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Preliminary computational and experimental design studies of the ISHTAR thermostatic rig for the high-temperature reactors materials irradiation

Talarowska Anna, Lipka Maciej, Wojtania Grzegorz

Nukleonika

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2021

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Vol. 66, No. 4

127--132

EN

The Ir radiation System for High-Temperature Reactors (ISHTAR) thermostatic rig will be used to irradiate advanced core material samples in conditions corresponding to those prevailing in the high-temperature reactors (HTRs): these conditions include a stable temperature extending up to 1000°C in the helium atmosphere. Computational and experimental studies concerning the design have been conducted, proving the possibility of these conditions’ fulfi llment inside the rig while maintaining the safety limits for MARIA research reactor. The outcome is the thermostatic rig design that will be implemented in the MARIA reactor. Appropriate irradiation temperature will be achieved by a combination of electric heating with the control system, gamma heating, and a helium insulation gap with precisely designed thickness. The ISHTAR rig will be placed inside the vertical irradiation channel, which is located in the reactor pool. The device is being developed from scratch at the Nuclear Facilities Operation Department of the National Centre for Nuclear Research as a part of the GOSPOSTRATEG programme

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Modelling of thermal hydraulics in a KAROLINA calorimeter for its calibration methodology validation

Luks A., Pytel K., Tarchalski M., Uzunow N., Krok T.

Nukleonika

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2016

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Vol. 61, No. 4

453--460

EN

Results of numerical calculations of heat exchange in a nuclear heating detector for nuclear reactors are presented in this paper. The gamma radiation is generated in nuclear reactor during fission and radiative capture reactions as well as radioactive decay of its products. A single-cell calorimeter has been designed for application in the MARIA research reactor in the National Centre for Nuclear Research (NCBJ) in Świerk near Warsaw, Poland, and can also be used in the Jules Horowitz Reactor (JHR), which is under construction in the research centre in Cadarache, France. It consists of a cylindrical sample, which is surrounded by a gas layer, contained in a cylindrical housing. Additional calculations had to be performed before its insertion into the reactor. Within this analysis, modern computational fuid dynamics (CFD) methods have been used for assessing important parameters, for example, mean surface temperature, mean volume temperature, and maximum sample (calorimeter core) temperature. Results of an experiment performed at a dedicated out-of-pile calibration bench and results of numerical modelling validation are also included in this paper.

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Reaktor MARIA widziany w 2004 roku z perspektywy trzydziestolecia jego eksploatacji

Dąbek W., Mikulski A.

Postępy Techniki Jądrowej

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2015

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z. 2

9--11

PL

Artykuł przedstawia nieznane lub mało znane informacje dotyczące projektowania i budowy polskiego uniwersalnego, wysokostrumieniowego reaktora badawczego o mocy ok. 30 MW w Instytucie Badań Jądrowych (IBJ) w Świerku. W ramach prowadzenia prac projektowych zbudowano dwa zestawy krytyczne do badania rdzeni reaktorów. W artykule przytoczono niezwykle trudne na owe czasy problemy, które musiał rozwiązać IBJ w związku z konstrukcją tak nietypowego obiektu docelowego. Zgodnie z harmonogramem w połowie grudnia 1974 r. przeprowadzono doświadczenie krytyczne reaktora, któremu nadano imię MARIA. Artykuł został napisany przez doc. Wacława Dąbka zmarłego w 2014 r. byłego zastępcy dyrektora IBJ ds. energetyki.

EN

The paper describes generally unknown works connected with the design and construction of a new, general purpose high-flux research reactor of 30 MW power in Institute of Nuclear Research (INR) at Swierk. In a frame of design two critical assemblies were constructed for testing of reactor cores., The paper describes unusual difficult problem at those times to be solved by INR staff in a connection with construction of such no usual object. According to schedule in December 1974 critical experiment of the new reactor, named MARIA has been carried out. The paper was written by Mr. Wacław Dąbek, former deputy director of INR, who passed away in 2014.