scholarly journals THE LiCore POWER PLANT SIMULATOR OF THE MOLTEN SALT FAST REACTOR

2021 ◽  
Vol 247 ◽  
pp. 06030
Author(s):  
A. Laureau ◽  
E. Rosier ◽  
E. Merle ◽  
S. Beils ◽  
O. Bruneau ◽  
...  
Keyword(s):  
Power Plant ◽  
Molten Salt ◽  
Basic Principle ◽  
Kinetics Model ◽  
Simple Point ◽  
Delayed Neutron ◽  
Integrated Simulation ◽  
The Core ◽  
Definition Of ◽  
Point Kinetics

Molten salt reactors as liquid-fuelled reactors are flexible in terms of operation or design choices, but they are very different in terms of design, operation and safety approach compared to solid-fuelled reactors. Such reactors call for a new definition of their operating procedures and safety approach. Dedicated developments and studies have been performed in the frame of the European SAMOFAR project of Horizon2020 and in parallel in France involving CNRS, CORYS and Framatome to develop a system code called LiCore adapted to such reactors, corresponding to a basic-principle power plant simulator. The neutronic model LiCore, at the centre of the simulator, corresponds to an improved point-kinetics model to take into account the specificities of a MSR, notably the circulation of the delayed neutron precursors out of the core. Coupled to a simple piston model for the fuel motion in the core, this code can perform calculations faster than real time to simulate the behaviour of the fuel circuit. Transient calculations performed with LiCore are presented, together with comparisons first to a simple point-kinetics model and then to 3D calculations with the TFM-OpenFOAM coupled code. Finally, the LiCore code has recently been integrated in the ALICES platform, the integrated simulation toolset designed by CORYS for the development, maintenance and operation of major simulator such as power plant simulators.

Neutron point kinetics model with precursors’ shape function update for molten salt reactor

2020 ◽  
Vol 360 ◽  
pp. 110466 ◽  
Author(s):  
Rodrigo Costa Diniz ◽  
Alessandro da Cruz Gonçalves ◽  
Felipe Siqueira de Souza da Rosa
Keyword(s):  
Molten Salt ◽  
Shape Function ◽  
Kinetics Model ◽  
Molten Salt Reactor ◽  
Point Kinetics

Numerical Research on Steady Coupling of Neutronics and Thermal-Hydraulics for a Molten Salt Reactor

2008 ◽  
Author(s):  
Dalin Zhang ◽  
Changliang Liu ◽  
Libo Qian ◽  
Guanghui Su ◽  
Suizheng Qiu
Keyword(s):  
Thermal Neutron ◽  
Molten Salt ◽  
Molten Salt Reactor ◽  
Thermal Hydraulics ◽  
Steady Condition ◽  
Delayed Neutron ◽  
The Core ◽  
Production Of Hydrogen ◽  
Fuel Salt ◽  
Salt Flow

The Molten Salt Reactor (MSR), which is one of the ‘Generation IV’ concepts, can be used for production of electricity, actinide burning, production of hydrogen, and production of fissile fuels. In this paper, a single-liquid-fueled MSR was selected for conceptual research. For this MSR, a ternary system of 15%LiF-58%NaF-27%BeF2 was proposed as the reactor fuel solvent, coolant and also moderator with ca. 1 mol% UF4 dissolving in it, which circulates through the whole primary loop accompanying fission reaction only in the core. The fuel salt flow makes the MSR different from the conventional reactors using solid fissile materials, and makes the neutronics and thermal-hydraulic coupled strongly, which plays the important role in the research of reactor safety analysis. Therefore, it’s necessary to study the coupling of neutronics and thermal-hydraulic. The theoretical models of neutronics and thermal-hydraulics under steady condition were conducted and calculated by numerical method in this paper. The neutronics model consists of two group neutron diffusion equations for fast and thermal neutron fluxes, and balance equations for six-group delayed neutron precursors considering flow effect. The thermal-hydraulic model was founded on the base of the fundamental conservation laws: the mass, momentum and energy conservation equations. These two models were coupled through the temperature and heat source. The spatial discretization of the above models is based on the finite volume method (FVM), and the thermal-hydraulic equations are computed by SIMPLER algorithm with domain extension method on the staggered grid system. The distribution of neutron fluxes, the distribution of the temperature and velocity and the distribution of the delayed neutron precursors in the core were obtained. The numerical calculated results show that, the fuel salt flow has little effect to the distribution of fast and thermal neutron fluxes and effective multiplication factor; however, it affects the distribution of the delayed neutron precursors significantly, especially long-lived one. In addition, it could be found that the delayed neutron precursors influence the neutronics slightly under the steady condition, and the flow could remove the heat generated by the neutron reactions easily to ensure the reactor safe. The obtained results serve some valuable information for the research and design of this new generation reactor.

