Results 31 to 40 of about 17,249 (229)

OVERVIEW OF THE HINKLEY POINT C EPR PROJECT ‘J0’ AND BEYOND [PDF]

open access: yesEPJ Web of Conferences, 2021
The twin unit EPR construction at Hinkley Point C is the first nuclear new build project to be undertaken in the UK in a generation. Moreover, it is now the country’s only new reactor project still in progress.
Dyrda James, Morrison Richard
doaj   +1 more source

SURROGATE MODEL OPTIMIZATION OF A ‘MICRO CORE’ PWR FUEL ASSEMBLY ARRANGEMENT USING DEEP LEARNING MODELS [PDF]

open access: yesEPJ Web of Conferences, 2021
This paper investigates the applicability of surrogate model optimization (SMO) using deep learning regression models to automatically embed knowledge about the objective function into the optimization process.
Whyte Andy, Parks Geoff
doaj   +1 more source

Simulations of the AP1000-based reactor core with SERPENT computer code [PDF]

open access: yesArchive of Mechanical Engineering, 2018
The paper presents the core design, model development and results of the neutron transport simulations of the large Pressurized Water Reactor based on the AP1000 design.The SERPENT 2.1.29 Monte Carlo reactor physics computer code with ENDF/BVII and JEFF3.
Piotr Darnowski   +4 more
doaj   +1 more source

POSSIBILITIES OF 3D MACHINING OF MATERIALS BY ABRASIVE WATER JETS

open access: yesGeoScience Engineering, 2019
Machining of materials through the classical way, i.e. using conventional tools for turning, drilling, milling, grinding and polishing, has some limits that can be overcome applying an abrasive water jet (AWJ).
Jan RAŠKA   +3 more
doaj   +1 more source

Platelet to white blood cell ratio was an independent prognostic predictor in acute myeloid leukemia

open access: yesHematology, 2022
Background Recently, platelet to white blood cell ratio (PWR) was reported as an independent prognostic predictor in acute promyelocytic leukemia. Acute myeloid leukemia (AML) often presents with abnormal platelet counts and white blood cell counts (WBC)
Shuqi Zhao   +4 more
doaj   +1 more source

Criticality safety analysis of spent fuel pool for a PWR using UO2, MOX, (Th-U)O2 and (TRU-Th)O2 fuels

open access: yesBrazilian Journal of Radiation Sciences, 2019
A spent fuel pool of a typical Pressurized Water Reactor (PWR) was evaluated for criticality studies when it uses reprocessed fuels. PWR nuclear fuel assemblies with four types of fuels were considered: standard PWR fuel, MOX fuel, thorium-uranium fuel ...
Claubia Pereira   +4 more
doaj   +1 more source

SERPENT2-SUBCHANFLOW-TRANSURANUS PIN-BY-PIN DEPLETION CALCULATIONS FOR A PWR FUEL ASSEMBLY [PDF]

open access: yesEPJ Web of Conferences, 2021
This work presents the results for a coupled neutronic-thermalhydraulic-thermomechanic pin-level depletion calculation of a PWR fuel assembly using Serpent2-SUBCHANFLOW-TRANSURANUS.
García Manuel   +10 more
doaj   +1 more source

Effect of surface preparation on the corrosion of austenitic stainless steel 304L in high temperature steam and simulated PWR primary water [PDF]

open access: yes, 2012
The corrosion behavior of 304L grade stainless steel (SS) in high-temperature steam and in a simulated Pressurized Water Reactor (PWR) is studied. The goal was to characterize the nature of the oxide coating generated during 500 h exposure of samples in ...
Cissé, Sarata   +4 more
core   +1 more source

Comportamiento del acero de baja aleación SA-508 y del acero al carbono A-410b en las condiciones de operación y parada del circuito primario de los reactores de agua ligera tipo PWR

open access: yesRevista de Metalurgia, 2000
En este trabajo se ha determinado la cinética de corrosión del acero de baja aleación SA-508 y del acero al carbono A-410b en condiciones que simulan la operación y la parada de los reactores de agua ligera a presión.
María del Sol García-Redondo   +2 more
doaj   +1 more source

VALIDATION OF WIMS11 FOR SMALL MODULAR REACTOR ANALYSIS [PDF]

open access: yesEPJ Web of Conferences, 2021
The WIMS (Winfrith Improved Multigroup Scheme) reactor physics code is actively being developed for whole core modelling of a range of Small Modular Reactor types including the Pressurized Water Reactor (PWR), High Temperature Reactor (HTR), and Liquid ...
Smith Peter   +8 more
doaj   +1 more source

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