Scholarship, Postdocs, Internship, Job opportunities
There are two 6-months long opportunities at FZJ, in Germany
Schedule (6 months):
2 weeks: Literature review on coupling strategies or modeling of pressure decay systems.
6 weeks: Familiarization OpenModelica and containmentFOAM
8 weeks: Implementation of new developments for the Modelica models (coupling scheme and/or heat and mass transfer phenomenology)
6 weeks: Execution of coupled simulations, test of the robustness of the coupling and implementation of improvements if necessary. Application-oriented validation.
4 weeks: Preparation of the final documentation.
Schedule (6 months):
2 weeks: literature review on external cooling of submerged containments.
4 weeks: familiarization OpenFOAM / containmentFOAM
2 weeks: evaluation of optimal modeling approach to simulate the external cooling with containmentFOAM
6 weeks: development of model input and simulation of available experiments (boundary condition as a heat source for the external pool)
8 weeks: set-up coupled case with the current version of containmentFoam to represent the heat source to the external pool
4 weeks: Preparation of the final documentation
For both positions, the contact person is
Institute for Energy and Climate Research, Forschungszentrum Jülich GmbH, email@example.com, 02461/618057
CIEMAT has opened a position (3 years) for graduate/young PhDs in the framework of our R&D associated to transmutation and linked with our joint activities with Spanish National Company for Waste Management (ENRESA).
The work will consist of the simulation of nuclear reactors (mainly Generation IV reactors, small modular reactors – SMR and subcritical systems) using the Monte Carlo technique, and the simulation of experiments and neutron detectors. Besides, as usual, the propagation of the uncertainty to reactivity safety parameters will be analysed.
In our case, the main contributor is nuclear data. With this, nuclear data needs will be detected for advanced reactor concepts.
For more information: (https://www.ciemat.es/cargarAplicacionOfertaEmpleo.do?identificador=2243,
IRSN is looking for several Post-Docs in various nuclear fields.
All advertised positions are potentially eligible for a MSCA application (further information on this point is to be discussed with the contact person appointed in each description)
Cadarache Center – Provence-Alpes-Côte d’Azur – France
Main scientific field
CFD, multiphase phase flow, heat transfer
The candidate will work for the Incident and Accident Management Service (SEMIA). The activities conducted in this department covers especially the assessment of design basis accidents in nuclear power plants. This includes LOss of Coolant Accidents (LOCA) that correspond to transients induced by a pipe break in the primary loop of the plant.
Thematics: Civil engineering; Materials; Engineering Sciences
Keywords: Internal Sulfate Reaction (ISR), experimental data interpretation, sustainability indicators, scale effect, international ODOBA project
Place: Cadarache (13), France
Availability date: As soon as possible (May 2023)
Duration: 18 months
The proposed work is part of the research conducted at the Institute for Radiation Protection and Nuclear Safety (IRSN) concerning the ageing of concrete in nuclear power plant containments (extension of the operating life of nuclear reactors) in the framework of the international ODOBA project. This project focuses on internal swelling reactions (ISR) at the scale of massive blocks. They are of two types: the Internal Sulfate Reaction (ISR) and the Alkali-Aggregate Reaction (AAR). These reactions can lead to the degradation of the mechanical properties of the concrete but especially to cracking, potentially resulting in a loss of efficiency of the third containment barrier for radioactive materials.
IRSN Fontenay-aux-Roses, France
Laboratoire de Neutronique (LN) – Service de Neutronique et des risques de Criticité (SNC)
The objective of this work is to carry out a comparative study, between VESTA and TRIPOLI 4®, of the nuclear data uncertainty obtained on quantities of interest in depletion calculations after a first comparative study between the two codes on these same quantities of interest k inf and isotopic compositions of criticality safety nuclides.
Start in: As soon as possible
France Duration: 18 months
Monte Carlo burnup calculations are actually memory-bound, and the solution to this limitation lies in some sort of Domain Decomposition in order to distribute the memory requirements of a single simulation over several compute nodes. The problem of domain decomposition does not present the same challenges nor does it use the same approaches for deterministic methods and for Monte-Carlo simulations. A number of domain-decomposition methods adapted to neutron transport criticality calculations have been suggested in the literature, and a few codes, both production and research type, have tested some implementations.
Lieu de travail : Cadarache – Bouche du Rhône – France
Champ scientifique principal : Applied Mathematics, Fluid Mechanics
Key words: Large Eddy Simulation, numerical scheme
Fonction: Education and research
The work proposed in the framework of this post-doctorate is divided into two stages.
