Results 31 to 40 of about 2,496 (228)
Sensitivity Analysis of Continuous-energy Nuclear Data and Its Application in AP1000
Yuanzineng kexue jishu, 2022 AP1000 is the typical third-generation nuclear power technology. The sensitivity analysis of continuous-energy nuclear data for AP1000 is the basis of uncertainty quantification which plays an important role in subsequent safety analysis for AP1000 ...
HUANG Jinlong;CAO Liangzhi;HE Qingming;LI Jie;SHEN Wei
doaj
Uncertainties impact on the major FOMs for severe accidents in CANDU 6 nuclear power plant
Nuclear Engineering and Technology, 2023 In the nuclear safety studies, a new trend refers to the evaluation of uncertainties as a mandatory component of best-estimate safety analysis which is a modern and technically consistent approach being known as BEPU (Best Estimate Plus Uncertainty).The ...
R.M. Nistor-Vlad, D. Dupleac, G.L. Pavel
doaj +1 more source
, 2021 Repository containing the Serpent 2 input files and output data for a 3D CANDU-6 quarter core.The "Input Files" folder contains:- The Portable Batch System file - The refueling and error checking python script- The Serpent 2 CANDU-6 model files.
Burkhardt, A (via Mendeley Data)
core +1 more source
PERDAGANGAN CANDU DI SUMATERA TENGAH PADA MASA REVOLUSI 1945-1949 [PDF]
, 2022 ABSTRAK Skripsi ini berjudul “Perdagangan Candu Di Sumatera Tengah Pada Masa Revolusi 1945-1949”. Perdagangan candu dilakukan untuk mendapatkan dana biaya perang pada masa Revolusi di Sumatera Tengah khususnya dan Indonesia umumnya.
Rafiqatul, Afwa
core
Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis
Science and Technology of Nuclear Installations, 2015 The current neutronics design methodology of CANDU-PHWRs based on the two-step calculations requires determining not only homogenized two-group constants for ordinary fuel bundle lattice cells by the WIMS-AECL lattice cell code but also incremental two ...
Seung Yeol Yoo +2 more
doaj +1 more source
Analysis of fuel rejuvenation times in a fusion breeder reactor fuelled with a mixture of uranium-thorium oxides for the CANDU reactor [PDF]
Nuclear Technology and Radiation Protection, 2017 This study presents the determination of fuel rejuvenation times in a D-T fusion breeder reactor fuelled with a mixture of natUO2 and ThO2 for multi-reuse of nuclear fuels in CANDU-37 reactors.
Bakir Gizem, Yapici Huseyin
doaj +1 more source
Iron and radioactivity transport code package for multiple CANDU designs
Nuclear Engineering and TechnologyTo ensure the safe and reliable operation of nuclear reactors, predictive modelling of iron and activity transport is a necessary tool for examining how changes to key chemistry parameters impact the distribution of corrosion products and corresponding ...
C. Perry, O. Palazhchenko
doaj +1 more source
Physics Study of Canada Deuterium Uranium Lattice with Coolant Void Reactivity Analysis
Nuclear Engineering and Technology, 2017 This study presents a coolant void reactivity analysis of Canada Deuterium Uranium (CANDU)-6 and Advanced Canada Deuterium Uranium Reactor-700 (ACR-700) fuel lattices using a Monte Carlo code.
Jinsu Park +4 more
doaj +1 more source
Quality of Local Rice Genotypes and Their Improvement With Urea and Fermented Rice Husk Ash
Advances in Agriculture, Volume 2026, Issue 1, 2026.The quality and nutritional value of rice (Oryza sativa L.) are important for its economic value and for addressing malnutrition in developing countries. This study aims to identify local rice genotypes exhibiting high quality and high protein across various agroecosystems, and to increase rice protein content (PC) through the application of urea and ...
Nurhayati Nurhayati +11 more
wiley +1 more source
Nuclear Engineering and Technology, 2013 Two different kinds of nuclear power plants produce a substantial amount of spent fuel annually in Korea. According to the current projection, it is expected that around 60,000 MtU of spent fuel will be produced from 36 PWR and APR reactors and 4 CANDU ...
HEUI-JOO CHOI +2 more
doaj +1 more source