scholarly journals Recent developments of the FALSTAFF experimental setup

2018 ◽  
Vol 193 ◽  
pp. 04003
Author(s):  
A. Chietera ◽  
L. Thulliez ◽  
E. Berthoumieux ◽  
D. Doré ◽  
A. Letourneau ◽  
...  
Keyword(s):  
Nuclear Data ◽  
Nuclear Fission ◽  
Residual Energy ◽  
Experimental Setup ◽  
Experimental Apparatus ◽  
Recent Developments ◽  
Complementary Fragment ◽  
Energy Domain ◽  
Ionisation Chamber ◽  
Gen Iv

The study of nuclear fission is encountering renewed interest with the development of GEN-IV reactor concepts, mostly working in the neutron fast energy domain. To support the fast reactor technologies, new high quality nuclear data are needed. New facilities are being constructed to produce high intensity neutron beams from hundreds of keV to few tens of MeV (Licorne, NFS, nELBE, ...). They will open new opportunities to provide nuclear data. In this framework the development of an experimental setup called FALSTAFF for a characterisation of actinide fission fragments has been undertaken. Fission fragment yields and associated neutron multiplicities will be measured as a function of the neutron energy. Based on time-of-flight and residual energy technique, the setup will allow the simultaneous measurement of the complementary fragment velocity and energy. The FALSTAFF setup and the upgrade of the first arm prototype with the new ionisation chamber CALIBER will be presented. The performances of the experimental apparatus is discussed.

scholarly journals Performance validation of the first arm of FALSTAFF: 252Cf and 235U fission fragment characterisation

2019 ◽  
Vol 211 ◽  
pp. 04002 ◽  
Author(s):  
D. Doré ◽  
E. Berthoumieux ◽  
Q. Deshayes ◽  
L. Thulliez ◽  
P. Legou ◽  
...  
Keyword(s):  
Fission Fragment ◽  
Ionization Chamber ◽  
Nuclear Data ◽  
Nuclear Fission ◽  
Fragment Mass ◽  
Proportional Chamber ◽  
Before And After ◽  
Energy Domain ◽  
Gen Iv ◽  
Performance Validation

The renewed interest for the study of nuclear fission is mainly motivated by the development of GEN-IV reactor concepts, mostly foreseen to operate in the fast neutron energy domain. To support this development, new high-quality nuclear data are needed. In this context, a new experimental setup, the FALSTAFF spectrometer, dedicated to the study of nuclear fission is under development. Employing the double-velocity (2V) and energy-velocity (EV) methods, the fission fragment mass before and after neutron evaporation will be deduced and the correlation between prompt neutron multiplicity and fragment mass will be determined. The first arm of the spectrometer is achieved. It is composed of two SED-MWPC detectors (a combination of a foil to produce secondary electrons and a Multi-Wire Proportional Chamber to detect them) and an axial ionization chamber. The SED-MWPC give access to the velocity (V) via time-of-flight and position measurements. The ionization chamber measures the fragment kinetic energy (E) and the energy loss profile. Preliminary results for spontaneous fission of 252Cf and from the thermal-neutron induced fission experiment on 235U, performed at the Orphée reactor (CEA-Saclay, France), are presented.

scholarly journals FALSTAFF, an apparatus to study fission fragment properties First arm results

2020 ◽  
Vol 239 ◽  
pp. 05012
Author(s):  
Quentin Deshayes ◽  
Eric Berthoumieux ◽  
Diane Doré ◽  
Loic Thulliez ◽  
Michel Combet ◽  
...  
Keyword(s):  
Kinetic Energy ◽  
Fast Neutron ◽  
Neutron Energy ◽  
Fission Fragment ◽  
Time Of Flight ◽  
Theoretical Models ◽  
Nuclear Data ◽  
Nuclear Fission ◽  
Neutron Multiplicity ◽  
Energy Domain