Firstly, it consists in extending the space discretization for LES applications on unstructured meshes. This type of development is a difficult problem. In particular, it seems that it is necessary to choose the richest possible approximations of the pressure, while preserving stability (discrete inf-sup condition). Such work has been proposed in the literature for Crouzeix-Raviart finite elements, for the simulation of incompressible flows. The objective is to extend these ideas in two directions:
a) adaptation to compressible flows, within the framework of schemes developed over the last ten years by the Institut de Mathématique de Marseille (I2M) and the IRSN,
b) extension to discretization in space of the same type (i.e. with velocity degrees of freedom associated with faces) but based on cells of different shape: hexahedra (Rannacher-Turek elements), prisms and pyramids.
In a second step, the validation of these schemes will be done on hydrogen, air and water vapour deflagration tests in a flame acceleration tube (ENACCEF2 experiments, performed at the ICARE Laboratory of the CNRS in Orléans). The simulations should make it possible to characterise the turbulence in the flow and the structure of the flame front.
PhD Position – Investigation of the stability and corrosion behavior of uranium nitrides
Innovative nuclear reactor concepts are currently intensively discussed internationally.
For the operation of most of these concepts novel fuels are envisaged, in particular materials with a matrix of uranium nitride (UN) due to their good thermophysical properties. In addition to their suitability as nuclear fuel, the stability of the materials in contact with aqueous solutions, among other things, is of great interest for the safety assessment of a repository.
At IEK-6, such investigations are being carried out to maintain competence as part of the European collaborative project FREDMANS.
The work is carried out in close cooperation with European partners.
One focus is on the investigation of the oxidation behavior under conditions relevant for interim storage, as well as the conversion of the nitride matrix into an oxide matrix.
• Investigation of the oxidation of UN based materials
• Complete oxidation of the nitride matrix to an oxide matrix
• Influence of certain fission product types (Ln, PGM) on the oxidation of UN
• Influence of atmospheric composition on the oxidation of UN
• Development of thermodynamic and kinetic models to describe the oxidation of UN in collaboration with project partners
• Preparation of data and scientific interpretation of results
• Independent presentation of the results at scientific conferences and in scientific publications
• Completed university studies (Master) in natural sciences, chemistry, physics, or related discipline
• Experience in the fields of radiochemistry, analytics, and materials science
• Practical experience with laboratory work, as well as willingness and ability to learn and develop these skills are essential
• Experience in handling radioactive materials is desirable
• Ability to work in an international multidisciplinary team
• Willingness to travel nationally and internationally on official business
• Strong motivation to complete the PhD within 3 years
• Very good command of written and spoken English
Last application date: 2023-05-31
The University of Sheffield are currently recruiting a Research Associate in Fusion Thermal Hydraulics.
Position: Research Associate in Fusion Thermal Hydraulics
University of Sheffield – Faculty of Engineering – Department of Mechanical Engineering
|Salary:||£36,333 to £44,414 per annum, with potential to progress to £48,423 (Grade 7)|
|Contract Type:||Full time, fixed-Term for 36 months|
|Closes:||9th June 2023|
|Detail and application:||https://www.jobs.ac.uk/job/CZT473/research-associate-fusion-thermal-hydraulics|
The CERN Fire and Rescue Service, part of the Occupational Health and Safety and Environmental Protection (HSE) Unit is looking for a fire safety engineer working in tight collaboration with the CERN Fire Safety Engineering Team to enhance fire safety throughout the Organization that has already achieved a high level.
You will be involved in ensuring that existing and new premises comply with fire and emergency standards and grant CERN personnel and visitors, the surrounding environment and CERN assets the appropriate levels of safety.
You will work in a multidisciplinary and diverse team of firefighters, fire officers, engineers and physicists.
The skills and/or technologies you should have and/or know:
• Industrial safety, fire safety, fire prevention, fire risk assessment;
• International/Swiss/French fire regulations;
• Volunteer fire officer/firefighter in a local or industrial FRS will be an asset.
Area of Interest
Health, Safety and Environment
After an on-the-job training period you will participate in performing a wide variety of activities related to radiation protection instrumentation, electronics and control systems.
These include the following forms of maintenance activities;
- Preventative: from routine monthly operations to intensive 5 yearly calibration campaigns;
- Breakdown: provide support to first line interventions teams to resolve onsite issues with a goal of minimising equipment down times and avoiding impact to accelerator or physics operations whilst maintaining safety integrity;
- Corrective: aid in the deployment of software and hardware upgrades across all sites;
- CMMS management.
You will also prepare documentation for the design, operation and maintenance of systems ensuring all maintenance documentation is kept up to date. Working onsite, you will provide support to project teams for the installation, cabling, commissioning and acceptance of new radiation protection systems.
The skills and/or technologies you should have and/or know:
- Instrumentation and control or equipment maintenance or low voltage electricity or electro-mechanics;
- Fault-finding methodologies and their application;
- Maintenance management and its associated tools.
