On gas-cooled fast reactor designs – Nuclear data processing with sensitivity, uncertainty and similarity analyses-Reference-Cited by-同舟云学术

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On gas-cooled fast reactor designs – Nuclear data processing with sensitivity, uncertainty and similarity analyses

Published:2020-10 Issue: Volume:128 Page:103450
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Osuský Filip,Čerba Štefan,Lüley Jakub,Vrban Branislav,Haščík Ján,Nečas Vladimír

Funder

EU

Slovak Research and Development Agency

Scientific Grant Agency of the Ministry of Education of Slovak Republic and the Slovak Academy of Sciences

Cultural and Educational Grant Agency of the Ministry of Education of Slovak Republic

Publisher

Elsevier BV

Subject

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

Reference30 articles.

1. Scale: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design,2011

2. PARTISN: a time-dependent, parallel neutral particle transport code system;Alcouffe,2008

3. RSICC Computer Code Collection DIF3D10.0,2011

4. Actual status of the development of multigroup XS libraries for the gas-cooled fast reactor in Slovakia;Čerba,2017

5. ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology;Chadwick;Nucl. Data Sheets,2006

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1. A review of the current nuclear data performance assessments in advanced nuclear reactor systems;Annals of Nuclear Energy;2024-09

2. A gasket design suitable for helium circuits of generation IV Gas-Cooled reactors;Annals of Nuclear Energy;2024-06

3. Angular distribution uncertainty influence in a large sodium-cooled fast reactor with mixed-oxide fuel;Annals of Nuclear Energy;2024-03

4. Research and analysis of new generation nuclear reactors in the world;Naukovij žurnal «Tehnìka ta energetika»;2023-10-02

5. Nuclear data uncertainty influence on the breeding ratio in sodium-cooled fast reactor systems;Annals of Nuclear Energy;2023-08

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