2015: International Conference on Modelling and Simulation in Nuclear Science and Engineering | Proceedings of the Canadian Nuclear Society

New Exploration on TMSR: Modeling and Simulation

Shengyi Si, Qichang Chen, Hua Bei, Jinkun Zhao

PDF

Physical Design for a 100MWth Small Modular Natural Circulation Lead or Lead-alloy Cooled Fast Reactors Core

Chong Chen, Hongli Chen, Haoran Zhang, Zhao Chen, Qin Zeng

PDF

Mitigation of End Flux Peaking in CANDU Fuel Bundles using Neutron Absorbers

Dylan Pierce, Paul K. Chan, Wei Shen

PDF

Neutronic Research on Gas-cooled Travelling Wave Fast Reactor

Jinyang Li, Long Gu, Dawei Wang, Changping Qing

PDF

Neutronic characterization of GFR demonstrator unit

Jan Hascik, Stefan Cerba, Jakub Luley, Branislav Vrban

PDF

Modelling of Xe-135m for Evaluation of the CANDU6 Power Coefficient of Reactivity

Jaeha Kim, Yonghee Kim, Kwangsoo Kim

PDF

Application of Classroom Simulators in the Training of Managers at CANDU Plants

George Bereznai, Khalid Rizk

PDF

Development of Upgraded Full-Core 3D Diffusion Models for the Pickering Stations

Benoit Arsenault, Zlatko Catovic, Sergiy Shaula, P. David Buchan

PDF

CANDU®-Like Fields For Neutron Dosimetry

Samy El-Jaby, Jovica Atanackovic

PDF

A Fast Resonance Interference Treatment Scheme with Subgroup Method

Liangzhi Cao, Qingming He, Hongchun Wu, Tiejun Zu, Wei Shen

PDF

Preliminary Performance Evaluation of On-the-Fly Doppler Broadening Capability for Monte Carlo Simulation in MCS

Azamat Khassenov, Sooyoung Choi, Hyunsuk Lee, Peng Zhang, Youqi Zheng, Deok Jung Lee

PDF

Analysis of Resonance Self-Shielding Effect of Gold Foils under Low Energy

Bo Yang, Yun Bai, XinXin Lu, ZiJie Han

PDF

A New Coupled System for BWR Nuclear Fuel Management Problems

Alejandro Castillo, Juan Jose Ortiz-Servin, Jose Luis Montes-Tadeo, Raul Perusquia, Roberto Leonel Marinez Rizos

PDF

CRANE: A New Scale Super-Sequence for Neutron Transport Calculations

Congjian Wang, Hany S. Abdel-Khalik, Ugur Mertyurek

PDF

Particle Motion in Sudden Contraction & Sudden Expansion Structures

Xinru Lin, Xiao Yan, Zejun Xiao

PDF

Fixed Setpoints Introduce Error in Licensing Probability

Frank Laratta

PDF

Numerical Investigation on Wake of Single Air Bubble Rising in Narrow Rectangular Channel

Liqin Zhang, Y.P. Huang, Y.F. Zan, J.F. Wang

PDF

On CFD Methodology for Simulations of Whole Reactor Flow

Xue-Nong Chen

PDF

Assessment of the No-Core Melt Concept for the Canadian SCWR Conceptual Design

Chukwudi Azih

PDF

PHWR Modelling and Simulation Issues for SAM Enhancement in Korea after Fukushima

Yong Man Song, DongHa Kim, Sooyong Park, JinHo Song

PDF

Depletion Calculations of Adjuster Rods in Darlington

Benoit Arsenault, Kwok Tsang

PDF

Development of Parallel 3D Discrete Ordinates Transport Program on JASMIN Framework

Tangpei Cheng, Junxia Wei, Huayun Shen, Bin Zhong, Li Deng

PDF

Development of First Full Scope Commercial CANDU-6 Fuel Handling Simulator

William Crawford, Jeffrey M. McInerney, Eric S. Moran, Jeffrey W. Nice, Donald M. Sinclair, Stephen Somerville, E. Can Usalp, Murat Usalp

PDF

Virtual Reality-based Simulation System for Nuclear and Radiation Safety SuperMC/RVIS

Tao He, Mengyun Cheng, Shengpeng Yu, Jing Song, Jinbo Zhao, Qi Yang, Shaoheng Zhou, Leiming Shang, Pengcheng Long, Liqin Hu, Lijuan Hao