Nuclear fission is a complex process that still need fundamental studies. New measurements, particularly of correlated observables, could allow to develop more sophisticated theoretical models to eventually have truly predictive capabilities for the physics of fission. Moreover, the next generation reactors concepts are mostly foreseen to operate in the fast-neutron energy domain, requiring new high quality nuclear data. In this context, a new experimental setup, called FALSTAFF, dedicated to the study of fission is under development. The FALSTAFF setup aims to investigate the fission of actinides in the fast-neutron energy domain (from a few hundreds of keV to a few MeV). Once completed, this two-arm spectrometer will detect both fragments in coincidence and allow to measure their time of flight (ToF) and kinetic energy. The average neutron multiplicity as a function of the fission fragment mass can then be assessed. The first arm of the FALSTAFF spectrometer was built. It is composed of two main parts: first, two SED-MWPC (Multi-Wire Proportional Counter) detectors are used to measure the time-of-flight as well as the position of the fragments, thus reconstructing their velocity. Second, an axial ionisation chamber gives their kinetic energy and the energy loss profile. This proceeding will describe the FALSTAFF setup as well as the methods that are used to extract the required observables, leading up to the reconstruction of the neutron multiplicity to study the fission process. Then, the recent results obtained with the first arm of FALSTAFF will be presented, exhibiting kinetic energy, velocity and post-evaporation mass distributions. These observables will be displayed for 252Cf spontaneous fission and some of the improvements recently made will be discussed.

Preheat Limits in Practical Combustor Design: Experiments and Simulations

2018 ◽  
Author(s):  
Aleksandr Fridlyand ◽  
Brian Sutherland ◽  
Paul Glanville
Keyword(s):  
Natural Gas ◽  
A Priori ◽  
Effective Means ◽  
External Source ◽  
Chemical Kinetic ◽  
Residual Energy ◽  
Spontaneous Ignition ◽  
Autoignition Temperature ◽  
Air Stream ◽  
Experimental Apparatus

Autoignition in commercial and residential gas appliances is typically a phenomenon to be avoided. The autoignition temperature for a particular fuel, defined as the minimum temperature at which spontaneous ignition will occur without an external source of energy, is often used to characterize this phenomenon. In the design of combustion systems, it is used to demarcate conditions where autoignition may occur. In an emerging class of residential and commercial heating, cooling, and power generation appliances, preheating air and fuel can provide an effective means of boosting the overall energy efficiency by recuperating residual energy in the exhaust and reinvesting it back into the thermodynamic process. In such applications, the design question to answer is: How much can the air and fuel be preheated without autoignition? The autoignition temperature, often determined experimentally and can vary as much as 100°C for methane, may not be the most useful metric in this context. This work describes the results of a recent experimental investigation into the preheat limits for autoignition of air and natural gas with the aim of recuperating as much heat as possible in a heat pump. The experimental apparatus consisted of an air-fuel mixer supplying preheated mixture to a radiant burner. The air was first heated in excess of 750°C, cool natural gas was injected into and mixed with the hot-air stream, and all while avoiding autoignition. The current capability to predict autoignition in such applications a priori was also assessed using available chemical kinetic models and numerical simulations.

Nuclear Fission, Today and Tomorrow: From Renaissance to Technological Breakthrough (Generation IV)

2011 ◽  
Vol 133 (4) ◽  
Author(s):  
Georges Van Goethem
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Fission ◽  
Natural Uranium ◽  
Low Carbon ◽  
Nuclear Facilities ◽  
Research Issues ◽  
Low Carbon Economy ◽  
Safety And Reliability ◽  
Gen Iv

To better understand the industrial and political contexts of nuclear innovation, it is necessary to consider the history of nuclear fission technologies (four generations of nuclear power plants): (1) GEN I (construction 1950–1970): early prototypes, using mainly natural uranium as fuel, graphite as moderator, and CO2 as coolant (built at the time of “Atoms for Peace,” 1953); (2) GEN II (yesterday, construction 1970–2000): safety and reliability of nuclear facilities and energy independence (in order to ensure security of supply); (3) GEN III (today, construction 2000–2040): continuous improvement of safety and reliability, and increased industrial competitiveness in a worldwide growing energy market; (4) GEN IV (tomorrow, construction from 2040): for increased sustainability (optimal utilization of natural resources and waste minimization) and proliferation resistance. The focus in this paper is on the design objectives and research issues associated to the latter generation IV. Their benefits are discussed according to a series of ambitious criteria or technology goals established at the international level (generation IV international forum (GIF)). One will have to produce not only electricity at lower costs but also heat at very high temperatures, while exploiting a maximum of fissile and fertile matters, and recycling all actinides, under safe and reliable conditions. Scientific viability studies and technological performance tests for each system are being carried out worldwide, in line with the GIF agreement (2001). Their commercial deployment is planned for 2040. In Sec. 6, it is shown to what extent GEN IV can be considered as a beneficial, responsible, and sustainable response to the societal and industrial challenges of the future low-carbon economy.

