Effect of power excursion on the thermal characteristics of VVER-1200 reactor; Бутаковские чтения

Bibliografiske detaljer
Parent link:Бутаковские чтения.— 2023.— С. 261-264
Hovedforfatter: Odii C. J.
Institution som forfatter: Национальный исследовательский Томский политехнический университет
Andre forfattere: Korotkikh A. G. Aleksandr Gennadievich (научный руководитель)
Summary:This work involved performing a thermal hydraulics calculation on VVER-1200 reactor. In this calculation, the thermal power of the reactor was varied in steps from 100 to 180 % power to determine its influence on the thermal-hydraulics parameters, especially the points of onset of nucleate boiling (ONB) and the onset of significant void (OSV) which is also referred to as point of net vapor generation (NVG). The exit coolant temperature, predicted coolant temperature at ONB, predicted coolant temperature at OSV, maximum heat flux, variation of linear heat generation rate along the heat channel, minimum point of critical heat flux (CHF) and the corresponding minimum departure from nucleate boiling ratio (MDNBR) were all noted for each power step. The result showed that at about 130 % power, the descending predicted coolant temperature at ONB crossed below the ascending exit coolant temperature, indicating an ONB, furthermore, at about 165 % power, the descending predicted coolant temperature at OSV crossed below the ascending exit coolant temperature, indicating an OSV. In this calculation, there were no variation in any other parameter of the reactor and the inlet enthalpy remained constant throughout the step variation of power.
Текстовый файл
Sprog:engelsk
Udgivet: 2023
Serier:Производство тепловой и электрической энергии
Fag:
Online adgang:https://earchive.tpu.ru/handle/11683/77634
Format: MixedMaterials Electronisk Book Chapter
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=671030

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200 1 |a Effect of power excursion on the thermal characteristics of VVER-1200 reactor  |f C. J. Odii, A. G. Korotkikh   |g sci. adv. A. G. Korotkikh ; National Research Tomsk Polytechnic University 
225 |a Производство тепловой и электрической энергии 
283 |2 RDAcarrier 
320 |a References: p. 264 
330 |a This work involved performing a thermal hydraulics calculation on VVER-1200 reactor. In this calculation, the thermal power of the reactor was varied in steps from 100 to 180 % power to determine its influence on the thermal-hydraulics parameters, especially the points of onset of nucleate boiling (ONB) and the onset of significant void (OSV) which is also referred to as point of net vapor generation (NVG). The exit coolant temperature, predicted coolant temperature at ONB, predicted coolant temperature at OSV, maximum heat flux, variation of linear heat generation rate along the heat channel, minimum point of critical heat flux (CHF) and the corresponding minimum departure from nucleate boiling ratio (MDNBR) were all noted for each power step. The result showed that at about 130 % power, the descending predicted coolant temperature at ONB crossed below the ascending exit coolant temperature, indicating an ONB, furthermore, at about 165 % power, the descending predicted coolant temperature at OSV crossed below the ascending exit coolant temperature, indicating an OSV. In this calculation, there were no variation in any other parameter of the reactor and the inlet enthalpy remained constant throughout the step variation of power.  
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