EPJ Nuclear Sciences and Technologies

The OpenMC Monte Carlo particle transport code has been continuously developed for 13 years by a large community of contributors. In that time span, the codebase has undergone significant changes that have redefined what OpenMC is and made it an enduring presence in the nuclear science and engineering community. In this paper, we discuss the evolution of programming language use in OpenMC, trends in the overall design of the programming interfaces, and implications for the future of the code.

Paul Romano

John Tramm

Patrick Shriwise

EPJ Nuclear Sciences & Technologies

Language and design evolution of the OpenMC Monte Carlo particle transport code

OpenMC蒙特卡罗粒子输运代码的语言与设计演化

NECP-MCX is a Monte-Carlo particle-transport code developed by the Nuclear Engineering Computational Physics (NECP) Lab. of Xi’an Jiaotong University in 2018. The first version of NECP-MCX is focused on addressing the challenge of deep-penetration radiation-shielding problems. In recent years, new capabilities of unstructured-mesh geometries, dose engine for Boron Neutron Capture Therapy (BNCT), neutron noise analysis, sensitivity analysis, depletion and activation calculation, simulation of randomly dispersed media, homogenization and gamma dose calculation based on point-kernel integral method are implemented in NECP-MCX V2.0. A user interface of NECP-MCX V2.0 is also under active development. This paper will introduce these new capabilities.

Qingming He

Qi Zheng

Jie Li

Zhanpeng Huang

Jinlong Huang

Shuai Qin

Hanlin Shu

Heyu Peng

Xuran Yang

Jingwen Shen

Jiandi Guo

Liangzhi Cao

Hongchun Wu

Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0

NECP-MCX V2.0蒙特卡罗粒子输运代码新功能概述

The link between reactor design studies and scenarios calculations is usually sequential. From a list set of objectives, a reactor design is produced and passed to the scenarist in the form of a numeric irradiation model. This approach assumes that the reactor design is fixed from the scenarist perspective. The method presented in this article proposes to use a flexible reactor model, built with artificial neural networks, that gives the possibility to the scenarist to change a reactor design directly during the scenario calculations. Doing so, the reactor design is no longer an imposed parameter but a tool to find new optimal trajectories. Moreover, this flexible model is able to exploit the historical loaded fuel compositions generated by the scenario calculations in order to monitor the reactor performances over time. In this paper, the flexible reactor model construction is detailed and the interest of such method is highlighted with an application case that consists in the transition from a PWR fleet, similar to the French one, towards a PWR − SFR fleet stabilizing plutonium inventory.

Kévin Tirel

Timothée Kooyman

Christine Coquelet-Pascal

Elsa Merle

Coupling reactor design and scenario calculations: a promising method for scenario optimization

耦合反应器设计与情景计算：一种有前景的情景优化方法

This paper presents the latest updates on PHITS, a versatile radiation transport code, focusing specifically on track-structure models. Track structure calculations are methods used to simulate the movement of charged particles while explicitly considering each atomic reaction. Initially developed for radiation biology, these calculation methods aimed to analyze the radiation-induced damage to DNA and chromosomes. Several track-structure calculation models, including PHITS-ETS, PHITS-ETS for Si, PHITS-KURBUC, ETSART, and ITSART, have been developed and implemented for PHITS. These models allow users to study the behavior of various particles at the nano-scale across a wide range of materials. Furthermore, potential applications of track-structure calculations have also been proposed so far. This collection of track-structure calculation models, which encompasses diverse conditions, opens up new avenues for research in the field of radiation effects.

Tatsuhiko Ogawa

Yuho Hirata

Yusuke Matsuya

Takeshi Kai

Tatsuhiko Sato

Yosuke Iwamoto

Shintaro Hashimoto

Takuya Furuta

Shin-ichiro Abe

Norihiro Matsuda

Takuya Sekikawa

Lan Yao

Pi-En Tsai

Hunter N. Ratliff

Hiroshi Iwase

Yasuhito Sakaki

Kenta Sugihara

Nobuhiro Shigyo

Lembit Sihver

Koji Niita

Overview of PHITS Ver.3.34 with particular focus on track-structure calculation

PHITS Ver.3.34 综述：特别关注径迹结构计算

Scenario simulations are the main tool for studying the impact of a nuclear reactor fleet on the related fuel cycle facilities. This equilibrium preliminary study aims to present the functionalities of a new tool and to show the wide variety of reactors/cycles/strategies that can be studied in steady state conditions and validated with more details thanks to dynamic code. Different types of scenario simulation tools have been developed at CEA over the years, this study focuses on dynamic and equilibrium codes. Dynamic fuel cycle simulation code models the ingoing and outgoing material flow in all the facilities of a nuclear reactor fleet and their evolutions through the different nuclear processes over a given period of time. Equilibrium fuel cycle simulation code models advanced nuclear fuel cycles in equilibrium conditions, i.e. in conditions which stabilize selected nuclear inventories such as spent nuclear fuel constituents, plutonium or some minor actinides. The principle of this work is to analyze different nuclear reactors (PWR, AMR) and several fuel types (UOX, MOX, ERU, MIX) to simulate advanced nuclear fleet with partial and fully plutonium and uranium multi-recycling strategies at equilibrium. At this first stage, selected results are compared with COSI6 simulations in order to evaluate the precision of this new tool, showing a significant general agreement.

