STUDY ON CRITICALITY AND NEUTRONIC SAFETY PARAMETERS OF NUSCALE FUEL ASSEMBLY
Urania, 2021 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
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Neutronic and Thermalhydraulic Evaluation of Annular Fuel in PWR with Three Different Nanofluids
Sakarya Üniversitesi Fen Bilimleri Enstitüsü Dergisi, 2022 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
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Experimental investigation of PWR accident scenarios at the PKL test facility [PDF]
E3S Web of Conferences, 2019 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
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Verification and validation of STREAM/RAST-K for PWR analysis
Nuclear Engineering and Technology, 2019 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
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Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600 [PDF]
, 2006 In the present study alloy 600 was tested in simulated pressurised water reactor (PWR) primary water, at 360 °C, under an hydrogen partial pressure of 30 kPa. These testing conditions correspond to the maximum sensitivity of alloy 600 to crack initiation.
Andrieu, Eric +5 more
core +2 more sources
PACTEL and PWR PACTEL Test Facilities for Versatile LWR Applications
Science and Technology of Nuclear Installations, 2012 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 +1 more source
The core surveillance system SCORPIO and its validation against measured pressurised-water reactor plant data [PDF]
Modeling, Identification and Control, 1987 The computerised core surveillance system SCORPIO is described. Main modules in the system arc an interactive communication system with a function keyboard and a fully graphic colour screen; a strategy generator which proposes how to operate the reactor ...
Øivind Berg +2 more
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Corrosion and Materials Degradation, 2022 The radiolysis of water is a significant cause of corrosion damage in the primary heat transport systems (PHTSs) of water-cooled, fission nuclear power reactors (BWRs, PWRs, and CANDUs) and is projected to be a significant factor in the evolution of ...
Digby D. Macdonald, George R. Engelhardt
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Exergy analysis of a PWR nuclear steam supply system - II part: a case study [PDF]
, 2018 The paper shows the results of the exergetic analysis of the Nuclear Steam Supply System (NSSS) of the MARS Pressurized Light Water Reactor using the theoretical methodology described in the authors’ previous works [1] and [2].
Ferroni, Luisa, Natale, Antonio
core +1 more source
Estimation of neutron fluence distribution within German PWR components for decommissioning studies [PDF]
EPJ Web of ConferencesOn 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
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