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Journal articles on the topic 'Gas-cooled Fast Reactor'

Author: Grafiati

Published: 4 June 2021

Last updated: 16 February 2022

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1

Fielding, Randall, Mitch Meyer, Jan-Fong Jue, and Jian Gan. "Gas-cooled fast reactor fuel fabrication." Journal of Nuclear Materials 371, no. 1-3 (2007): 243–49. http://dx.doi.org/10.1016/j.jnucmat.2007.05.011.

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2

Polansky, Jiri. "Thermodynamics Cycle of Gas-Cooled Fast Reactor." Mechanics and Mechanical Engineering 22, no. 2 (2020): 585–92. http://dx.doi.org/10.2478/mme-2018-0046.

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AbstractThis paper deals with the thermo-hydraulic aspect of gas cooled fast 4 generation reactor. The paper is focused on the comparison of direct and indirect strategy of thermodynamics cycle of helium cooled reactor from the thermodynamics and turbomachinary point of view. The analyses respect pressure looses at all major part of the equipment - reactor, heat exchanger, pipe lines, etc. The compressor and gas turbines efficiency are includes in calculation as well. The working fluid in primary circuit is helium. In the secondary circuit a mixture of helium and nitrogen is considered. The Cy

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3

Stainsby, Richard, Karen Peers, Colin Mitchell, Christian Poette, Konstantin Mikityuk, and Joe Somers. "Gas cooled fast reactor research in Europe." Nuclear Engineering and Design 241, no. 9 (2011): 3481–89. http://dx.doi.org/10.1016/j.nucengdes.2011.08.005.

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4

Hejzlar, Pavel, Michael J. Pope, Wesley C. Williams, and Michael J. Driscoll. "Gas cooled fast reactor for generation IV service." Progress in Nuclear Energy 47, no. 1-4 (2005): 271–82. http://dx.doi.org/10.1016/j.pnucene.2005.05.077.

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5

Gužela, Štefan, František Dzianik, Martin Juriga, and Juraj Kabát. "Shell and Tube Heat Exchanger – the Heat Transfer Area Design Process." Strojnícky casopis – Journal of Mechanical Engineering 67, no. 2 (2017): 13–24. http://dx.doi.org/10.1515/scjme-2017-0014.

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AbstractNowadays, the operating nuclear reactors are able to utilise only 1 % of mined out uranium. An effective exploitation of uranium, even 60 %, is possible to achieve in so-called fast reactors. These reactors commercial operation is expected after the year 2035. Several design configurations of these reactors exist. Fast reactors rank among the so-called Generation IV reactors. Helium-cooled reactor, as a gas-cooled fast reactor, is one of them. Exchangers used to a heat transfer from a reactor active zone (i.e. heat exchangers) are an important part of fast reactors. This paper deals wi

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6

van Rooijen, W. F. G. "Gas-Cooled Fast Reactor: A Historical Overview and Future Outlook." Science and Technology of Nuclear Installations 2009 (2009): 1–11. http://dx.doi.org/10.1155/2009/965757.

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A review is given of developments in the area of Gas-Cooled Fast Reactors (GCFR) in the period from roughly 1960 until 1980. During that period, the GCFR concept was expected to increase the breeding gain, the thermal efficiency of a nuclear power plant, and alleviate some of the problems associated with liquid metal coolants. During this period, the GCFR concept was found to be more challenging than liquid-metal-cooled reactors, and none were ever constructed. In the second part of the paper, we provide an overview of the investigations on GCFR since the year 2000, when the Generation IV Init

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7

Zaki, Su'ud. "Unprotected Loss of Flow Accident in Small Long Life Gas Cooled Fast Reactor." Applied Mechanics and Materials 751 (April 2015): 263–67. http://dx.doi.org/10.4028/www.scientific.net/amm.751.263.