PDF

An MCNP Feasibility Study for a Switchable Gamma Source

Ruxandra Dranga, Glen A. McRae

PDF

Modelling the Radial Distribution of the Inventory of U and Pu Isotopes in PWR Fuel Rods at High Burnup

Lucas Furlano, Armando Marino

PDF

Study of Neutronics and Thermal-hydraulics Coupling with RMC/COBRA-EN System

S.C. Liu, J.K. Yu, J.G. Liang, K. Wang

PDF

CANDU-PHWR Core Analysis by the McCARD/SCAN Code System

Seung Yeol Yoo, Hyung Shim, Chang Hyo Kim

PDF

Multilevel Parallel Strategy on Monte Carlo Particle Transport for the Large-Scale Full-Core Pin-by-Pin Simulations

BaoYin Zhang, Gang Li, Wei Wang, Danhua Shangguan, Li Deng

PDF

Asynchronous Transport Algorithm For Domain Decomposed In JMCT Monte Carlo code

Gang Li, BaoYin Zhang, Li Deng, Zeyao Mo, Yan Ma, Rui Li, Danhua Shangguan, Yuanguang Fu

PDF

OpenMC - TD, A New Module for Monte Carlo Time Dependent Simulations Used to Simulate a CANDU-6 Cell LOCA Accident

Mehdi Mahjoub, Jean Koclas

PDF

Perspectives on the Development of Next Generation Reactor Systems Safety Analysis Codes

Hongbin Zhang

PDF

The Development and Validation of a Natural Circulation Analysis Code for Marine Reactors

Houjun Gong, Xingtuan Yang, Yanping Huang, Shengyao Jiang

PDF

Applicability of Simplified Human Reliability Analysis Methods for Severe Accidents

Ronald Boring, Shawn StGermain, Georgeta Banaseanu, Hayat Chatri, Yolande Akl

PDF

Atomistic Modelling of Aqueous Systems Relevant to the SCWR

Dimitrios Kallikragas, Igor Svishchev

PDF

Benchmarking of Fast-Running Software Tools Used to Model Releases During Nuclear Accidents

Peter Devitt, Alexandre Viktorov

PDF

Code Development of Total Sensitivity and Uncertainty Analysis for Reactor Physics Calculations

Chenghui Wan, Liangzhi Cao, Hongchun Wu, Tiejun Zu, Wei Shen

PDF

Validation of Moderator-Level Reactivity Coefficient Using Station Data

Mohamed Younis, Iouri Martchouk, P. David Buchan

PDF

Probabilistic Error Bounds for Reduced Order Modeling

Mohammad G. Abdo, Congjian Wang, Hany S. Abdel-Khalik

PDF

Physics-guided Coverage Mapping (PCM): A New Methodology to Avoid Model Calibration

Hany S. Abdel-Khalik, Ayman I. Hawari, Congjian Wang

PDF

A Mesh-Free Method for Approximate Solution of Neutron Transport Equation

Dimitar V. Altiparmakov

PDF

Leakage-Corrected Discontinuity Factors for PHWR Lattices - A Simple Test

E. Usalp, Eleodor Nichita

PDF

A Reformulation of the Transport-Transport SPH Equivalence Technique

Alain Hebert

PDF

A New Method to Diagnose the Time Constant of a Subcritical Device

Yun Bai, Bo Yang, Li Deng, XianJue Peng

PDF

Analysis of a SBO in a CANDU Using RELAP/SCDAPSIM/MOD3.6

Elena Dinca, Daniel Dupleac, Roxana-Mihaela Nistor-Vlad, Analia Bonelli, Larry Siefken, C. Allison, Judith K. Hohorst

PDF

Simulation of a Turbine Trip Transient at Embalse NPP with Full-Circuit CATHENA Model

Arnaldo Rabiti, Ana Parrondo, Pablo Serrano, Antoine Sablayrolles, Hermes Damiani

PDF

Assessment of Human Interactions Credited in Canadian PSA Using SPAR-H Method

Hayat Chatri, Georgeta Banaseanu, Yolande Akl, Ronald Boring, Shawn StGermain

PDF

Numerical Predictions of Heat Transfer and Pressure Tube/Calandria Tube Deformation During Calandria-Tube Strain Contact Boiling (CSCB) Tests

Aurelian Tanase, Jacek Szymanski, Magdy El-Hawary, Aleksandar Delja

PDF

Modelling of Field Programmable Gate Array Based Nuclear Power Plant Safety Systems Part I: Failure Mode and Effects Analysis

Phillip McNelles, Zhao Chang Zeng, Guna Renganathan

PDF

Articles