, J. E.
core +1 more source