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In post Fukushima nuclear accidents inherent safety capability is necessary against some standard accidents such as unprotected loss of flow (ULOF), unprotected rod run-out transient over power (UTOP), unprotected loss of heat sink (ULOHS). Gas cooled fast reactors is one of the important candidate of 4th generation nuclear power plant and in this paper the safety analysis related to unprotected loss of flow in small long life gas cooled fast reactors has been performed. Accident analysis of unprotected loss of flow include coupled neutronic and thermal hydraulic analysis which include adiabat

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8

Monado, Fiber, Zaki Su’ud, Abdul Waris, Khairul Basar, Menik Ariani, and Hiroshi Sekimoto. "Application of Modified CANDLE Burnup to Very Small Long Life Gas-Cooled Fast Reactor." Advanced Materials Research 772 (September 2013): 501–6. http://dx.doi.org/10.4028/www.scientific.net/amr.772.501.

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Gas-cooled Fast Reactor is a good candidate for fourth generation nuclear power plant that projected to be used started in 2030. In this study, modified CANDLE burn-up strategy is adopted to create 300 MWt long life Gas-cooled Fast Reactor with metallic fuel U-10wt%Zr without enrichment. This design demonstrated excellent performance with the average discharge burn-up is about 25.9% HM.

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9

Kvizda, Boris, Gusztáv Mayer, Petr Vácha, et al. "ALLEGRO Gas-cooled Fast Reactor (GFR) demonstrator thermal hydraulic benchmark." Nuclear Engineering and Design 345 (April 2019): 47–61. http://dx.doi.org/10.1016/j.nucengdes.2019.02.006.

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10

Perkó, Zoltán, Sandro Pelloni, Konstantin Mikityuk, et al. "Core neutronics characterization of the GFR2400 Gas Cooled Fast Reactor." Progress in Nuclear Energy 83 (August 2015): 460–81. http://dx.doi.org/10.1016/j.pnucene.2014.09.016.

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11

Stacey, W. M., K. A. Boakye, S. K. Brashear, et al. "Advances in the Subcritical, Gas-Cooled, Fast Transmutation Reactor Concept." Nuclear Technology 159, no. 1 (2007): 72–105. http://dx.doi.org/10.13182/nt07-a3857.

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12

Zaki, Su’ud. "Accident Analysis Simulation in Modular 300MWt Gas Cooled Fast Reactor." Journal of Physics: Conference Series 799 (January 2017): 012003. http://dx.doi.org/10.1088/1742-6596/799/1/012003.

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13

Kumar, Akansha, Sunil S. Chirayath, and Pavel V. Tsvetkov. "Analysis of a sustainable gas cooled fast breeder reactor concept." Annals of Nuclear Energy 69 (July 2014): 252–59. http://dx.doi.org/10.1016/j.anucene.2014.02.016.

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14

Stainsby, Richard, Karen Peers, Colin Mitchell, Christian Poette, Konstantin Mikityuk, and Joe Somers. "Gas Cooled Fast Reactor Research and Development in the European Union." Science and Technology of Nuclear Installations 2009 (2009): 1–7. http://dx.doi.org/10.1155/2009/238624.

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Gas-cooled fast reactor (GFR) research is directed towards fulfilling the ambitious goals of Generation IV (Gen IV), that is, to develop a safe, sustainable, reliable, proliferation-resistant and economic nuclear energy system. The research is directed towards developing the GFR as an economic electricity generator, with good safety and sustainability characteristics. Fast reactors maximise the usefulness of uranium resources by breeding plutonium and can contribute to minimising both the quantity and radiotoxicity nuclear waste by actinide transmutation in a closed fuel cycle. Transmutation i

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15

Dzianik, František, Štefan Gužela, and Eva Puškášová. "Thermal Characteristics of High Temperature Naturally Circulating Helium Cooling Loop." Strojnícky casopis – Journal of Mechanical Engineering 68, no. 1 (2018): 1–10. http://dx.doi.org/10.2478/scjme-2018-0001.

