Modelling and neutronic calculation of vvr-m2 fuel assembly and Dalat nuclear research reactor using tripoli4 code and apollo2 code /

Código QR

Modelling and neutronic calculation of vvr-m2 fuel assembly and Dalat nuclear research reactor using tripoli4 code and apollo2 code /

Gardado en:

Detalles Bibliográficos
Autor Principal:	Tran Quoc Duong.
Outros autores:	Eric Dumonteil., Huynh Tan Dat, Jean Michel Do, Yi-Kang Lee
Formato:	Artigo
Idioma:	Vietnamese
Các nhãn:	Engadir etiqueta Sen Etiquetas, Sexa o primeiro en etiquetar este rexistro!

Thư viện lưu trữ:	Thư viện Trường Đại học Đà Lạt

Títulos similares

Neutronics analysis of Dalat nuclear research reactor by MVP/GMVP code /
por: Nguyễn Kiên Cường.

Assessment of CFD codes used in nuclear reactor safety simulations /
por: Smith, B.L..

Irradiation test of mox fuel in the halden reactor and the analysis of measured data with the fuel performance code cosmos /
por: Wiesenack, Wolfgang.

Characterization of neutron spectrum parameters at irradiation channels for neutron activation analysis after full conversion of the Dalat nuclear research reactor to low …
por: Trịnh, Thị Tú Anh
Publicado: (2023)

Characteristics of filtered neutron beam energy spectra at Dalat Reactor
por: Tran, Tuan Anh, et al.
Publicado: (2023)

Fundamental aspects of the performance of nuclear reactor fuel elements
por: Olander, Donald R
Publicado: (2013)

Simulation Design of Thermal Neutron Collimators for Neutron Capture Studies at The Dalat Research Reactor
por: Trịnh, Thị Tú Anh
Publicado: (2022)

Tokamak reactor system analysis code for the conceptual development of demo reactor /
por: Hong, Bong-Guen.

Victory in Tripoli :
por: London, Joshua E.
Publicado: (2005)

Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor
por: Trịnh, Thị Tú Anh
Publicado: (2023)

Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor
por: Trinh Thi Tu Anh, Pham Dang Quyet, Pham Ngoc Son, Phan Bao Quoc Hieu, Nguyen Thi Minh Sang, Cao Dong Vu
Publicado: (2024)

Design and simulation of a thermal neutron beam for neutron capture studies at the Dalat research reactor
por: Trịnh, Thị Tú Anh, et al.
Publicado: (2023)

Evolution of nuclear fuel management and reactor operational aid tools /
por: Turinsky, Paul J.

An Evaluation of Energy-loss Straggling Calculation of the LISE++ Code
Publicado: (2023)

Development and validation of coupled dynamics code 'trikin' for VVER reactors /

Development of 24 and 59 keV filtered neutron beams for neutron capture experiments at Dalat Research Reactor
por: Pham, Ngoc Son, et al.
Publicado: (2023)

Core design for heterogeneous thorium fuel assemblies for PWR(1)-nuclear design and fuel cycle economy /
por: Bae, Kang-Mok.

APOLLO2 year 2010 /

Dose calculation and measurement from B10(n,α)Li7 reaction using filtered neutron beam at Dalat Nuclear Research Institute
por: Trịnh, Thị Tú Anh
Publicado: (2022)

AEGIS : An advanced lattice physics code for light water reactor analyses /

The benchmark calculations of the gamma+ code with the HTR-10 safety demonstration experiments /
por: Jun, Ji-Su.

Solid fuel reactors /
por: Dietrich, Joseph R. ,
Publicado: (1958)

Fractional-order Modeling of Nuclear Reactor: From Subdiffusive Neutron Transport to Control-oriented Models
por: Vyawahare, Vishwesh, et al.
Publicado: (2020)

Measurement of Neutron Flux and Gamma Dose Rate Distribution Inside a Water Phantom for Boron Neutron Capture Therapy Study at Dalat Research Reactor
por: Trịnh, Thị Tú Anh
Publicado: (2022)

Apollo :
por: Reinach, Salomon
Publicado: (1924)

A computer code for calculation of fissio product concentrations for time following fission burst /
por: Phạm Ngọc Sơn.

Calculation of the shielding safety of Computed Tomography scanner room by using MCNP5 code
por: Trần, Ái Khanh, et al.
Publicado: (2024)

Reactor core fuel management
por: Silvennoinen, P
Publicado: (2014)

How to Code .NET: Tips and Tricks for Coding .NET 1.1 and .NET 2.0 Applications Effectively
por: Gross, Christian
Publicado: (2012)

A study on the influence of axial heterogeneity in the distribution of burnable absorbers in the fuel assembly WWER-1200 at neutronic characteristics - K∞

Nuclear Reactor Engineering: Reactor Systems Engineering
por: Glasstone, Samuel, et al.
Publicado: (2014)

DOE fundamentals handbook: Nuclear physics and reactor theory. Volume 2
por: Washington DC USDOE
Publicado: (2013)

Dynamics of nuclear reactors
por: Hetrick, David L
Publicado: (2013)

Nuclear reactor theory
por: Bell, George I, et al.
Publicado: (2013)

Nuclear Reactor Theory
por: Sekimoto, Hiroshi
Publicado: (2012)

Nuclear reactor physics
por: Stacey, Weston M
Publicado: (2014)

Nuclear reactor analysis
por: Duderstadt, James J, et al.
Publicado: (2014)

Nuclear Reactor Physics
por: Dam, H. van, et al.
Publicado: (2014)

Nuclear-reactor analysis
por: Henry, Allan F
Publicado: (2014)

Mission Apollo
por: Lewis Kerr
Publicado: (2002)