Reactor physics trang 1 tải miễn phí từ TAILIEUCHUNG

"Reactor physics" trang 1 - tải miễn phí từ Tailieuchung

Simulation for neutron transport in pwr reactor moderator and evaluation for proper thickness of light water reflector

Simulation for neutron transport in pwr reactor moderator and evaluation for proper thickness of light water reflector

6 52 0

A fission matrix based validation protocol for computed power distributions in the advanced test reactor

A fission matrix based validation protocol for computed power distributions in the advanced test reactor

10 2 1

Uncertainty quantiﬁcation works relevant to ﬁssion yields and decay data

Uncertainty quantiﬁcation works relevant to ﬁssion yields and decay data

7 82 0

A multi-physics analysis for the actuation of the SSS in Opal reactor

A multi-physics analysis for the actuation of the SSS in Opal reactor

8 67 0

Reﬂector features and physics consideration issued from the Jules Horowitz Reactor design analyses

Reﬂector features and physics consideration issued from the Jules Horowitz Reactor design analyses

8 54 0

Some main results of commissioning of the Dalat research reactor with low enriched fuel

Some main results of commissioning of the Dalat research reactor with low enriched fuel

10 36 3

Advanced numerical simulation and modelling for reactor safety contributions from the CORTEX, HPMC, McSAFE and NURESAFE projects

Advanced numerical simulation and modelling for reactor safety contributions from the CORTEX, HPMC, McSAFE and NURESAFE projects

14 62 0

Pyramid finite elements for discontinuous and continuous discretizations of the neutron diffusion equation with applications to reactor physics

Pyramid finite elements for discontinuous and continuous discretizations of the neutron diffusion equation with applications to reactor physics

10 2 1

Multi-physics models for design basis accident analysis of sodium fast reactors. Part I: Validation of three-dimensional TRACE thermal-hydraulics model using Phenix end-of-life experiments

Multi-physics models for design basis accident analysis of sodium fast reactors. Part I: Validation of three-dimensional TRACE thermal-hydraulics model using Phenix end-of-life experiments

11 1 1

MC21/COBRA-IE and VERA-CS multiphysics solutions to VERA core physics benchmark problem #6

MC21/COBRA-IE and VERA-CS multiphysics solutions to VERA core physics benchmark problem #6

14 1 1

One-dimensional multigroup neutron diffusion eigenvalue problem solution using finite difference method

One-dimensional multigroup neutron diffusion eigenvalue problem solution using finite difference method

9 1 1

Solving point burnup equations by Magnus method

Solving point burnup equations by Magnus method

5 50 0

Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes

Reactor physics modelling of accident tolerant fuel for LWRs using ANSWERS codes

9 53 0

Đã phát hiện trình chặn quảng cáo AdBlock

Trang web này phụ thuộc vào doanh thu từ số lần hiển thị quảng cáo để tồn tại. Vui lòng tắt trình chặn quảng cáo của bạn hoặc tạm dừng tính năng chặn quảng cáo cho trang web này.