Current status of the reactor physics code WIMS and recent developments

BA Lindley, JG Hosking, PJ Smith, DJ Powney… - Annals of Nuclear …, 2017 - Elsevier
The WIMS modular reactor physics code has been under continuous development for over
fifty years. This paper discusses the current status of WIMS and recent developments, in …

European benchmark on the ASTRID-like low-void-effect core characterization: neutronic parameters and safety coefficients

S Bortot, P Sciora, F Alvarez-Velarde… - … on Advances in …, 2015 - cea.hal.science
A benchmark analysis was launched within the Work Package on Core Safety of the EU FP7
cross-cutting project supporting the European Sustainable Industrial Initiative (ESNII) …

Improvement of few-group cross-section generation in fast reactor analysis system SARAX

L Wei, Y Zheng, H Wu - Annals of Nuclear Energy, 2019 - Elsevier
For better accuracy, the few-group cross-section generation module, named TULIP, in the
SARAX code system was further improved. In the new TULIP, the pure deterministic method …

[HTML][HTML] 快堆中子学计算程序NECP-SARAX 的改进与验证

郑友琦, 吴宏春, 杜夏楠, 肖云龙, 何明涛 - 强激光与粒子束, 2017 - cpsjournals.cn
NECP-SARAX 是西安交通大学NECP 团队开发的用于快中子反应堆的中子学程序系统.
为准确处理快中子反应堆中中等质量核素散射共振以及非弹性散射导致的复杂的中子慢化效应 …

[PDF][PDF] Analysis of the coolant density reactivity coefficient in LFRs and SFRs via Monte Carlo perturbation/sensitivity

M Aufiero, M Martin, M Fratoni, E Fridman… - Conference …, 2016 - researchgate.net
The coolant density effect represents one of the main reactivity feedback in LFR and SFR.
These reactivity feedback effects are often calculated via direct perturbation in Monte Carlo …

Improved methodologies for evaluation of severe transient conditions of sodium-cooled fast systems

A Ponomarev - 2017 - inis.iaea.org
[en] The work is dedicated to the analysis and improvements of methodologies of safety
evaluations of Sodium-cooled Fast Reactor (SFR) systems. In particular, the work is built …

Analysis of OECD/NEA medium 1000 MWth sodium-cooled fast reactor using the Monte Carlo serpent code and ENDF/B-VIII. 0 nuclear data library

FI Al-Hamadi, BA Khuwaileh, PH Liem… - Nuclear Science and …, 2020 - Springer
This study presents a benchmark evaluation of the new ENDF/B-VIII. 0 nuclear data library
for the Organization for Economic Co-operation and Development/Nuclear Energy Agency …

[PDF][PDF] Solution of the OECD/NEA SFR Neutronic Benchmark using WIMS and MONK

B Stray, M Delaney, B Lindley, M Shepherd… - …, 2016 - answerssoftwareservice.com
This paper presents solutions for the Sodium Fast Reactor (SFR) benchmark defined by the
OECD/NEA Working Party Scientific Issues of Reactor Systems using Amec Foster …

Analysis of the OECD/NEA SFR benchmark with ants reduced-order nodal diffusion solver and the serpent Monte Carlo code

M Szogradi - EPJ Web of Conferences, 2021 - epj-conferences.org
In order to meet modern industrial and scientific demands the Kraken multi-physics
platform's development was recently launched at VTT Technical Research Centre of …

[PDF][PDF] Analysis of OECD/NEA SFR Benchmarks Using McCARD

SH Janga, HJ Shima - 2015 - kns.org
As a part of international collaboration projects for evaluating performance of next
generation nuclear energy systems, Working Party on Scientific Issues on Reactor System …