Neutron and gamma-ray deep penetration calculation through biological concrete shield of VVER-1000 reactor by a new technique based on variance reduction-Reference-Cited by-同舟云学术

Neutron and gamma-ray deep penetration calculation through biological concrete shield of VVER-1000 reactor by a new technique based on variance reduction

Published:2013-10 Issue: Volume:60 Page:86-92
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Alizadeh Alia,Shirani Amir Saeid,Kashi Samira

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference13 articles.

1. ANS, 1977. American National Standard Neutron and Gamma-ray Flux-to-Dose Rate Factors, ANSI/ANS-6.1.1-1977. American Nuclear Society, La Grange Park, IL.

2. Booth, T.E., 1985. A Sample Problem for Variance Reduction in MCNP. LA-10363-MS.

3. Booth, T.E., 2004. MCNP Variance Reduction Examples. Los Alamos National Laboratory, Diagnostic Applications Group X-5. Mail Stop F663.

4. MCNP – A General Monte Carlo N-Particle Transport Code, Version 4C, LA-13709-M,2000

5. Final Safety Analysis Report (FSAR) of BNPP-1, 2003. Reactor, Revision 0, October.

Cited by 10 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. Utilization of steel slag from industrial waste for ionizing radiation shielding concrete: A systematic review;Construction and Building Materials;2023-06

2. Neutron shielding properties of TPX/B4C composites based on Monte Carlo method;IOP Conference Series: Earth and Environmental Science;2021-01-01

3. Metal and alloy composites for neutron shielding;Micro and Nanostructured Composite Materials for Neutron Shielding Applications;2020

4. Simulation of neutron shielding performance of concrete material in different incident directions;IOP Conference Series: Materials Science and Engineering;2019-04-12

5. Study on neutron and photon shielding properties of various concretes using MCNP code;IOP Conference Series: Earth and Environmental Science;2018-12-19