Existing elastic analysis methods cannot be adhered to in order to assess the structural integrity of a reactor vessel and internals for a beyond design basis earthquake.
Sang-Jeong Lee +5 more
doaj +3 more sources
MODAL CHARACTERISTIC ANALYSIS OF THE APR1400 NUCLEAR REACTOR INTERNALS FOR SEISMIC ANALYSIS
Reactor internals are sensitive to dynamic loads such as earthquakes and flow induced vibration. Thus, it is essential to identify the dynamic characteristics to evaluate the seismic integrity of the structures.
JONG-BEOM PARK +6 more
doaj +3 more sources
Measurement of vibration and stress for APR-1400 reactor internals
The U.S. Nuclear Regulatory Commission, Regulatory Guide 1.20 needs to perform a comprehensive vibration assessment program for reactor internals during preoperational and startup testing for nuclear power plants and extended power uprate.
Do-Young Ko, Kyu-Hyung Kim
doaj +3 more sources
Pyrolysis characteristics of waste tire particles in fixed-bed reactor with internals
This study investigated the characteristics of pyrolysis for waste tire particles in the newly developed fixed-bed reactor with internals that are a central gas collection channel mounted inside reactor. And a few metallic plates vertically welded on the
Shipei Xu +8 more
doaj +3 more sources
Deep-Learning and Dynamic Time Warping-Based Approaches for the Diagnosis of Reactor Systems [PDF]
The degradation of clamping force in the core support barrel, which forms the internal structure of a nuclear power plant, has the potential to significantly impact the plant’s safety and reliability.
Hoejun Jeong +3 more
doaj +2 more sources
The U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.20 provides guidance on the comprehensive vibration assessment program (CVAP) to be performed on reactor internals during pre-operational and startup tests.
Jongsung Moon +3 more
doaj +3 more sources
The role of nickel in forming a structure providing increased service properties of reactor structural materials [PDF]
Nickel is an essential alloying element in steels used as structural materials in the most common nuclear power reactors of the VVER type. The paper considers reviews the results of structural studies of traditional and advanced materials of the vessels ...
Evgenia A. Kuleshova +5 more
doaj +3 more sources
A study into the structure and physical properties of the Cr18Ni9-grade steel following long-term irradiation as part of the BN-600 reactor internals * [PDF]
The microstructures and physical properties of the austenitic Cr18Ni9-grade steel after 22 and 33 years of operation as part of the reactor internals were tested for assessing the conditions of the BN-600 reactor non-replaceable components (internals ...
Irina A. Portnykh +3 more
doaj +3 more sources
Assessing the degree of plug flow in oxidation flow reactors (OFRs): a study on a potential aerosol mass (PAM) reactor [PDF]
Oxidation flow reactors (OFRs) have been developed to achieve high degrees of oxidant exposures over relatively short space times (defined as the ratio of reactor volume to the volumetric flow rate).
D. Mitroo +7 more
doaj +1 more source
Modelling Irradiation Effects in Metallic Materials Using the Crystal Plasticity Theory—A Review
The review starts by highlighting the significance of nuclear power plants in the contemporary world, especially its indispensable role in the global efforts to reduce CO2 emissions.
Karol Frydrych
doaj +1 more source