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Abstract The paper deals with the process properties in terms of the heat transfer, i.e. the thermal performance of the thermal-process units within a helium loop intended for the testing of the decay heat removal (DHR) from the model of the gas-cooled fast reactor (GFR). The system is characterised by a natural circulation of helium, as a coolant, and assume the steady operating conditions of the circulation. The helium loop consists of four main components: the model of the gas-cooled fast reactor, the model of the heat exchanger for the decay heat removal, hot piping branch and cold piping

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16

Girardin, G., P. Coddington, F. Morin, G. Rimpault, and R. Chawla. "ICONE15-10466 DESIGN OF THE CONTROL ROD SYSTEM FOR THE 2400 MW_ GENERATION IV GAS-COOLED FAST REACTOR." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2007.15 (2007): _ICONE1510. http://dx.doi.org/10.1299/jsmeicone.2007.15._icone1510_249.

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17

Cheng, Lap-Yan, and Thomas Y. C. Wei. "Decay Heat Removal in GEN IV Gas-Cooled Fast Reactors." Science and Technology of Nuclear Installations 2009 (2009): 1–13. http://dx.doi.org/10.1155/2009/797461.

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The safety goal of the current designs of advanced high-temperature thermal gas-cooled reactors (HTRs) is that no core meltdown would occur in a depressurization event with a combination of concurrent safety system failures. This study focused on the analysis of passive decay heat removal (DHR) in a GEN IV direct-cycle gas-cooled fast reactor (GFR) which is based on the technology developments of the HTRs. Given the different criteria and design characteristics of the GFR, an approach different from that taken for the HTRs for passive DHR would have to be explored. Different design options bas

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18

Tran, Hoai Nam, Yasuyoshi Kato, Van Khanh Hoang, and Sy Minh Tuan Hoang. "Characteristics of a gas-cooled fast reactor with minor actinide loading." Nuclear Science and Technology 8, no. 2 (2021): 1–9. http://dx.doi.org/10.53747/jnst.v8i2.85.

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This paper presents the neutronics characteristics of a prototype gas-cooled (supercritical CO2-cooled) fast reactor (GCFR) with minor actinide (MA) loading in the fuel. The GCFR core is designed with a thermal output of 600 MWt as a part of a direct supercritical CO2 (S-CO2) gas turbine cycle. Transmutation of MAs in the GCFR has been investigated for attaining low burnup reactivity swing and reducing long-life radioactive waste. Minor actinides are loaded uniformly in the fuel regions of the core. The burnup reactivity swing is minimized to 0.11% ∆k/kk’ over the cycle length of 10 years when

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19

Zaki, Su'ud, Nuri Trianti, and Rosidah M. Indah. "Preliminary Analysis of Unprotected Loss of Heat Sink in Small Long Life Gas Cooled Fast Reactor." Applied Mechanics and Materials 751 (April 2015): 268–72. http://dx.doi.org/10.4028/www.scientific.net/amm.751.268.

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The failure of the secondary side in Gas Cooled Fast Reactor system, which may contain co-generation system, will cause loss of heat sink (LOHS) accident. In this study accident analysis of unprotected loss of heat sink due to the failure of the secondary cooling system has been investigated. The thermal hydraulic model include transient hot spot channel model in the core, steam generator, and related systems. Natural circulation based heat removal system is important to ensure inherent safety capability during unprotected accidents. Therefore the system similar to RVACS (reactor vessel auxili

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20

van Rooijen, W. F. G., J. L. Kloosterman, T. H. J. J. van der Hagen, and H. van Dam. "Fuel Design and Core Layout for a Gas-Cooled Fast Reactor." Nuclear Technology 151, no. 3 (2005): 221–38. http://dx.doi.org/10.13182/nt05-a3645.

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21

Martín-del-Campo, Cecilia, Ricardo Reyes-Ramírez, Juan-Luis François, and Arturo G. Reinking-Cejudo. "Contributions to the neutronic analysis of a gas-cooled fast reactor." Annals of Nuclear Energy 38, no. 6 (2011): 1406–11. http://dx.doi.org/10.1016/j.anucene.2011.01.029.

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22

Shamanin, Igor, Sergey Bedenko, Yuriy Chertkov, and Ildar Gubaydulin. "Gas-Cooled Thorium Reactor with Fuel Block of the Unified Design." Advances in Materials Science and Engineering 2015 (2015): 1–8. http://dx.doi.org/10.1155/2015/392721.