Area of Interest
Electrical or Electronics Engineering
Opportunity at JRC Karlsruhe
Code: 2023-KRU-S4001-FGIV-022714 – KARLSRUHE
FG IV Scientist – Exploratory Research Project – Exploitation of Critical rAw materials REcovered from nuclear FUEL wastes (CAREFUEL)
Deadline: 08/05/2023 23:59 Brussels time
Following the success of the demonstration courses organized in the framework of the ENEEP project, we are pleased to announce a new series of educational courses in the Autumn of 2023.
The courses will cover a selection of fundamental aspects of nuclear science and technology, including topics such as
- reactor physics,
- neutron detection,
- isotope production,
- criticality safety,
- and neutron shielding
The courses will be structured as a short and intense dive into the fundamentals of each topic, providing participants with a comprehensive overview in a condensed timeframe. The courses represent a unique opportunity to gain hands-on experience performing experiments in nuclear facilities or understand and enhance knowledge of computational methods and codes commonly used in nuclear technology.
The course duration is 4 days, with 2 full days dedicated to experimental activities at research reactors or nuclear laboratories.
The ENEEP autumn courses are organized in cooperation with the ENEN2plus project. Participants are therefore encouraged to apply for ENEN2plus Mobility Grant. Please, carefully read the ENEN2plus Mobility Manual.
Some highlights of the position
IAEA wish for: we are looking for an enthusiastic and motivated chemist who has preferentially experience with chemical separation mostly with actinides and also working with mass spectrometry.
Assets: experience working with radioisotopes, having experience in using radiometry measurement techniques (alpha, gamma), working in accredited laboratory and clean laboratory experience are assets.
What can IAEA offer? A professional position with emphasize on technical tasks and working in an international team with highly trained professionals at the IAEA Safeguards Environmental Sample Laboratory in Seibersdorf. The work is mostly carried out in the Clean Laboratory with trace level of U, Pu, Am, and Th bearing samples. The incumbent would be responsible for the sample preparation like digestion, separation and purification of cotton swipes, but also of soil and biota samples, screening with ICP MS, and reporting results for customers. Additionally, would be responsible for maintaining the laboratory equipment, doing procurement, method development, and quality control.
Deadline of application: 23rd April 2023
JOB DESCRIPTION HERE
LINK TO JOB APPLICATION HERE
PhD student in applied nuclear physics, nuclear safeguards for SMR
This project is devoted to research on non-proliferation and safeguards aspects related to the introduction and possibly deployment of SMR:s in Sweden. Of particular interest is accounting for and verification of the nuclear material, which means that the reactors themselves are central, but that also that other issues related to e.g. the transportation and storage of fuel could become relevant. In this context, potential challenges include geographically distributed and even transportable reactor systems, systems located at non-traditional sites, and nuclear materials and reactor operations that differ from current commercial large-scale light water reactors. Safeguards solutions need to be comprehensive, cost-efficient, robust, make efficient use of safeguards resources and be as non-intrusive as possible on plant operations. The main objective of this project is to provide safeguards concepts and solutions to ensure that safeguards requirements can be met during development, assessment and licensing of SMRs. The project will also research methods and equipment suitable for safeguards verification of the fuel cycle activities for modular reactor systems. Although this project focuses on the introduction of SMRs in Sweden, the research is highly relevant for the implementation of safeguards on an international level, through the International Atomic Energy Agency (IAEA) as well as on a regional and national level.
Research tasks include studies of selected SMR concepts to better understand safeguards considerations and challenges associated with all parts of the fuel cycle. This may include aspects related to national legislation, deployment scenarios, operation modes, logistic and storage considerations and fuel recycling. The objective is to better understand what implications the deployment of SMRs and or Advanced Modular Reactors could have on nuclear safeguards, from both a technical and non-technical perspective. This work could benefit from considering proliferation assessment studies, diversion pathway analysis or studies on material attractiveness. The research is furthermore expected to include analysis of (national) needs in terms of e.g. new facilities, new logistical solutions and new instruments/approaches/methods. This part of the project is related to the societal impacts of deployment of SMRs, and the work is foreseen to be done in collaboration with other partners and working groups in ANItA.
Another major part of this project is research on the characterization of material flows of fresh and irradiated fuels, and assessments related to future fuel use in the SMRs, as well as safeguards-relevant process materials streams. It is expected that the PhD student will model and simulate for instance used nuclear fuel as well as the detection of radiation from the fuel in order to draw conclusions about how to best verify the nuclear material. This research is expected to also include the use of machine learning methods for data analysis. Also this part of the project will be executed in collaboration and cooperation with other partners and working groups in ANItA.
Placement: Department of Physics and Astronomy
Type of employment: Full time , Temporary position
Pay: Fixed salary
Number of positions: 1
Working hours: 100 %
County: Uppsala län
Union representative: ST/TCO firstname.lastname@example.org
Seko Universitetsklubben email@example.com
Number of reference: UFV-PA 2023/1069
Last application date: 2023-05-02