Results 21 to 30 of about 190,515 (293)

Intermittent quakes and record dynamics in the thermoremanent magnetization of a spin-glass [PDF]

, 2006
A novel method for analyzing the intermittent behavior of linear response data in aging systems is presented and applied to spin-glass thermoremanent magnetization (TRM) (Rodriguez et al. Phys. Rev. Lett. 91, 037203, 2003).
G. F. Rodriguez, G. G. Kenning, L. Buisson, L. Struik, N. G. V. Kampen, P. Sibani, Paolo Sibani   +6 more
core   +1 more source

Analysis of ESFR Decay Heat Removal Systems in Protected Station Blackout

Journal of Nuclear Engineering and Radiation Science, 2021
Abstract As part of the European sodium fast reactor (ESFR)-safety measures assessment and research tools (SMART) project, safety assessments are being conducted on the updated ESFR design. An important part of the study is the evaluation of the reactor's behavior within hypothetical accidental conditions to assess and ensure that the ...
Bodi, Janos, Ponomarev, Alexander, Bubelis, Evaldas, Mikityuk, Konstantin   +3 more
openaire   +2 more sources

Decay Heat Removal and Transient Analysis in Accidental Conditions in the EFIT Reactor

Science and Technology of Nuclear Installations, 2008
The development of a conceptual design of an industrial-scale transmutation facility (EFIT) of several 100 MW thermal power based on accelerator-driven system (ADS) is addressed in the frame of the European EUROTRANS Integral Project. In normal operation,
Giacomino Bandini, Paride Meloni, Massimiliano Polidori, Maddalena Casamirra, Francesco Castiglia, Mariarosa Giardina   +5 more
doaj   +1 more source

Core thermal-hydraulics analysis during dipped-type direct heat exchanger operation in natural circulation conditions

Mechanical Engineering Journal, 2022
A direct reactor auxiliary cooling system (DRACS) under natural circulation (NC) conditions with a dipped-type direct heat exchanger (D-DHX) in the upper plenum of a reactor vessel (RV) has been investigated for enhancing the safety of sodium-cooled fast
Erina HAMASE, Yasuhiro MIYAKE, Yasutomo IMAI, Norihiro DODA, Ayako ONO, Masaaki TANAKA   +5 more
doaj   +1 more source

CFD Investigation of MHTGR Natural Circulation and Decay Heat Removal in P-LOFC Accident

Frontiers in Energy Research, 2020
One of the key postulated accidents in a high-temperature gas-cooled reactor (HTGR) is the pressurized loss of forced cooling (P-LOFC) of the primary loop, which can be triggered by its primary helium circulator trip or turbine trip.
Chengqi Wang, Xiaodong Sun, Piyush Sabharwall   +2 more
doaj   +1 more source

Simulation of Steady States of Helium Loop at Long Time Scenarios [PDF]

MATEC Web of Conferences, 2020
The natural circulation helium loop is an experimental facility designed for the research of the possibility of utilizing natural convection cooling for the case of decay heat removal from a fast nuclear reactor.
Világi František, Knížat Branislav, Olšiak Róbert, Mlkvik Marek, Mlynár Peter, Ridzoň František, Urban František   +6 more
doaj   +1 more source

Unique safety features and licensing requirements of the NuScale small modular reactor

Frontiers in Energy Research, 2023
Small modular reactors (SMR) offer a novel approach to the construction and operation of nuclear power plants. The NuScale VOYGR™ plant uses a simplified SMR design that is based on proven light-water reactor technology with substantial improvements in ...
Kent Welter, José N. Reyes, Adam Brigantic   +2 more
doaj   +1 more source

Thermal Characteristics of High Temperature Naturally Circulating Helium Cooling Loop

Journal of Mechanical Engineering, 2018
The paper deals with the process properties in terms of the heat transfer, i.e. the thermal performance of the thermal-process units within a helium loop intended for the testing of the decay heat removal (DHR) from the model of the gas-cooled fast ...
Dzianik František, Gužela Štefan, Puškášová Eva1   +2 more
doaj   +1 more source

On capabilities and limitations of current fast neutron-flux monitoring instrumentation for the DEMO LFR ALFRED [PDF]

, 2016
Among Gen IV projects for future nuclear power plants, Lead cooled Fast Reactors (LFR) seem to be a very interesting solution due to its benefits in terms of fuel cycle, coolant-safety and waste management.
LEPORE , LUIGI, REMETTI, Romolo
core   +1 more source

Numerical Simulation of Natural Circulation Characteristic of Fast Reactor Passive Decay Heat Removal System Based on “1-D System+3-D CFD” Coupled Method

Yuanzineng kexue jishu
The sodium-cooled fast reactor is one of the important reactor types of the fourth-generation advanced nuclear energy system. The safety of sodium-cooled fast reactors is improved by introducing a new passive decay heat removal system.
LU Daogang1, 2, SONG Haijie1, 2, GUO Jinsong1, 2, ZHAO Haiqi1, 2, ZHANG Yuhao1, 2, , , SUI Danting1, 2
doaj   +1 more source