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Scientific researches of new technological platform realization carried out in Russia are based on ideas of nuclear fuel breeding in closed fuel cycle and physical principles of fast neutron reactors. Innovative projects of low-power reactor systems correspond to the new technological platform. High-temperature gas-cooled thorium reactors with good transportability properties, small installation time, and operation without overloading for a long time are considered perspective. Such small modular reactor systems at good commercial, competitive level are capable of creating the basis of the reg

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23

Soto, Alfredo, and David Delepine. "Neutronic studies for the actinides incineration in a Gas-cooled Fast Reactor (GFR)." Acta Universitaria 26, no. 1 (2016): 39–47. http://dx.doi.org/10.15174/au.2016.837.

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24

Choi, Hangbok, Robert W. Schleicher, and Puja Gupta. "A Compact Gas-Cooled Fast Reactor with an Ultra-Long Fuel Cycle." Science and Technology of Nuclear Installations 2013 (2013): 1–10. http://dx.doi.org/10.1155/2013/618707.

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In an attempt to allow nuclear power to reach its full economic potential, General Atomics is developing the Energy Multiplier Module (EM2), which is a compact gas-cooled fast reactor (GFR). The EM2augments its fissile fuel load with fertile materials to enhance an ultra-long fuel cycle based on a “convert-and-burn” core design which converts fertile material to fissile fuel and burns it in situ over a 30-year core life without fuel supplementation or shuffling. A series of reactor physics trade studies were conducted and a baseline core was developed under the specific physics design requirem

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25

Čížek, Jakub, Jana Kalivodová, Miloš Janeček, Josef Stráský, Ondřej Srba, and Anna Macková. "Advanced Structural Materials for Gas-Cooled Fast Reactors—A Review." Metals 11, no. 1 (2021): 76. http://dx.doi.org/10.3390/met11010076.

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This review summarizes the development of the Gas-Cooled Fast Reactor (GFR) concept from the early 1970s until now, focusing specifically on structural materials and advanced fuel cladding materials. Materials for future nuclear energy systems must operate under more extreme conditions than those in the current Gen II or Gen III systems. These conditions include higher temperatures, a higher displacement per atom, and more corrosive environments. This paper reviews previous GFR concepts in light of several promising candidate materials for the GFR system. It also reviews the recent development

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26

Kohyama, Akira. "Advanced SiC/SiC Composite Materials for Fourth Generation Gas Cooled Fast Reactors." Key Engineering Materials 287 (June 2005): 16–21. http://dx.doi.org/10.4028/www.scientific.net/kem.287.16.

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As one of the most important breakthrough in the field of SiC/SiC composite materials, the new process called Nano-powder Infiltration and Transient Eutectoid (NITE) Process has been developed. The outstanding total properties of the NITE SiC/SiC composites are presented. Then, the current efforts to make attractive GFR based on the NITE SiC/SiC composites and the technology R & D to make reactor components with the NITE SiC/SiC composites are provided together with our efforts on innovative reactor designs.

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27

Stacey, W. M., V. L. Beavers, W. A. Casino, et al. "A Subcritical, Gas-Cooled Fast Transmutation Reactor with a Fusion Neutron Source." Nuclear Technology 150, no. 2 (2005): 162–88. http://dx.doi.org/10.13182/nt05-a3614.

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28

Choi, Hangbok, Gérald Rimpault, and Jean C. Bosq. "A Physics Study of a 600-MW(thermal) Gas-Cooled Fast Reactor." Nuclear Science and Engineering 152, no. 2 (2006): 204–18. http://dx.doi.org/10.13182/nse06-a2576.

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29

Chen, X. N., L. Andriolo, A. Rineiski, E. Bubelis, G. Mayer, and F. Bentivoglio. "Extension and validation of SIMMER III code for gas cooled fast reactor." Annals of Nuclear Energy 81 (July 2015): 320–31. http://dx.doi.org/10.1016/j.anucene.2015.03.007.

