Results 71 to 80 of about 248 (163)

Wettability of candidate Accident Tolerant Fuel (ATF) cladding materials in LWR conditions

, 2020
Since the 2011 Fukushima accident, substantial research has been dedicated to developing accident tolerant fuel (ATF) cladding materials. These analyses have mostly concentrated on the capability of potential ATF materials to withstand runaway steam oxidation and preserve their mechanical strength and structural integrity under thermal shocks. However,
openaire   +1 more source

EHA2024 Hybrid Congress

HemaSphere, Volume 8, Issue S1, June 2024.
wiley   +1 more source

GIFT-1.0: Advanced light water reactor fuel performance code

Nuclear Engineering and Technology
In response to emerging fuel technologies, such as Accident Tolerant Fuels (ATF), Small Modular Reactor (SMR) fuels, and extended spent fuel storage in the nuclear power industry, GIFT-1.0 was developed to enable full life-cycle simulations of Light ...
Kyuseok Shim, Hyuntaek Rho, Chansoo Lee, Changhyun Jo, Youho Lee   +4 more
doaj   +1 more source

Assessment of stainless steel 348 fuel rod performance against literature available data using TRANSURANUS code

EPJ Nuclear Sciences & Technologies, 2016
Early pressurized water reactors were originally designed to operate using stainless steel as cladding material, but during their lifetime this material was replaced by zirconium-based alloys.
Giovedi Claudia, Cherubini Marco, Abe Alfredo, D’Auria Francesco   +3 more
doaj   +1 more source

Some practical methodologies to assess the overall high temperature (one-sided) steam oxidation protectiveness of chromium-based coatings on a zirconium-based substrate, as Enhanced – Accident tolerant (Nuclear) fuels (E-ATF) claddings

Journal of Nuclear Materials
Among various Enhanced-Accident Tolerant nuclear fuel claddings studied worldwide, Cr-coated Zr-based claddings are largely considered as a reference with evolutionary design and resulting ability to improve the high-temperature (HT) oxidation resistance.
Jean-Christophe Brachet, Thomas Guilbert, Stéphane Urvoy, Elodie Rouesne, Marion Peyret, Thierry Vandenberghe, Cédric Prou, Thai Le Hong, Didier Hamon   +8 more
openaire   +2 more sources

Critical evaluation of accident tolerant fuel selection criteria for APR-1400 nuclear reactors

Advances in Physics: X
The United Arab Emirates (UAE) launched its nuclear energy program in 2008, achieving notable outcomes with the ‘UAE Policy on the Peaceful Use of Nuclear Energy’ program.
Mohammad Alrwashdeh, Asma Alzarooni, Khurrum Saleem Chaudri, Maithah Alaleeli, K. Karuppasamy, Andreas Schiffer, Imran Afgan, Daniel Choi, Saeed A. Alameri   +8 more
doaj   +1 more source

Development of FEMAXI-ATF for analyzing PCMI behavior of SiC cladded fuel under power ramp conditions

Nuclear Engineering and Technology
FEMAXI-ATF is being developed for fuel performance modeling of SiC cladded UO2 fuel with focuses on modeling pellet-cladding mechanical interactions (PCMI). The code considers probability distributions of mechanical strengths of monolithic SiC (mSiC) and
Yoshihiro Kubo, Akifumi Yamaji
doaj   +1 more source

Aspects of Applied Chemistry Related to Future Goals of Safety and Efficiency in Materials Development for Nuclear Energy. [PDF]

Molecules, 2023
Golgovici F, Tudose AE, Diniasi D, Nartita R, Fulger M, Demetrescu I.   +5 more
europepmc   +1 more source

Corrosion Behavior of Al_x(CrFeNi)_1-x HEA under Simulated PWR Primary Water. [PDF]

Materials (Basel), 2022
Luo D, Yang Z, Yang H, Chen Q, Wang Y, Qiu N.   +5 more
europepmc   +1 more source

Recent Progress on Creep Properties of ODS FeCrAl Alloys for Advanced Reactors. [PDF]

Materials (Basel), 2023
Jia H, Wang Y, Wang Y, Han L, Zhang Y, Zhou Z.   +5 more
europepmc   +1 more source