Applicability of the Krško nuclear power plant core Monte Carlo model for the determination of the neutron source term-Reference-Cited by-同舟云学术

Applicability of the Krško nuclear power plant core Monte Carlo model for the determination of the neutron source term

Published:2021-11 Issue:11 Volume:53 Page:3528-3542
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Goričanec Tanja,Štancar Žiga,Kotnik Domen^ORCID,Snoj Luka,Kromar Marjan^ORCID

Funder

Javna Agencija za Raziskovalno Dejavnost RS

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference30 articles.

1. Nuclear design calculations of the NPP Krško core;Kromar;Journal of Energy Technology,2009

2. “Activation Neutronics for the Swiss Nuclear Power Plants”, Dissertation, Diss. ETH No. 21623;Garces,2013

3. Initial MCNP6 Release Overview - MCNP6 Version 1.0;Goorley,2013

4. “Validation and Modification of Fuel Burnup with the Use of ISOlib Library in the CORD-2 Program’, PhD Thesis, Faculty of Civil Engineering, Transportation Engineering and Architecture;Ćalić,2016

5. Determination of neutron flux redistribution factors for typical PWR using Monte Carlo neutron transport methods;Goričanec,2019

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. Towards establishment of an efficient approach for validation of PWR full core Monte Carlo simulations at hot zero power conditions;Progress in Nuclear Energy;2024-07

2. Nuclear safety operating margin using new power peaking factors for NUR nuclear research reactor;Progress in Nuclear Energy;2024-03

3. Analysis of fluctuations in ex-core neutron detector signal in Krško NPP during an earthquake;Nuclear Engineering and Technology;2024-02

4. Determination of neutron flux redistribution factors for a typical pressurized water reactor ex-core measurements using Monte Carlo technique;Frontiers in Energy Research;2023-02-23