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30

Anggraeni, Adeliya Ayu, Yanti Yulianti, and Posman Manurung. "Analisis Termal-hidrolik Reaktor Cepat Berpendingin Gas (Gas Cooled Fast Reactor) Menggunakan Metode Runge Kutta." Jurnal Teori dan Aplikasi Fisika 6, no. 2 (2018): 141–46. http://dx.doi.org/10.23960/jtaf.v6i2.1913.

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31

Dzianik, František, and Štefan Gužela. "Hydrodynamic Properties of High Temperature Natural Circulating Helium Cooling Loop." Strojnícky casopis – Journal of Mechanical Engineering 67, no. 1 (2017): 29–36. http://dx.doi.org/10.1515/scjme-2017-0003.

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Abstract The paper deals with the hydrodynamic properties, i.e. the consumption of mechanical energy expressed by pressure drops within a helium loop intended for the testing of decay heat removal (DHR) from the model of a gas-cooled fast reactor (GFR). The system is characterised by the natural circulation of helium, as a coolant, and assume steady operating conditions of circulation. The helium loop consists of four main components: model of gas-cooled fast reactor, model of the heat exchanger for decay heat removal, hot piping branch and cold piping branch. Using the process hydrodynamic ca

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32

Novalianda, S., M. Ariani, F. Monado, and Z. Su’ud. "Neutronic Design of Uranium-Plutonium Nitride Fuel-Based Gas-Cooled Fast Reactor (GFR)." Jurnal Pendidikan Fisika Indonesia 14, no. 2 (2018): 92–98. http://dx.doi.org/10.15294/jpfi.v14i2.6602.

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This study presents the calculation results of the cell, and core Gas-cooled Fast Reactor (GFR) based fuel Uranium-Plutonium Nitride (U, Pu)N. Parameter survey results of calculations of the fuel cell consisting of a kinf, burnup level, and the conversion ratio and for the calculation of the reactor core produce value keff during a refueling cycle. The calculation was performed by using a set of SRAC program by comparing three types of fuel cell designs. Reactor Design A based on natural uranium could not reach criticality because of keff < 1. Design B used the enrichment of uranium-235 by

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33

van Rooijen, W. F. G., and J. L. Kloosterman. "Closed Fuel Cycle and Minor Actinide Multirecycling in a Gas-Cooled Fast Reactor." Science and Technology of Nuclear Installations 2009 (2009): 1–9. http://dx.doi.org/10.1155/2009/282365.

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The Generation IV International Forum has identified the Gas-Cooled Fast Reactor (GCFR) as one of the reactor concepts for future deployment. The GCFR targets sustainability, which is achieved by the use of a closed nuclear fuel cycle where only fission products are discharged to a repository; all Heavy Metal isotopes are to be recycled in the reactor. In this paper, an overview is presented of recent results obtained in the study of the closed fuel cycle and the influence of the addition of extra Minor Actinide (MA) isotopes from existing LWR stockpiles. In the presented work, up to 10% of th

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34

Lima-Reinaldo, Yrobel, Juan-Luis François, and Cecilia Martín-del-Campo. "Analysis of the use of thorium in the GFR2400 gas-cooled fast reactor." Nuclear Engineering and Design 343 (March 2019): 11–21. http://dx.doi.org/10.1016/j.nucengdes.2018.12.016.

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35

Piera, Mireia, Carlos Corrochano, Alberto Abánades, and Javier Muñoz-Antón. "Conceptual design of a gas-cooled accelerator-driven reactor with very fast spectrum." Progress in Nuclear Energy 78 (January 2015): 361–71. http://dx.doi.org/10.1016/j.pnucene.2014.03.010.

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36

van Rooijen, W. F. G., J. L. Kloosterman, T. H. J. J. van der Hagen, and H. van Dam. "Lithium-6-Based Passive Reactivity Control Devices for a Gas-Cooled Fast Reactor." Nuclear Technology 159, no. 2 (2007): 119–33. http://dx.doi.org/10.13182/nt07-a3859.

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37

Osusky, Filip, Stefan Cerba, Jakub Luley, Branislav Vrban, and Jan Hascik. "COUPLED SIMULATION OF GAS COOLED FAST REACTOR FUEL ASSEMBLY WITH NESTLE CODE SYSTEM." Acta Polytechnica CTU Proceedings 14 (May 17, 2018): 34. http://dx.doi.org/10.14311/app.2018.14.0034.

