David R. Novog : rechercher sur Z-Library

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1

Measurement, simulation and uncertainty quantification of the neutron flux at the McMaster Nuclear Reactor

MacConnachie, Elizabeth L., Novog, David R.

Journal:

Annals of Nuclear Energy

Année:

2021

Fichier:

PDF, 376 KB

2021

2

A generalized failure map for fuel elements subject to a power pulse

John C. Luxat, David R. Novog

Journal:

Nuclear Engineering and Design

Année:

2011

Langue:

english

Fichier:

PDF, 680 KB

english, 2011

3

Evaluation of ASSERT-PV V3R1 against the PSBT Benchmark

Leung, Kenneth H., Novog, David R.

Journal:

Science and Technology of Nuclear Installations

Année:

2012

Langue:

english

Fichier:

PDF, 2.42 MB

english, 2012

4

Selected Papers from OECD-NEA PSBT Benchmark

Avramova, Maria, Manera, Annalisa, Novog, David, Cuervo, Diana, Petruzzi, Alessandro

Journal:

Science and Technology of Nuclear Installations

Année:

2014

Langue:

english

Fichier:

PDF, 83 KB

english, 2014

5

Coupled 3D neutron kinetics and thermalhydraulic characteristics of the Canadian supercritical water reactor

Hummel, David William, Novog, David Raymond

Journal:

Nuclear Engineering and Design

Année:

2016

Langue:

english

Fichier:

PDF, 4.39 MB

english, 2016

6

RELAP5 simulation of CANDU Station Blackout accidents with/without water make-up to the steam generators

Zhou, Feng, Novog, David R.

Journal:

Nuclear Engineering and Design

Année:

2017

Langue:

english

Fichier:

PDF, 6.49 MB

english, 2017

7

Investigation of Fuel Burnup Impacts on Reactor Physics Phenomena in the Canadian Pressure Tube Supercritical Water-cool Reactor

Moghrabi, Ahmad, Novog, David

Journal:

Journal of Nuclear Engineering and Radiation Science

Année:

2017

Langue:

english

Fichier:

PDF, 941 KB

english, 2017

8

Optimization of the Canadian SCWR Core Using Coupled 3D Reactor Physics and Thermalhyraulics Calculations

Salaun, Frederic, Novog, David

Journal:

Journal of Nuclear Engineering and Radiation Science

Année:

2017

Langue:

english

Fichier:

PDF, 2.90 MB

english, 2017

9

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

Salaun, Frederic, Novog, David R.

Journal:

Science and Technology of Nuclear Installations

Année:

2018

Langue:

english

Fichier:

PDF, 5.78 MB

english, 2018

10

Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors

Younan, Simon, Novog, David

Journal:

Science and Technology of Nuclear Installations

Année:

2018

Langue:

english

Fichier:

PDF, 1.85 MB

english, 2018

11

Comparison of the Subchannel Code CTF to Steady-State and Transient Heat Transfer Experiments at Intermediate Pressures in Water

Wu, Pan, Novog, David

Journal:

Nuclear Technology

Année:

2018

Langue:

english

Fichier:

PDF, 1.89 MB

english, 2018

12

Quantification of system uncertainties in activation experiments at nuclear research reactors

MacConnachie, Elizabeth Laurel, Novog, David, Day, Simon

Journal:

Annals of Nuclear Energy

Année:

2019

Langue:

english

Fichier:

PDF, 1.10 MB

english, 2019

13

Extension and preliminary validation of the Polaris lattice physics code for CANDU analysis

Younan, Simon, Novog, David

Journal:

Nuclear Engineering and Design

Année:

2020

Fichier:

PDF, 2.50 MB

2020