A Study on Doppler Weighting Factor for Control Element Assembly Ejection Accident by Using Newly Developed Nuclear Design Code and Non-LOCA Methodology

2013 ◽  
Author(s):  
Kyungmin Yoon ◽  
Chansu Jang ◽  
Jooil Yoon
Keyword(s):  
Safety Analysis ◽  
Weighting Factor ◽  
Time Effect ◽  
Kinetics Model ◽  
Control Element ◽  
Fuel Temperature ◽  
Design Code ◽  
The Core ◽  
Point Kinetics ◽  
Reactivity Insertion

Among Reactivity Initiated Accidents (RIAs) for Pressurized Water Reactor (PWR), Control Element Assembly Ejection (CEAE) accident causes the rapid positive reactivity insertion to the core. It causes an asymmetric power distortion which results in the rising of local fuel temperature, fuel pellet thermal expansion and cladding ballooning or rupture. In the CEAE accident, Doppler feedback has a profound effect because the negative reactivity insertion due to the rise of fuel temperature reduces the core power after rapid power excursion. But the Doppler reactivity can’t be calculated properly in the safety analysis code, using point kinetics model, because the point kinetics model is not able to consider spatial-time effect of the sudden rise in local fuel temperature on Doppler feedback calculation during CEAE accident. And then the excessively high core power which results from the underestimated Doppler feedback would make more severe results such as PCMI fuel failure, fuel cladding rupture and serious DNB fuel failure. Therefore, Doppler Weighting Factor (DWF) is needed for the safety analysis of CEAE accident to compensate a missing spatial-time effect on Doppler feedback calculation. In this study, the adequacy of the application of DWF for APR1400 was evaluated by using nuclear design code called ASTRA (Advanced Static and Transient Reactor Analyzer)[1] and a methodology called ISAM (Integrated Safety Analysis Methodology)[2]. ASTRA is the 3D nuclear design code newly developed by KNF and has various functions such as the static core design, the transient core analysis and the operational support. ISAM is the methodology which is newly developed by KNF to perform the Non-LOCA safety analysis by using RETRAN[3] code which is widely used in the transient analysis and based on the point kinetics model.

Inaccurate Use of Boron Concentration for Reactivity Feedback

2002 ◽  
Author(s):  
Birol Aktas ◽  
Sule Ergun
Keyword(s):  
Boron Concentration ◽  
Solute Concentration ◽  
Kinetics Model ◽  
The Core ◽  
The Us ◽  
Point Kinetics

A deficiency has been identified with the use of boron concentration for formulating reactivity feedback while the power of a PWR in response to boron injection in the aftermath of a scram failure was simulated. The US NRC Consolidated Code (TRAC-M) was used to simulate this transient, in which the boron injection was expected to shutdown the reactor. The results of this study, which employed the point-kinetics model of TRAC-M, reveal that the use of core-average boron concentration for formulating the reactivity feedback is inadequate for transients when there is substantial coolant void inside the core. It is recommended that the macroscopic boron density be used for more accurate predictions of the boron feedback as the use of solute concentration is only adequate when no voiding occurs in the core.

scholarly journals Numerical Solution of Fractional Neutron Point Kinetics Model in Nuclear Reactor

2014 ◽  
Vol 24 (2) ◽  
pp. 129-154 ◽  
Author(s):  
Tomasz Karol Nowak ◽  
Kazimierz Duzinkiewicz ◽  
Robert Piotrowski
Keyword(s):  
Differential Equations ◽  
Fractional Derivative ◽  
Numerical Solution ◽  
Nuclear Reactor ◽  
Bilinear System ◽  
Kinetics Model ◽  
Proposed Model ◽  
Definition Of ◽  
Point Kinetics ◽  
The Impact

Abstract This paper presents results concerning solutions of the fractional neutron point kinetics model for a nuclear reactor. Proposed model consists of a bilinear system of fractional and ordinary differential equations. Three methods to solve the model are presented and compared. The first one entails application of discrete Grünwald-Letnikov definition of the fractional derivative in the model. Second involves building an analog scheme in the FOMCON Toolbox in MATLAB environment. Third is the method proposed by Edwards. The impact of selected parameters on the model’s response was examined. The results for typical input were discussed and compared.