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The paper is focused on coupled calculation of the Gas Cooled Fast Reactor. The proper modelling of coupled neutronics and thermal-hydraulics is the corner stone for future safety assessment of the control and emergency systems. Nowadays, the system and channel thermal-hydraulic codes are accepted by the national regulatory authorities in European Union for license purposes, therefore the code NESTLE was used for the simulation. The NESTLE code is a coupled multigroup neutron diffusion code with thermal-hydraulic sub-channel code. In the paper, the validation of NESTLE code 5.2.1 installation

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38

Dragunov, Yu G., A. A. Dunaitsev, D. D. Kim, P. V. Kobzev, V. V. Kudinov, and D. G. Kulikov. "Conception of a Transportable Small Power Plant with a Fast Gas-Cooled Reactor." Atomic Energy 126, no. 1 (2019): 1–6. http://dx.doi.org/10.1007/s10512-019-00504-6.

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39

Ariani, Menik, Zaki Su’ud, and Fiber Monado. "Design of Gas-Cooled Fast Reactor 600MWth with Natural Uranium As Fuel Circle Input." Jurnal ILMU DASAR 14, no. 1 (2013): 11. http://dx.doi.org/10.19184/jid.v14i1.476.

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This article presents the conceptual design of gas-cooled fast reactor (helium), the small size of the long-lived 600 MWth. Early stages of the design is to determine the geometry of the terrace, the value of the volume fraction and the mass fraction of fuel, cladding and coolant structure to calculate the parameters of reactivity, burnup, power distribution and density changes nuclides U238 and Pu239. The calculation is done using SRAC-CITATION code. SRAC code with JENDL-3.2 Data nuclides produced macroscopic cross section values for the eight energy group. Multi-group numerical solution of d

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40

Peakman, Aiden, and Bruno Merk. "The Role of Nuclear Power in Meeting Current and Future Industrial Process Heat Demands." Energies 12, no. 19 (2019): 3664. http://dx.doi.org/10.3390/en12193664.

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There is growing interest in the use of advanced reactor systems for powering industrial processes which could significantly help to reduce CO 2 emissions in the global energy system. However, there has been limited consideration into the role nuclear power would play in meeting current and future industry heat demand, especially with respect to the advantages and disadvantages nuclear power offers relative to other competing low-carbon technologies, such as Carbon Capture and Storage (CCS). In this study, the current market needs for high temperature heat are considered based on UK industry r

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41

Yamaguchi, Akira, Eisaku Tatsumi, Takashi Takata, et al. "Gas entrainment allowance level at free surface and gas dynamic behavior of sodium-cooled fast reactor." Nuclear Engineering and Design 241, no. 5 (2011): 1627–35. http://dx.doi.org/10.1016/j.nucengdes.2011.01.035.

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42

Ariani, Menik, Z. Su'ud, Fiber Monado, et al. "Optimization of Small Long Life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input." Applied Mechanics and Materials 260-261 (December 2012): 307–11. http://dx.doi.org/10.4028/www.scientific.net/amm.260-261.307.

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In this study gas cooled reactor system are combined with modified CANDLE burn-up scheme to create small long life fast reactors with natural circulation as fuel cycle input. Such system can utilize natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. Therefore using this type of nuclear power plants optimum nuclear energy utilization including in developing countries can be easily conducted without the problem of nuclear proliferation. In this paper, optimization of Small and Medium Long-life Gas Cooled Fast Reactors with Natural Uranium as Fu

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43

Osuský, F., R. Bahdanovich, G. Farkas, J. Haščík, and G. V. Tikhomirov. "Test case specifications for coupled neutronics-thermal hydraulics calculation of Gas-cooled Fast Reactor." Journal of Physics: Conference Series 781 (January 2017): 012038. http://dx.doi.org/10.1088/1742-6596/781/1/012038.

