Results 31 to 40 of about 9,551,406 (202)
The large $ \mathcal{N} $ = 4 superconformal $ \mathcal{W} $ ∞ algebra [PDF]
ISSN:1126-6708ISSN:1029-8479ISSN:1029 ...
Gaberdiel, Matthias R. +7 more
core +1 more source
Evaluating the coolant void reactivity for assemblies of CANDU lattices [PDF]
Dragon code -- Neutron transport equation -- Collision probability method -- Reactivity formula -- Homogenization technique -- Cell model -- Standard CANDU-6 geometry -- Square pin model for CANDU-6 -- Multi-step cell simulation -- Direct cell simulation
Talebi, Farshad
core +1 more source
BACKUP AND ULTIMATE HEAT SINKS IN CANDU REACTORS FOR PROLONGED SBO ACCIDENTS
In a pressurized heavy water reactor, following loss of the primary coolant, severe core damage would begin with the depletion of the liquid moderator, exposing the top row of internally-voided fuel channels to steam cooling conditions on the inside and ...
T. NITHEANANDAN, M.J. BROWN
doaj +1 more source
ANALISIS KONSEP CANDU ADVANCED PASSIVE MODERATOR PADA OPERASI NORMAL MENGGUNAKAN CATHENA. CANDU
ANALISIS KONSEP CANDU ADVANCED PASSIVE MODERATORPADA OPERASI NORMAL MENGGUNAKAN CATHENA. CANDU – advanced passive moderator (APM) mempunyai konsep, bahwa reaktivitas positif fraksi hampa dihilangkan dengan jalan mengurangi densitas moderator.
Alfa, Sudjatmi K
core +1 more source
SAFETY ANALYSIS METHODOLOGY FOR AGED CANDU® 6 NUCLEAR REACTORS
This paper deals with the Safety Analysis for CANDU® 6 nuclear reactors as affected by main Heat Transport System (HTS) aging. Operational and aging related changes of the HTS throughout its lifetime may lead to restrictions in certain safety system ...
WOLFGANG HARTMANN, JONG YEOB JUNG
doaj +1 more source
Iron and radioactivity transport code package for multiple CANDU designs
To 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
A Lattice-Based Monte Carlo Evaluation of Canada Deuterium Uranium-6 Safety Parameters
Important safety parameters such as the fuel temperature coefficient (FTC) and the power coefficient of reactivity (PCR) of the CANada Deuterium Uranium (CANDU-6) reactor have been evaluated using the Monte Carlo method.
Yonghee Kim, Donny Hartanto, Woosong Kim
doaj +1 more source
Zirconium remains the main structural material for thermal reactors due to the small capture cross section of thermal neutrons. In the period of stricter safety requirements for reactors with a simultaneous increase in operating parameters, predicting ...
M.G. Isaenkova +6 more
doaj +1 more source
Quality of Local Rice Genotypes and Their Improvement With Urea and Fermented Rice Husk Ash
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
STUDI PARAMETER PENUKAR PANAS UNTUK REAKTOR CANDU 6 YANG DISEMPURNAKAN
STUDI PARAMETER PENUKAR PANAS UNTUK REAKTOR CANDU 6 YANG DISEMPURNAKAN. Sistem moderator pasif untuk reaktor CANDU 6 yang disempurnakan membutuhkan penukar panas dengan ukuran kecil dan mempunyai koefisien tahanan yang kecil pula pada sisi cangkangnya ...
Umar, Efrizon
core +1 more source

