A5056604749- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Nuclear Engineering Thermal-Hydraulics
- Radiation Detection and Scintillator Technologies
- Heat transfer and supercritical fluids
- Oil and Gas Production Techniques
- Image and Signal Denoising Methods
- 3D IC and TSV technologies
- Manufacturing Process and Optimization
- Graphite, nuclear technology, radiation studies
- Electronic Packaging and Soldering Technologies
- Industrial Vision Systems and Defect Detection
- Hydrocarbon exploration and reservoir analysis
Canadian Nuclear Laboratories
2016-2023
Atomic Energy (Canada)
2012-2022
Abstract The supercritical water-cooled reactor (SCWR) is one of the six concepts selected by Generation-IV International Forum (GIF) for future research. This technology a natural evolutionary step current reactors. Canada participant GIF, and under this international endeavor developed Canadian SCWR, which 1200 MWe concept. However, due to high capital cost associated with building large units, nuclear industry rekindled an old concept: Small Reactors (SRs), now small modular reactors...
A joint European Canadian Chinese development of a supercritical water-cooled small modular reactor technology has been in progress since September 2020 the framework Horizon project called ECC-SMART. specific work package dedicated to studying design- and safety-related neutronic parameters physics behavior SCW-SMR support pre-conceptual design process. Three Monte Carlo codes, viz., MCNP, OpenMC, Serpent, were selected for applications code-to-code comparison within Gen-IV SCWR-FQT...
Recent cross-section measurements on gadolinium have raised concerns over the accuracy of moderator poison reactivity coefficient calculations. Measurements been made at ZED-2 (Zero Energy Deuterium) critical facility, Chalk River Laboratories, AECL, to study effect in moderator. Since neutron capture boron is well known, were also with provide calibration data for gadolinium. The used quantify bias full-core simulations using MCNP, a transport code extensively nuclear systems, along...
Dynamic parameters such as prompt neutron generation time are essential to safety analysis of a nuclear reactor. Currently, Monte Carlo based simulation methods relied on for obtaining dynamic parameters. There known disagreements between different codes. Further, the data that all simulations cannot be considered accurate parameter ranges. An independent method getting is desired and code verification purposes. A flux perturbation experiment address this gap introduced in paper. The...
The positions of the components a reactor can change over time, due to radiation damage, sagging, etc. Thus, it is important determine their positions. To satisfy this requirement staff at Point Lepreau Generating Station, method has been developed and demonstrated. This combines use dose rate measurements Monte Carlo simulations. It first involves measuring high γ-ray rates as function position within reactor. Then entails comparing these with In order perform such measurements, silicon...
The objective of this paper is to present the results an evaluation gadolinium isotopes with main focus on 155 Gd and 157 Gd. evaluations were carried out in resolved resonance region using Reich-Moore formalism. originality addition new high-resolution capture cross section measurements performed at neutron time-of-flight, n_TOF facility for enriched samples statistical analysis parameters. was multilevel R-matrix code SAMMY together generalized least-squares technique based Bayes’ theory.