Recent R&D around the Monte-Carlo code Tripoli-4 for criticality calculation (original) (raw)

TRIPOLI-4® Monte Carlo code ITER A-lite neutronic model validation

Clément Fausser, Yi-Kang Lee

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Criticality qualification of a new Monte Carlo code for reactor core analysis

Παναγιώτα Σάββα, Thanasis Zisis

Annals of Nuclear Energy, 2009

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A Monte-Carlo Benchmark of TRIPOLI-4® and MCNP on ITER neutronics

Bruno Fontaine

EPJ Web of Conferences, 2017

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Fission matrix based Monte Carlo criticality calculations

Waclaw Gudowski

Annals of Nuclear Energy, 2009

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Fission Neutron Multiplicity in MCNP6 Criticality Calculations

Anil Prinja

2017

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Recent developments in the TRIPOLI-4® Monte-Carlo code for shielding and radiation protection applications

Yi-Kang Lee

EPJ Web of Conferences

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The RAPID Fission Matrix Approach to Reactor Core Criticality Calculations

Alireza Haghighat

Nuclear Science and Engineering, 2018

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Undersampling diagnostics by fission matrix in Monte Carlo criticality calculations

Jingang Liang

Annals of Nuclear Energy, 2013

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Variance reduction adjustment in Monte Carlo TRIPOLI-4® neutron gamma coupled calculations

Yi-Kang Lee

Progress in Nuclear Science and Technology, 2014

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MCNP: Neutron benchmark problems

David Cardon

1991

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Monte Carlo Codes for Neutron Buildup Factors

Dubravko Pevec

2018

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Analysis of the ITER computational shielding benchmark with the Monte Carlo TRIPOLI-4® neutron gamma coupled calculations

Yi-Kang Lee

Fusion Engineering and Design, 2016

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New Improved Nuclear Data for Nuclear Criticality and Safety

S. Kopecky

2011

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Criticality Benchmarking of ANET Monte Carlo code

Thalia Xenofontos

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An updated nuclear criticality slide rule

Calvin Hopper

1998

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A global approach to the physics validation of simulation codes for future nuclear systems

Giuseppe Palmiotti

Annals of Nuclear Energy, 2009

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Acceleration of Monte Carlo Criticality Calculations Using Deterministic-Based Starting Sources

Ahmad Ibrahim

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Burnup dependent Monte Carlo neutron physics calculations of IAEA MTR benchmark

Sikander M Mirza

Progress in Nuclear Energy, 2015

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Multi-core performance studies of a Monte Carlo neutron transport code

Kord Smith

The International Journal of High Performance Computing Applications, 2013

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Verification of Monte Carlo calculations of the neutron flux in typical irradiation channels of the TRIGA reactor, Ljubljana

Marko Maucec

Journal of Radioanalytical and Nuclear Chemistry, 2003

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High Performance Parallel Monte Carlo Transport Computations for ITER Fusion Neutronics Applications (Selected Papers of the Joint International Conference of Supercomputing in Nuclear Applications and Monte Carlo : SNA + MC 2010)

Arkady Serikov

Progress in nuclear science and technology, 2011

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Criticality calculations with MCNP{sup TM}: A primer

Robert Busch

1994

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Monte Carlo simulation of the Greek Research Reactor neutron irradiation facilities

F. Tzika

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2007

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Benchmark of neutron production cross sections with Monte Carlo codes

Lawrence Heilbronn

Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, 2018

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Correlated Production and Analog Transport of Fission Neutrons and Photons using Fission Models FREYA, FIFRELIN and the Monte Carlo Code TRIPOLI-4®

O. Litaize

EPJ Web of Conferences, 2018

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Neutron Deep Penetration Calculations in Light Water with Monte Carlo TRIPOLI-4® Variance Reduction Techniques

Yi-Kang Lee

EPJ Web of Conferences, 2017

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ITER Neutronics Modeling Using Hybrid Monte Carlo/Deterministic and CAD-Based Monte Carlo Methods

Ahmad Ibrahim

Nuclear Technology, 2011

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Advances in the treatment of the electromagnetic cascade in the TRIPOLI-4® Monte-Carlo code

Francois-Xavier Hugot

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Validation of the MORET 5 Monte Carlo Transport Code on Reactor Physics Experiments

Isabelle Duhamel

Journal of Nuclear Engineering

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A new model with Serpent for the first criticality benchmarks of the TRIGA Mark II reactor

Antonio Cammi

Annals of Nuclear Energy

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Neutronics analysis of the international thermonuclear experimental reactor (ITER) MCNP 'Benchmark CAD Model'with the ATTILA discrete ordinance code

Russell Feder

Fusion Eng. Des, 2008

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FASTER 3: A generalized-geometry Monte Carlo computer program for the transport of neutrons and gamma rays. Volume 1: Summary report

thomas m jordan

1970

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