Computational benchmark for fuel assembly of VVER-1000 using the Monte Carlo Serpent code-Reference-Cited by-同舟云学术

Computational benchmark for fuel assembly of VVER-1000 using the Monte Carlo Serpent code

Published:2018 Issue:1 Volume:33 Page:24-30
ISSN:1451-3994
Container-title:Nuclear Technology and Radiation Protection
language:en
Short-container-title:NUCL TECH RAD PROT

Author:

Galchenko Vitaliy¹,Shlapak Ihor¹,Gulik Volodymyr²

Affiliation:

1. RPA „Impulse”, Kyiv, Ukraine

2. RPA „Impulse”, Kyiv, Ukraine + Institute for Safety Problems of Nuclear Power Plants, Kyiv, Ukraine

Abstract

The use of a new Monte Carlo Serpent code for the calculation of water-cooled reactors is presented and a calculation scheme of the fuel assembly for VVER-1000 reactors developed. The calculation of neutron-physical characteristics for the fuel assembly of VVER-1000 is carried out for different states and the results obtained by the Serpent model compared with the results of other reactor codes. The analyses of these results are presented in the paper submitted here. Based on this article, the Monte Carlo Serpent code could be used for neutron-physical calculations of VVER-1000 reactors.

Publisher

National Library of Serbia

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Cited by 2 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. Computational study on distribution feasibility of radioactive waste transmutation in accelerator driven system;Nuclear Technology and Radiation Protection;2020

2. THE DEVELOPMENT OF A THREE-DIMENSIONAL MODEL OF WWER-1000 CORE USING THE MONTE CARLO SERPENT CODE FOR NEUTRON-PHYSICAL MODELING;Problems of Atomic Science and Technology;2019-10-07