Results 41 to 50 of about 56,822 (209)
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
Severe Accidents Management in PWRs
Procedia Engineering, 2014 AbstractThis paper identifies severe accident management strategies developed for current evolutionary reactors and deals with implementation of some measures to existing nuclear power plants, which do not include severe accident mitigation measures in their original design projects.
Rajzrová, Jana, Jiřičková, Jana
openaire +1 more source
Effect of Zinc injection on the surface CRUD of PWR zirconium alloy
He jishu, 2022 BackgroundThe corrosion products deposited on the surface of pressurized water reactor (PWR) zirconium alloy will form chalk rivers unidentified deposit (CRUD), which will reduce the heat transfer capacity of fuel cladding and affect the primary ...
HU Yisong +4 more
doaj +1 more source
SURROGATE MODEL OPTIMIZATION OF A ‘MICRO CORE’ PWR FUEL ASSEMBLY ARRANGEMENT USING DEEP LEARNING MODELS [PDF]
EPJ 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
WRAP-PWR verification studies [PDF]
, 1980 A modular computational system known as the Water Reactor Analysis Package - Evaluation Model (WRAP-EM) was developed for the Nuclear Regulatory Commission (NRC) to interpret and evaluate reactor vendor EM methods and computed results. A subset of the system (WRAP-PWR-EM) provides the computational tools to perform a complete analysis of loss-of ...
Gregory, M V +4 more
openaire +2 more sources
RELAP5 code study of ROSA/LSTF experiment on a PWR station blackout (TMLB') transient
Mechanical Engineering Journal, 2014 RELAP5 code post-test analysis was performed on one of abnormal transient tests conducted with the ROSA/large scale test facility (LSTF) simulating a PWR station blackout (SBO) transient with the TMLB' scenario in 1995.
Takeshi TAKEDA, Hideo NAKAMURA
doaj +1 more source
, 2002 The equivalence of the covariant renormalization and the partial-wave renormaliz ation (PWR) approach is proven explicitly for the one-loop self-energy correction (SE) of a bound electron state in the presence of external perturbation potentials.
E. A. Uehling +25 more
core +1 more source
A study on Quantization Dimension in complete metric spaces [PDF]
, 2020 The primary objective of the present paper is to develop the theory of quantization dimension of an invariant measure associated with an iterated function system consisting of finite number of contractive infinitesimal similitudes in a complete metric ...
Roychowdhury, Mrinal K., Verma, S.
core +2 more sources
Studi Opsi Daur Bahan Bakar Nuklir Berbasis Reaktor Pwr dan Candu [PDF]
, 2009 STUDI OPSI DAUR BAHAN BAKAR NUKLIR BERBASIS REAKTOR PWR DAN CANDU. Telah dilakukan studi opsi daur bahan nuklir berbasis reaktor PWR dan CANDU. Ada 5 jenis opsi daur berbasis PWR dan CANDU, yaitu: opsi PWR-OT, PWR-MOX, CANDU-OT, DUPIC, dan PWR-CANDU-OT ...
Finahari, I. N. (Ida) +1 more
core +2 more sources
Brazilian Journal of Radiation Sciences, 2022 This work presents the description of the first part of a methodology applied to perform In-Core Fuel Management (ICFM) in Pressurized Water Reactor (PWR).
Pedro Henrique Silva Rodrigues +2 more
doaj +1 more source