Results 91 to 100 of about 2,496 (228)

Auto Sizing of CANDU Nuclear Reactor Fuel Channel Flaws from UT Scans. [PDF]

Sensors (Basel), 2023
Hammad I, Poloni M, Isherwood A, Simpson R.   +3 more
europepmc   +1 more source

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, Ida Nuryatin, Salimy, D. H. (Djati), Salimy, Djati Hoesen, Finahari, I. N. (Ida)   +3 more
core   +1 more source

A REVIEW OF CANDU FEEDER WALL THINNING [PDF]

Nuclear Engineering and Technology, 2010
Flow Accelerated Corrosion is an active degradation mechanism of CANDU feeder. The tight bend downstream to Gray loc weld connection, close to reactor face, suffers significant wall thinning by FAC. Extensive in-service inspection of feeder wall thinning is very difficult because of the intense radiation field, complex geometry, and space restrictions.
openaire   +1 more source

CANDU 9 PHWR

, 2010
The World's Reactors, No. 104, CANDU 9, Canada.
Nuclear Engineering International
core  

Cooling the intact loop of primary heat transport system using Shutdown Cooling System in case of LOCA events

EPJ Nuclear Sciences & Technologies, 2015
The purpose of this paper is to model the operation of the Shutdown Cooling System (SDCS) for CANDU 6 nuclear power plants in case of LOCA accidents, using Flowmaster calculation code, by delimiting models and setting calculation assumptions, input data ...
Icleanu Diana Laura, Prisecaru Ilie, Jianu Iulia Nicoleta   +2 more
doaj   +1 more source

Microstructural Effects on Irradiation Creep of Reactor Core Materials. [PDF]

Materials (Basel), 2023
Griffiths M.
europepmc   +1 more source

Thorium utilization in ACR (Advanced CANDU Reactor) and CANDU-6

, 2020
96
openaire   +1 more source

CANDU 원자로의 실제계측치를 이용한 노심분석

, 1991
학위논문(박사) - 한국과학기술원 : 핵공학과, 1991.2, [ vii, 86 p. ]For operating CANDU reactors using on-power fuelling, the simulation results, which predict neutron flux and power distribution, are very important for economic and safe operations.
Kim, Bong-Ghi, 김봉기
core  

Analysis of Control Rod Drop Accidents for the Canadian SCWR Using Coupled 3-Dimensional Neutron Kinetics and Thermal Hydraulics

Science and Technology of Nuclear Installations, 2018
The Canadian Supercritical Water-cooled Reactor (SCWR), a GEN IV reactor design, is a hybrid design of the well-established CANDU™ and Boiling Water Reactor with water above its thermodynamic critical point.
Frederic Salaun, David R. Novog
doaj   +1 more source

Analisis Konsep Candu Advanced Passive Moderator Pada Operasi Normal Menggunakan Cathena. Candu

, 2001
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, S. K. (Sudjatmi)
core