Assessment of the Radiotoxicity of Spent Nuclear Fuel from a Fleet of PWR Reactors

Oettingen, Mikołaj

doi:10.3390/en14113094

Cited by 20 publications

(12 citation statements)

References 21 publications

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“…The benchmarking will defi ne the areas of the reactor core physics that can be reliably modelled using the volumetric homogenization method, e.g. radiotoxicity of the spent nuclear fuel [9], which may facilitate the whole MHTR design methodology.…”

Section: Discussionmentioning

confidence: 99%

Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel

Oettingen

Cetnar

2021

Nukleonika

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The volumetric homogenization method for the simplified modelling of modular high-temperature gas-cooled reactor core with thorium-uranium fuel is presented in the paper. The method significantly reduces the complexity of the 3D numerical model. Hence, the computation time associated with the time-consuming Monte Carlo modelling of neutron transport is considerably reduced. Example results comprise the time evolutions of the effective neutron multiplication factor and fissionable isotopes (233U, 235U, 239Pu, 241Pu) for a few configurations of the initial reactor core.

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Section: Discussionmentioning

confidence: 99%

Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel

Oettingen

Cetnar

2021

Nukleonika

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“…At present, most of the calculations of spent fuel characteristics after in-service operation are performed by means of validated numerical codes such as ORIGEN (Oak Ridge Isotope Generation, developed at ORNL, Oak Ridge, TN, USA) or KORIGEN (FZK, Hannover, Germany). However, the behaviour out-ofreactor, at interim storage or final disposal, requires a detailed isotopic characterisation and radioactivity evaluation [6][7][8].…”

Section: Storage Strategiesmentioning

confidence: 99%

Assessment of Spent Nuclear Fuel in Ukrainian Storage System: Inventory and Performance

Dolin,

Lo Frano,

Cancemi

2024

Energies

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It is of meaningful importance to evaluate the performance of all the nuclear facilities, and particularly those part of such buildings where spent nuclear fuel (SNF) is stored to assess what kinds of consequences are anomalous/abnormal or to determine what types of accident events may occur. In this preliminary study, the strategies adopted for the management of SNF, and the risk related to them are discussed. The aim of this study is to evaluate the total radioactivity inventory characterising Ukrainian nuclear facilities, including storage facilities. The dataset used to calculate the total activity associated with nuclear fuel is provided and discussed. For the evaluation, it is considered that a SNF pool in VVER-1000 is designed to store 687 fuel assemblies, and 670 are in VVER-440. When it is half full, which is the case for 15 Ukrainian units, it will store about 2200 tU containing up to 1·1019 Bq of 137Cs, 7·1018 Bq of 90Sr, and 1·1019 Bq of TUE. This study focuses particularly on the total activity of the SNF stored at the Zaporozhye plant, the biggest nuclear plant in Europe, and the risk posed by the potential loss that cooling the plant could incur because of pond water level variation. The results of the analysis of the Zaporozhye NPP behaviour suggest that the water flow rate which keeps the SNF pool temperature constant is about 200,000 m3·day−1. Therefore, the water level in the pond should not be lower than 1.5–2 m; otherwise, the plant will need an additional source of water of more than 200,000 m3 per day to guarantee safe storage of SNF.

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“…. , y r(k+p|k) )] T ; (8) next, y k+1|k−1 denotes a rp×1 vector connected to the unforced output sequence (with control signal held at its current prior value) (9): y k+1|k−1 = [(y 1(k+1|k−1) , . .…”

Section: Model Predictive Controlmentioning

confidence: 99%

“…The subject of nuclear power plant operation discussed in the literature largely covers the issues of the nuclear fuel cycle for PWR reactors [8] or fourth generation reactors (GT-MHR) [9], as well as the issues of reactor operation safety. Nevertheless, from the point of view of the safe operation of a nuclear power plant, the issue of the operation of nuclear power plants in the power system under normal conditions, as well as the response of the control systems to sudden load changes in the system, is also relevant.…”

Section: Introduction 1power Generation Problem At Largementioning

confidence: 99%

Power System Stabilizer as a Part of a Generator MPC Adaptive Predictive Control System

et al. 2021

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In this paper, a model predictive controller based on a generator model for prediction purposes is proposed to replace a standard generator controller with a stabilizer of a power system. Such a local controller utilizes an input-output model of the system taking into consideration not only a generator voltage Ug but also an additional, auxiliary signal (e.g., α, Pg, or ωg). This additional piece of information allows for taking oscillations into account that occur in the system and minimizing their impact on the overall system performance. Parameters of models used by the controller are obtained on the basis of the introduced black-box models both for a turbine and a synchronous generator, parameters of which are estimated in an on line fashion using a RLS method. The aim of this paper is to compare the behavior of the classical generator control system with a power system stabilizer and a model predictive control with an additional feedback signal. The novelty of the paper is related to the use of the predictive controller instead of the classical controller/stabilizer system and its possibility of stabilizing the power system. Contrary to the solutions found in the literature, which are commonly-based on a fuzzy logic approach, the authors propose the use of an adaptive model predictive controller, which takes advantage of the knowledge concerning the plant in the form of a model and adapts itself to the operating point of the system using the model parameters estimation mechanism. Moreover, the adaptive predictive controller, unlike other solutions, automatically adjusts signal levels to changes in the plant. The proposed solution is able to calculate the best control signal regardless of whether these changes of the plant are caused by a change in the operating point, or resulting from operation, e.g., wear of mechanical parts.

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Assessment of the Radiotoxicity of Spent Nuclear Fuel from a Fleet of PWR Reactors

Cited by 20 publications

References 21 publications

Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel

Numerical modelling of modular high-temperature gas-cooled reactors with thorium fuel

Assessment of Spent Nuclear Fuel in Ukrainian Storage System: Inventory and Performance

Power System Stabilizer as a Part of a Generator MPC Adaptive Predictive Control System

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