Results 51 to 60 of about 219 (116)

Dataset of observables for small modular lead-cooled fast reactor MOX spent nuclear fuel. [PDF]

Data Brief
Casas-Molina VJ, Romojaro P, Nourry G, Eynde GVD, Fiorito L, Merino-Rodríguez I, Dhaene T, Couckuyt I.   +7 more
europepmc   +1 more source

What cooling pond sediments can reveal about 14C in nuclear power plant liquid effluents: Case study Lake Drūkšiai, Ignalina nuclear power plant cooling pond. [PDF]

PLoS One, 2023
Barisevičiūtė R, Mažeika J, Maceika E, Juodis L, Rakauskas V, Jefanova O, Ežerinskis Ž, Šapolaitė J, Butkus L, Remeikis V.   +9 more
europepmc   +1 more source

Combination of nuclear battery and nuclear power plant: A conceptual framework. [PDF]

Sci Rep
Moshkbar-Bakhshayesh K.
europepmc   +1 more source

Investigating the possibility of extending the BWR cycle length for 15 years of operation by mixing highly enriched UO₂ fuel with burnable absorbers. [PDF]

Sci Rep, 2023
Mustafa SS.
europepmc   +1 more source

Measurements of stable ruthenium fission products in nuclear reactor fuel samples. [PDF]

Sci Rep
Patton GM, Torrano ZA, Salazar A, Miller J, Sanborn ME, Hanson SK.   +5 more
europepmc   +1 more source

Localizing Perturbations in Pressurized Water Reactors Using One-Dimensional Deep Convolutional Neural Networks. [PDF]

Sensors (Basel), 2021
Pantera L, Stulík P, Vidal-Ferràndiz A, Carreño A, Ginestar D, Ioannou G, Tasakos T, Alexandridis G, Stafylopatis A.   +8 more
europepmc   +1 more source

Corrosion of Stainless Steel in Simulated Nuclear Reactor Primary Coolant-Experiments and Modeling. [PDF]

Materials (Basel)
Bojinov M, Betova I, Karastoyanov V, Avdeev G.   +3 more
europepmc   +1 more source

Long-Term Oxidation of Zirconium Alloy in Simulated Nuclear Reactor Primary Coolant-Experiments and Modeling. [PDF]

Materials (Basel), 2023
Betova I, Bojinov M, Karastoyanov V.
europepmc   +1 more source

The mathematical model of the NPP power unit primary circuit with reactor of PWR-1000 type and evaluation of her dynamic accuracy in variable modes

Vestnik IGEU, 2015
D.V. Lavrentichev, Yu.S. Tverskoy
openaire   +1 more source

Corrosion Mechanism and Electrochemical Reactions on Alloy 690 in Simulated Primary Coolant of Water-Water Energy Reactors. [PDF]

Materials (Basel)
Bojinov M, Betova I, Karastoyanov V.
europepmc   +1 more source