Analysis of Crystalline Rock Permeability Versus Depth in a Canadian Precambrian Rock Setting
Journal of Geophysical Research: Solid Earth, Volume 126, Issue 5, May 2021., 2021 Abstract Over the last 50 years, there has been an increased interest in characterizing Precambrian crystalline rock, such as the Canadian Shield, to investigate the feasibility of deep geologic repositories for isolating used nuclear fuel from the biosphere.
Andrew P. Snowdon +2 more
wiley +1 more source
Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction [PDF]
, 2015 The denominated instant release fraction (IRF) is considered in performance assessment (PA) exercises to govern the dose that could arise from the repository.
Casas Pons, Ignasi +4 more
core +2 more sources
Determination of burnup limit for CANDU 6 fuel using Monte-Carlo method
Nuclear Engineering and Technology, 2021 KHNP recently has obtained the approval for the commercialization of the modified 37-element (or 37 M) fuel bundle and now is loading the 37 M fuel bundles in CANDU-6 reactors in KOREA. One of the main issues for approval was the burnup limit.
Eun-ki Lee
doaj +1 more source
Tritium supply and use: a key issue for the development of nuclear fusion energy [PDF]
, 2018 Full power operation of the International Thermonuclear Experimental Reactor (ITER) has been delayed and will now begin in 2035. Delays to the ITER schedule may affect the availability of tritium for subsequent fusion devices, as the global CANDU-type ...
Armando B. Antoniazzi +38 more
core +1 more source
THE IMPACT OF POWER COEFFICIENT OF REACTIVITY ON CANDU 6 REACTORS
Nuclear Engineering and Technology, 2013 The combined effects of reactivity coefficients, along with other core nuclear characteristics, determine reactor core behavior in normal operation and accident conditions.
D. KASTANYA +3 more
doaj +1 more source
Nuclear Engineering and Technology, 2017 In any reactor physics analysis, the instantaneous power distribution in the core can be calculated when the actual bundle-wise burnup distribution is known.
Doddy Kastanya
doaj +1 more source
Ultrasonic evaluation of hydrogen concentration and hydride properties in zirconium alloys
e-Journal of Nondestructive Testing, 2023 Various ultrasonic techniques and transducers, used for CANDU reactor pressure tube inspection to detect areas with increased hydrogen concentration, estimate its level, and determine the hydride platelet features (dimensions, orientation, and spacing)
Alex Karpelson
doaj +1 more source
Qualitative and quantitative investigation of the propagation noise in various reactor systems [PDF]
, 2014 The space-dependent neutron noise, induced by propagating perturbations (propagation noise for short) is investigated in a one-dimensional homogeneous model of various reactor systems. By using two-group theory, the noise in both the fast and the thermal
Dykin, Victor +2 more
core +1 more source
CANDU Safety R&D Status, Challenges, and Prospects in Canada
Science and Technology of Nuclear Installations, 2015 In Canada, safe operation of CANDU (CANada Deuterium Uranium; it is a registered trademark of Atomic Energy of Canada Limited) reactors is supported by a full-scope program of nuclear safety research and development (R&D) in key technical areas.
W. Shen, F. Doyle
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