Heddy Barale

Camille Laguerre

Paul Sabatini

Fanny Courtin

Guillaume Martin

A new tool for the simulation of different nuclear fleets at equilibrium

不同核舰队在平衡状态下的仿真新工具

Optimizing nuclear installation decommissioning and dismantling operations is an ongoing quest. Faced with the complexity of this activity, Model Based System Engineering promotes relevant principles and modeling techniques. It motivated the definition of a functional generic pattern model of the waste package production line and the decommissioning of the facility. It proposes a global and generic functional architecture of such a system aiming to reduce the level of the pollutant. This pattern is coupled with a process of logistics. Six functions are combined to define this functional pattern. The application of this pattern model to a case of waste recovery in a pit shows the relevance of the model-based system engineering approach, reducing the weight of the history in the development of scenarios by optimizing the control means for nuclear safety and product quality.

Philippe Girones

Vincent Chapurlat

A contribution for dismantling of nuclear facilities: a functional pattern for dismantling operations and indicators design and management

拆除核设施的贡献：拆除作业的功能模式及指标设计与管理

This article provides an overview of the developments made over the last 10 years within RayXpert ® , a CAD-based geometry 3D Monte Carlo software developed by TRAD – Tests &amp; Radiations. The main features of RayXpert ® are its 3D Monte Carlo engine and its CAD-based geometry. It is also possible to import STEP file, automatically detect overlaps, and perform parallel Monte Carlo computations. During the last 10 years, numerous new features were added to the software: TTB approximation, dose and flux mapping, computation resumption, radioactive decay computation, script support, MPI computation, advanced convergence indicators, etc. New features such as advanced biasing or neutron-induced activation simulation are under development. This article presents the past and future functionalities of RayXpert ® .

Nicolas Dray

Nicolas Mary

Cédric Dossat

Jefferson Bourgoin

Nathalie Chatry

An overview of last decade’s developments in RayXpert<sup>®</sup>, a 3D Monte Carlo code

RayXpert<sup>®</sup> 3D蒙特卡罗代码近十年发展概述

短名	EPJ Nuclear Sci. Technol.
Journal Impact	0.88
国际分区	NUCLEAR SCIENCE & TECHNOLOGY(Q3)

涉及主题	物理工程类量子力学核物理学化学计算机科学材料科学核工程数学热力学环境科学中子统计生物核化学冶金复合材料机械工程程序设计语言有机化学地理废物管理经济
出版信息	出版商: EDP Sciences，出版周期: ，期刊类型: journal，开源期刊: 是
基本数据	创刊年份: 2020，原创研究文献占比: 59.09%，自引率:11.10%， Gold OA占比: 97.14%
期刊费用	$详情
平均审稿周期	网友分享经验：10 Weeks

EPJ Nuclear Sciences and Technologies

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Language and design evolution of the OpenMC Monte Carlo particle transport code

Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0

Coupling reactor design and scenario calculations: a promising method for scenario optimization

Overview of PHITS Ver.3.34 with particular focus on track-structure calculation

A new tool for the simulation of different nuclear fleets at equilibrium

Language and design evolution of the OpenMC Monte Carlo particle transport code

Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0

Overview of PHITS Ver.3.34 with particular focus on track-structure calculation

A contribution for dismantling of nuclear facilities: a functional pattern for dismantling operations and indicators design and management

An overview of last decade’s developments in RayXpert^®, a 3D Monte Carlo code

ISSN	2491-9292
h-index	4

EPJ Nuclear Sciences and Technologies

期刊引文格式

有 1 位以上作者的期刊

有 2 位作者的期刊

有 3 位作者的期刊

有 5 位以上作者的期刊

书籍引用格式

学位论文引用格式

网页引用格式

专利引用格式

手工熬夜修改参考文献？研飞自动匹配期刊，一键轻松成稿，支持 Word/WPS

投稿经验分享

Language and design evolution of the OpenMC Monte Carlo particle transport code

Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0

Coupling reactor design and scenario calculations: a promising method for scenario optimization

Overview of PHITS Ver.3.34 with particular focus on track-structure calculation

A new tool for the simulation of different nuclear fleets at equilibrium

Language and design evolution of the OpenMC Monte Carlo particle transport code

Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0

Overview of PHITS Ver.3.34 with particular focus on track-structure calculation

A contribution for dismantling of nuclear facilities: a functional pattern for dismantling operations and indicators design and management

An overview of last decade’s developments in RayXpert®, a 3D Monte Carlo code

An overview of last decade’s developments in RayXpert^®, a 3D Monte Carlo code