Neutron Kinetics and Reactor Control

2021 ◽  
pp. 23-31
Author(s):  
Wei Shen ◽  
Benjamin Rouben
Keyword(s):  
Nuclear Reactor ◽  
Fission Neutron ◽  
Neutron Production ◽  
Neutron Generation ◽  
Fission Reactions ◽  
Multiplication Factor ◽  
Fission Event ◽  
Fission Neutrons ◽  
New Generation ◽  
Eventual Death

A nuclear reactor is designed to achieve the very delicate balance between neutron “production” (release) in fission reactions and neutron loss by absorption and leakage. A given neutron will be “born” in a fission event and will then usually scatter about the reactor until it meets its eventual “death” either by being absorbed in some material or by leaking out of the reactor. A certain number of these neutrons will be absorbed by fissionable nuclei and induce further fissions, thereby leading to the birth of new fission neutrons, that is, to a new generation of neutrons. The ratio of the number of neutrons born in a fission-neutron generation to the number born in the previous generation is called the effective reactor multiplication factor, keff. The keff characterizes the balance or imbalance in the chain reaction. Alternatively, keff can be defined by the ratio of production rate to loss rate of neutrons in the reactor. These definitions are given below:

Measurement of fission neutron spectrum averaged cross sections of some threshold reactions on europium: small scale production of no-carrier-added 153Sm in a nuclear reactor

2002 ◽  
Vol 90 (2) ◽  
Author(s):  
I. Fatima ◽  
Jamshed H. Zaidi ◽  
Shujaat Ahmad ◽  
M. S. Subhani
Keyword(s):  
Neutron Spectrum ◽  
Cross Sections ◽  
Nuclear Reactor ◽  
Fission Neutron ◽  
Small Scale ◽  
Activation Technique ◽  
Scale Production ◽  
Radiochemical Separations ◽  
Fission Neutron Spectrum ◽  
Γ Ray

SummaryEmploying the activation technique in combination with radiochemical separations and high-resolution γ-ray spectroscopy fission neutron spectrum averaged cross sections were measured for several (

Methodology for Verification of the Heat Transfer Crisis in the Nuclear Fuel Assemblies

2013 ◽  
Author(s):  
Anastasiia Zvorykina ◽  
Georgij Sharayevskiy ◽  
Nataliya Fialko ◽  
Nina Sharayevskaya
Keyword(s):  
Nuclear Power ◽  
Nuclear Reactor ◽  
Emergency Operation ◽  
Complex Problem ◽  
Diagnostic Systems ◽  
Software Support ◽  
Nuclear Power Installations ◽  
Safety Operation ◽  
New Generation ◽  
Power Installations

The present-day stage of nuclear-power engineering development raises sharply a number of complicated questions regarding the guarantee of safety operation of nuclear power-generating units of operating and designed Nuclear Power Plant (NPP). The most important of these unsolved technological problems were considered in [1] on the base of analysis of ways of operation reliability improvement for Nuclear Power Installations (NPI) with WWER and RBMK reactors. In connection with the priorities formulated in [1], in papers [2–6] the main aspects of approaches available for solution of most complex problem are considered: the development of methods of early identification of initial phases of emergency operation regimes in such nuclear power-generating units which are critically important for NPI trouble-free operation. It is necessary to stress, that reliable identification of the anomalies mentioned, especially of thermal-hydraulic nature ones in core region of nuclear reactor, must be provided under conditions when such operating troubles can not yet be detected by the issued supervisory instruments of NPI. Taking into account the requirement to prospective diagnostic provision of NPP equipment, in papers [2–5] are underlined that at present time the development of effective methods of anomalies identification in NPI equipment and development of mathematical software support on base of these methods for computer-aided diagnostic systems on base of AI conceptions in structure of hardware of operator support tools of new generation NPP are considered as the main condition which determine the development of diagnostic means with mentioned functional possibilities.

scholarly journals MEDAPP: Fission neutron beam for science, medicine, and industry

2015 ◽  
Vol 1 ◽  
Author(s):  
Christoph Genreith
Keyword(s):  
Fast Neutron ◽  
Neutron Beam ◽  
World Wide ◽  
Fission Neutron ◽  
Thermal Neutrons ◽  
Irradiation Position ◽  
Beam Tube ◽  
The World ◽  
Broad Variety ◽  
Fission Neutrons

The instrument MEDAPP <strong>Med</strong>ical <strong>App</strong>lications), operated by the Technische Universität München, and the respective irradiation position are located at the world-wide unique fast neutron beam tube SR10 to which a uranium converter is attached. Thus, the instrument is operated with unmoderated fission neutrons and can be used for a broad variety of applications. For selected tasks, an alternative use with thermal neutrons is possible.

scholarly journals NECTAR: Radiography and tomography station using fission neutrons

2015 ◽  
Vol 1 ◽  
Author(s):  
Thomas Bücherl ◽  
Stefan Söllradl
Keyword(s):  
Neutron Radiography ◽  
Fission Neutron ◽  
Fission Neutrons ◽  
Non Destructive

NECTAR, operated by the Technische Universität München, is a versatile facility for the non-destructive inspection of various objects by means of fission neutron radiography and tomography, respectively.

Integration of NuScale SMR With Desalination Technologies

2014 ◽  
Author(s):  
D. T. Ingersoll ◽  
Z. J. Houghton ◽  
R. Bromm ◽  
C. Desportes
Keyword(s):  
Large Scale ◽  
Nuclear Reactor ◽  
Cost Effective ◽  
Water Desalination ◽  
Plant Design ◽  
Electrical Grids ◽  
Cost Effective Approach ◽  
Attractive Option ◽  
Parametric Studies ◽  
New Generation

Nuclear energy plants are attractive energy source for large scale water desalination since the thermal energy produced in a nuclear reactor can provide both electricity and steam to desalt water without the production of greenhouse gases. A particularly attractive option is to couple a desalination plant with the new generation of nuclear plant designs: small modular reactors (SMR). This allows regions with smaller electrical grids and limited infrastructure to add new electrical and water capacity in more appropriate increments and allows countries to consider siting plants at a broader range of distributed locations. The NuScale SMR plant design is especially well suited for the co-generation of electricity and desalted water. The enhanced safety, improved affordability, and deployment flexibilities of the NuScale design provide a cost-effective approach to expanding global desalination capacity. Parametric studies have been performed to evaluate technical options for coupling a NuScale plant to a variety of different desalination technologies. An economic comparison of these options was performed for each of the different desalination technologies coupled to an appropriately sized NuScale plant capable of providing sufficient carbon-free electricity and clean water to support a city of 300,000 people.

scholarly journals Challenges to deployment of twenty-first century nuclear reactor systems

2017 ◽  
Vol 473 (2198) ◽  
pp. 20160815 ◽  
Author(s):  
Sue Ion
Keyword(s):  
Nuclear Power ◽  
Potential Role ◽  
Nuclear Reactor ◽  
First Century ◽  
Science And Engineering ◽  
Fuel Cycles ◽  
Small Modular Reactors ◽  
New Generation ◽  
Historical Issues

The science and engineering of materials have always been fundamental to the success of nuclear power to date. They are also the key to the successful deployment and operation of a new generation of nuclear reactor systems and their associated fuel cycles. This article reflects on some of the historical issues, the challenges still prevalent today and the requirement for significant ongoing materials R&D and discusses the potential role of small modular reactors.

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