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Analysis of nuclear reactors
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The obtained results with the neutron flux correction were found to be in good agreement with the certified values. In conclusion, the proposed technique can be applied for activation analyses without sandwiching flux monitors between samples during irradiations.
10p
vicedric
08-02-2023
4
3
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For the future of nuclear power, the design and development of an economical, accident tolerant fuel (ATF) for use in the current pressurized water reactors (PWRs) are highly desirable and essential. It is reported that the composite fuels are advantageous over the conventional UO2 fuel due to their higher thermal conductivities and a higher uranium densities.
12p
vicedric
08-02-2023
7
4
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This paper presents the development and verification of a deterministic model using the SRAC code system for analysing the criticality and control rod worth of the Dalat Nuclear Research Reactor (DNRR). Numerical calculations were performed based on seven core configurations established experimentally during the startup period of the DNRR.
7p
vicedric
08-02-2023
4
3
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In this paper, two meta-heuristic approaches, Differential evolution and Genetic algorithms were proposed to solve this problem. The optimal objectives are both the maximization of the length and the minimization of power peaking factor in a fuel cycle.
9p
vicedric
08-02-2023
3
3
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This study was conducted to carry out an independent thermal-hydraulic safety analysis for LB-LOCA of VVER-1200/491 and to investigate the agreement of the SAR conservative results with requirement stated in the IAEA Specific Safety Guide by using RELAP5/MOD 3.3 computer code with both conservative and best estimate approach.
10p
visnape
30-01-2023
7
4
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The traditional method to evaluate the feasibility of IVR-ERVC strategy is based on the steady state of the molten pool. But in the early stage, the transient behavior of the molten corium may impose a greater threat to the integrity of the reactor pressure vessel.
7p
vironald
15-12-2022
11
5
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During a hypothetical severe accident in a nuclear reactor most of the radioactivity would be released from the damaged core and the broken primary circuit in the form of aerosols and chemical vapours and gases. However the effective radio-toxicity per unit release from the fuel depends both on the released mass and on the chemical form as well.
13p
vironald
15-12-2022
13
4
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The nonlinear stability analysis of a supercritical light water reactor (SCLWR) is presented using a nuclearcoupled thermal-hydraulic reduced-order model. The analytical model is developed by coupling 1. the pointkinetics equations with one group of delayed neutrons, 2. the fuel heat transfer and 3. a 1-D reduced order model which represents the heat absorption phenomenon during the coolant flow.
20p
vironald
15-12-2022
15
5
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This study deals with the feasibility study of a new in-vessel core melt retention (IVCMR) strategy capable to extend the coping period in the event of adverse situations, involving the melting of the core. Since Fukushima accident, many studies have been carried out to resolve the severe accident mitigation issues related to the corium stabilization inside and outside the reactor vessel.
8p
vironald
15-12-2022
14
5
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This work addresses the conceptual design of a submerged nuclear power plant, where a horizontal cylindrical hull, placed on the floor of a sea or an artificial lake, hosts an integral pressurized Small Modular Reactor (SMR).
10p
vironald
15-12-2022
12
4
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This paper focuses on activation of oxygen isotopes in water and decay of this activated isotopes, i.e. 16N, 17N and 19O. An analysis of activation of water in pressurized water reactors and in fusion reactors was performed. Different evaluated nuclear data libraries were used in activation calculations (ENDF/B-VIII.0, FENDL-3.1b, JEFF-3.2 and TENDL-2015).
14p
vironald
15-12-2022
9
4
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One of the first steps in developing a risk assessment model is an exhaustive search for initiating events, which is a systematic and comprehensive starting point to answer the question “what can go wrong?” for a given system design.
14p
vironald
15-12-2022
11
5
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In this study, analysis of the complete operational history of the “Joˇzef Stefan” Institute (JSI) TRIGA reactor was performed. Reactor power changes, core configurations and weekly excess reactivity measurements were analysed to obtain the needed data for fuel burnup calculations.
21p
vironald
15-12-2022
13
4
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In this paper, we present a reduced-order modeling approach to study the Molten Salt Fast Reactor (MSFR). Our approach is nonintrusive and based on the proper orthogonal decomposition method. We include adaptivity in selecting the sampling points both in time and parameter space. Steady-state and transient analysis were both performed using the developed models.
14p
vironald
15-12-2022
11
4
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SuperCritical Water Reactor(SCWR) applies water beyond the thermodynamic critical point as the coolant, which aims to achieve high efficiency around 45% compared to 33% for existing commercial light water reactors.
15p
vironald
15-12-2022
11
4
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In the frame of Super-Critical Reactor In Pipe Test Preparation (SCRIPT) project in China, one of the challenge tasks is to predict the transient performance of SuperCritical Water Reactor-Fuel Qualification Test (SCWR-FQT) loop under some accident conditions. Several thermal–hydraulic codes (system code, sub-channel code) are selected to perform the safety analysis.
9p
vironald
15-12-2022
8
4
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In view of the potential deployment of demonstrators and prototypes associated with the European Sustainable Nuclear Industrial Initiative (ESNII), the present licensing framework, based on the current Light Water Reactor (LWR) technology, will have to adjust as necessary taking into account to the new safety aspects introduced by these innovative technologies.
15p
vironald
15-12-2022
12
4
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A model has been made of the primary shutdown system of an Advanced Gas-cooled Reactor nuclear power station. The aim of this paper is to explore the use of sensitivity analysis techniques on this model.
10p
vironald
15-12-2022
7
4
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The new reactor concepts proposed in the Generation IV International Forum require the development and validation of new components and new materials. Inside the Collaborative Project on the European Sodium Fast Reactor, several accidental scenario have been studied.
9p
vironald
15-12-2022
12
3
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Helium is relevant in determining nuclear fuel behaviour. It affects the performance of nuclear fuel both in reactor and in storage conditions. Helium becomes important in reactor conditions when high burnups are targeted or MOX fuel is used, whereas for storage conditions it can represent a threat to the fuel rods integrity.
7p
vironald
15-12-2022
11
3
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