MCNP geometry transformation and plotter equations-Reference-Cited by-同舟云学术

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MCNP geometry transformation and plotter equations

Published:2012-11 Issue: Volume:61 Page:26-40
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Durkee Joe W.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference17 articles.

1. MCNP–A General Monte Carlo N–Particle Transport Code, Version 4A,1993

2. MCNP–A General Monte Carlo N–Particle Transport Code, Version 5;Brown,2003

3. MCNP–A General Monte Carlo N–Particle Transport Code, Version 5;Brown,2003

4. Intersection of a Ray with a Surface of Third or Fourth Degree;Cashwell,1969

5. Private Communication;Forest,2012

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Neutronic response of the neutral beam after EAST NBI upgraded;Fusion Engineering and Design;2023-07

2. Efficiency analysis of multiple detector effects on MCNP 6.2 simulations;Progress in Nuclear Energy;2021-09

3. csg2csg: A TOOL TO ASSIST VALIDATION & VERIFICATION;EPJ Web of Conferences;2021

4. MCNP6 moving objects part I: Theory;Progress in Nuclear Energy;2016-03

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