scholarly journals Fission fragments observables measured at the LOHENGRIN spectrometer

2020 ◽  
Vol 239 ◽  
pp. 05017
Author(s):  
S. Julien-Laferrière ◽  
L. Thombansen ◽  
G. Kessedjian ◽  
A. Chebboubi ◽  
O. Serot ◽  
...  
Keyword(s):  
Neutron Emission ◽  
Evaluation Process ◽  
Nuclear Data ◽  
Nuclear Fission ◽  
Experimental Program ◽  
Spent Fuel ◽  
Ionic Charge ◽  
Fission Fragments ◽  
Common Effort ◽  
Fission Yields

Nuclear fission yields are key data for reactor studies, such as spent fuel inventory or decay heat, and for understanding fission process. Despite a significant effort allocated to measure fission yields during the last decades, the recent evaluated libraries still need improvements in particular in the reduction of the uncertainties. Moreover, some discrepancies between these libraries must be explained. Additional measurements provide complementary information and estimations of experimental correlations, and new kinds of measurements enable to test the models used during the nuclear data evaluation process. A common effort by the CEA, the LPSC and the ILL aims at tackling these issues by providing precise measurements of isotopic and isobaric fission yields with the related variance-covariance matrices. Additionally, the experimental program involves a large range of observables requested by the evaluations, such as kinetic energy dependency of isotopic yields and odd-even effect in order to test the sharing of total excitation energy and the spin generation mechanism. Another example is the complete range of isotopic distribution per mass that allows the determination of the charge polarization, which has to be consistent for complementary masses (pre-neutron emission). For instance, this information is the key observable for the evaluation of isotopic yields. Finally, ionic charge distributions are indirect measurements of nanosecond isomeric ratios as a probe of the nuclear de-excitation path in the (E*, J, π) representation. Measurements for thermal neutron induced fission of 241 Pu have been carried out at the ILL in Grenoble, using the LOHENGRIN mass spectrometer. Methods, results and comparison to models calculations will be presented corresponding to a status on fission fragments observables reachable with this facility.

Design of Remote Laboratory Experiments Using LabVIEW Web Services

2012 ◽  
Author(s):  
Serdar Tumkor ◽  
Sven K. Esche ◽  
Constantin Chassapis
Keyword(s):  
Real Time ◽  
Laboratory Experiments ◽  
Engineering Students ◽  
The Internet ◽  
Specific Method ◽  
Experimental Setup ◽  
Remote Laboratory ◽  
Batch Mode ◽  
Theoretical Concepts ◽  
Experimental Apparatus

Laboratory experiments are an important and integral part of the learning experience for undergraduate engineering students. They help the students in getting hands-on experience and in better understanding theoretical concepts. In recent years, a significant number of remotely accessible experiments have been developed and integrated into engineering laboratory courses at many educational institutions worldwide. There exist several approaches and technologies for making experimental hardware accessible via the Internet. This paper will discuss some of the available technologies and a specific method for acquiring data from experimental setups via LabVIEW Virtual Instruments over a network. As an example, a remote experimental apparatus that was developed by upgrading a commercially available air flow rig with remote control and monitoring capabilities is presented. This system is used in a junior-level mechanical engineering course on fluid mechanics. It enables the students to access the experimental setup via the Internet either in real-time or batch mode. For real-time use of the experimental setup, remote panels are used. These remote panels are exactly the same as those that would be used on a local on-site server. They can be run under LabVIEW’s Web server to be observed and controlled by the client via any Internet browser. For the batch-mode use of the experimental setup, on the other hand, simple HTML pages in conjunction with forms are used to generate experimental requests that are sent to the LabVIEW server. This server then places these experimental requests in a queue and executes the appropriate LabVIEW scripts on a first-come first-served basis. This paper will discuss and compare both methods for performing remote laboratory experiments.

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