Ways and Voices in the Psychoanalysis of Links According to Enrique Pichon-Rivière

2016 ◽  
Vol 6 (2) ◽  
Author(s):  
Rosa Jaitin
Keyword(s):  
Couple Therapy ◽  
Clinical Observation ◽  
Clinical Work ◽  
The Core ◽  
The Social ◽  
The 1960S ◽  
Definition Of ◽  
Relationship Of ◽  
The Voice ◽  
Different Levels

This article covers several stages of the work of Pichon-Rivière. In the 1950s he introduced the hypothesis of "the link as a four way relationship" (of reciprocal love and hate) between the baby and the mother. Clinical work with psychosis and psychosomatic disorders prompted him to examine how mental illness arises; its areas of expression, the degree of symbolisation, and the different fields of clinical observation. From the 1960s onwards, his experience with groups and families led him to explore a second path leading to "the voices of the link"—the voice of the internal family sub-group, and the place of the social and cultural voice where the link develops. This brought him to the definition of the link as a "bi-corporal and tri-personal structure". The author brings together the different levels of the analysis of the link, using as a clinical example the process of a psychoanalytic couple therapy with second generation descendants of a genocide within the limits of the transferential and countertransferential field. Body language (the core of the transgenerational link) and the couple's absences and presence during sessions create a rhythm that gives rise to an illusion, ultimately transforming the intersubjective link between the partners in the couple and with the analyst.

ДОМИНАНТНО-ФУНКЦИОНАЛЬНАЯ СТРУКТУРА ИДИОСТИЛЯ М.Ф. ДОРОНОВИЧА// Humanitarian and Socio-Economic Sciences Journal/ OEAPS Inc., Berlin, Germany, pp.46-55

2018 ◽  
Author(s):  
Olga Dorofeeva ◽  
Любовь Викторовна Чернова
Keyword(s):  
Functional Structure ◽  
The Core ◽  
Definition Of

Обращаясь к рассмотрению вопроса о доминантно-функциональной структуреидиостиля, авторы раскрывают дефиницию «идиостиль» в его связи с экстра- и интралингвистическими факторами. Рассматривая творчество публициста М.Ф. Дороновича через призму одножанровых текстов, авторы выделяют доминанты, составляющие ядро идиостиля публициста. К числу таковых относятся оценочная метафоричность, гиперболичность, фразеологичность, реализующиеся как на уровне тропов, так и на уровне синтаксических фигур.Addressing the issue of dominant-functional structure of idiostyle, the authors reveal the definition of "idiostyle" in its connection with extra- and intralinguistic factors. Considering the creativity of the writer M.F. Doronovich through the lens of various genres of texts, the authors identify the dominant components of the core of the idiostyle of the writer. These include evaluative metaphoricity, hyperbolicity, phraseology, which are implemented both at the level of tropes and at the level of syntactic figures.СВЕДЕНИЯ О ГРАНТАХ И ФИНАНСИРОВАНИИИсследование подготовлено при поддержке Российского фонда фундаментальных исследований (отделение гуманитарных и общественных наук) и Министерства образования, науки и молодёжной политики Краснодарского края в рамках научного проекта № 18-412-230008 а(р) «Язык и стиль публикаций М.Ф. Дороновича в кубанских дореволюционных газетах». Руководитель проекта – О.А. Дорофеева.

Reference Conundrum: The Broad Definition of Peer-Review

2018 ◽  
Author(s):  
Cody Fullerton
Keyword(s):  
Peer Review ◽  
Gold Standard ◽  
Review Process ◽  
Peer Review Process ◽  
Academic Publishing ◽  
Inaccurate Information ◽  
The Core ◽  
Literature Reviews ◽  
Reference Interactions ◽  
Definition Of

For years, the gold-standard in academic publishing has been the peer-review process, and for the most part, peer-review remains a safeguard to authors publishing intentionally biased, misleading, and inaccurate information. Its purpose is to hold researchers accountable to the publishing standards of that field, including proper methodology, accurate literature reviews, etc. This presentation will establish the core tenants of peer-review, discuss if certain types of publications should be able to qualify as such, offer possible solutions, and discuss how this affects a librarian's reference interactions.

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