PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications [PDF]
This paper describes construction and experimental research activities with two test facilities, PACTEL and PWR PACTEL. The PACTEL facility, comprising of reactor pressure vessel parts, three loops with horizontal steam generators, a pressurizer, and ...
Virpi Kouhia +5 more
doaj +2 more sources
Verification and validation of STREAM/RAST-K for PWR analysis [PDF]
This paper presents the verification and validation (V&V) of the STREAM/RAST-K 2.0 code system for a pressurized water reactor (PWR) analysis. A lattice physics code STREAM and a nodal diffusion code RAST-K 2.0 have been developed by a computational ...
Jiwon Choe +8 more
doaj +2 more sources
Estimation of neutron fluence distribution within German PWR components for decommissioning studies [PDF]
On 15 April 2023, the last German NPPs were shut down. The final shutdown is followed by a post-operational phase in which measures can be carried out to prepare for the NPPs dismantling and decommissioning.
Rachamin Reuven +3 more
doaj +3 more sources
Thorium nuclear reactors [PDF]
U ovom radu tematizirani su nuklearni reaktori temeljeni na toriju. Spomenut je MSR koji predstavlja jednu od sedam klasa reaktora nove generacije, poznatih kao 4. generacija. Istaknute su brojne prednosti ovog tipa reaktora u usporedbi s LWR-om. Posebno
Busić, Nenad
core +4 more sources
STUDY ON CRITICALITY AND NEUTRONIC SAFETY PARAMETERS OF NUSCALE FUEL ASSEMBLY
STUDY ON CRITICALITY AND NEUTRONIC SAFETY PARAMETERS OF NUSCALE FUEL ASSEMBLY. NuScale, a typical Pressurized Water Reactor (PWR) Small Modular Reactors (SMRs), offers a new opportunity for the future of nuclear industry.
Zuhair Zuhair +3 more
doaj +1 more source
Pwr effect on crack initiation under equi-biaxial loading [PDF]
International audienceThe lifetime extension of the nuclear power stations is considered as an energy challenge worldwide. That is why, the risk analysis and the study of various effects of different factors that could potentially represent a hazard to a
Dhahri, H. +5 more
core +3 more sources
Neutronic and Thermalhydraulic Evaluation of Annular Fuel in PWR with Three Different Nanofluids
In pressurized nuclear reactors, one of the fuel design principles is the fuel centerline temperature limit. Since the thermal conductivity of UO2 is not high, the temperature increases rapidly from the fuel surface to the fuel center.
Ali Tiftikçi
doaj +1 more source
A comparative study on severe accident phenomena related to melt progression in SFR and PWR [PDF]
International audienceThe nuclear safety approach has to cover accident sequences involving core degradation in order to develop reliable mitigation strategies for both existing and future reactors.
Bachrata, Andrea +3 more
core +1 more source
Experimental investigation of PWR accident scenarios at the PKL test facility [PDF]
PKL is the only test facility in Europe that replicates the entire primary side and the most important parts of the secondary side of western-type Pressurized Water Reactors (PWR) in the scale of 1:1 in heights.
Bryk Rafał +2 more
doaj +1 more source
Qualification of nuclear reactor nominal power upgrades.
In extreme wartime conditions due to damage/destruction/occupation of a number of power generating facilities and continuous damage/destruction of the critical energy infrastructure of Ukraine, the priority and urgent task of the operating organization ...
Володимир Іванович Скалозубов +4 more
doaj +5 more sources

