MCS ANALYSIS OF 1000 MWTH SODIUM-COOLED FAST REACTOR
This paper describes the neutron transport calculations for the sodium-cooled fast reactors by using the new under-developing Monte Carlo code MCS in combination with various nuclear data libraries.
Dos, Vutheam +3 more
core
Mechanical Testing of Metal-Packaged FBG-Based Sensors Before and After High-Fluence Reactor Irradiation. [PDF]
Sapatayev Y +8 more
europepmc +1 more source
The numerical reactor system for China's new-generation exascale supercomputer. [PDF]
Miao X +14 more
europepmc +1 more source
Preparation of levulinic acid and 5-(chloromethyl)furfural directly from terrestrial and marine biomass in a batch reactor under conventional and microwave heating. [PDF]
Aranha DA +7 more
europepmc +1 more source
Advances in High-Temperature Irradiation-Resistant Neutron Detectors. [PDF]
Wang C, Yu R, Xia W, Gong J.
europepmc +1 more source
Startup of the FFTF sodium cooled reactor. [Acceptance Test Program]
The Fast Flux Test Facility (FFTF), located on the Department of Energy (DOE) Hanford Reservation near Richland, Washington, is a 3 Loop 400 MW(t) sodium cooled fast reactor with a primary mission to test fuels and materials for development of the Liquid
Redekopp, R. D., Umek, A. M.
core
Continuous-flow photogeneration of nitrosobenzaldehydes enables indazolone formation. [PDF]
Leclercq N +3 more
europepmc +1 more source
Interfacial solidification behavior during liquid metal-water interactions. [PDF]
Zhang L, Deng C, Zheng M, Liu X.
europepmc +1 more source
Continuous Synthesis of Carbon-Coated Na<sub>3</sub>V<sub>2</sub>(PO<sub>4</sub>)<sub>3</sub> by Segmented Flow Tubular Reactor. [PDF]
Gatti SF +4 more
europepmc +1 more source
Fretting Corrosion Behavior of Multilayer Structure on Nitrided 2.25Cr-1Mo Steel in 723 K Liquid Sodium. [PDF]
Chen X, Hu W, Chen F, Wang L, Wang J.
europepmc +1 more source