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44

Syarifah, Ratna Dewi, Zaki Su’ud, Khairul Basar, and Dwi Irwanto. "Actinide Minor Addition on Uranium Plutonium Nitride Fuel for Modular Gas Cooled Fast Reactor." Journal of Physics: Conference Series 1493 (March 2020): 012020. http://dx.doi.org/10.1088/1742-6596/1493/1/012020.

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45

Kheradmand Saadi, M., A. Abbaspour, and A. Pazirandeh. "Startup of “CANDLE” burnup in a Gas-cooled Fast Reactor using Monte Carlo method." Annals of Nuclear Energy 50 (December 2012): 44–49. http://dx.doi.org/10.1016/j.anucene.2012.07.019.

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46

Seleznev, Evgeny, and Valery Bereznev. "Application of diffusion approximation in the calculations of reactor with cavities." Nuclear Energy and Technology 4, no. 3 (2018): 203–9. http://dx.doi.org/10.3897/nucet.4.31863.

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The importance of calculation of radiation fields inside in-reactor cavities is associated with the necessity to simulate the emergency modes in fast breeder reactors (FBR), as well as reactor states with different coolant levels in special dedicated channels of passive feedback devices in lead-cooled fast reactors (LFR) of BREST type or in sodium cavities in sodium-cooled fast reactors (SFR). The Last Flight (LF) method (Bell and Glesston 1974, Davison 1960, DOORS3.2 1988, Mynatt et. al. 1969, Rhoades and Childs 1988, Rhoades and Sipmson 1997, SCALE 2009, Voloschenko et. al. 2012), or the met

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47

KIMURA, Nobuyuki, Toshiki EZURE, Akira TOBITA, and Hideki KAMIDE. "Experimental Study on Gas Entrainment at Free Surface in Reactor Vessel of a Compact Sodium-Cooled Fast Reactor." Journal of Nuclear Science and Technology 45, no. 10 (2008): 1053–62. http://dx.doi.org/10.1080/18811248.2008.9711892.

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48

Viaud, C., G. Carlot, P. Garcia, et al. "Thermal Behaviour of Xenon in a Refractory Metal for Gas Fast Reactor Fuel Elements." Defect and Diffusion Forum 272 (March 2008): 25–30. http://dx.doi.org/10.4028/www.scientific.net/ddf.272.25.

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Helium cooled Gas Fast Reactors (GFR) are designed for producing energy more efficiently and improving safety features such as a total retention of fission products (Xe, I, Cs). This study deals with the diffusion of xenon in refractory liners dedicated to the retention of fission products produced in GFR fuels. The material (W, Mo, W-Re, Mo-Re) will be located in the heart of the nuclear fuel element, where the operating temperature is in the 1000°C- 1600°C range. For the investigation of thermally activated rare gas behaviour, a γ-spectrometry analysis experiment has been performed on the 13

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Osuský, Filip, Štefan Čerba, Jakub Lüley, Branislav Vrban, Ján Haščík, and Vladimír Nečas. "On gas-cooled fast reactor designs – Nuclear data processing with sensitivity, uncertainty and similarity analyses." Progress in Nuclear Energy 128 (October 2020): 103450. http://dx.doi.org/10.1016/j.pnucene.2020.103450.

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Sardi, Widya, Dian Fitriyani, and Feriska Handayani Irka. "Analisis Neutronik pada Gas Cooled Fast Reactor (GCFR) dengan Variasi Umur Teras dan Daya Reaktor." Jurnal Fisika Unand 7, no. 2 (2018): 151–58. http://dx.doi.org/10.25077/jfu.7.2.151-158.2018.

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Telah dilakukan analisis neutronik pada Gas Cooled Fast Reactor (GCFR) dengan variasi umur teras dan daya reaktor. Reaktor ini menggunakan uranium alam sebagai bahan bakar dan helium sebagai pendingin. Parameter neutronik yang diamati meliputi faktor multiplikasi (keff) dan densitas bahan bakar. Pengaturan bahan bakar menggunakan strategi shuffling pada model teras silinder dua dimensi R-Z.Teras dibagi menjadi 10 region. Setiap 10 tahun bahan bakar yang ada pada masing-masing region di shuffling ke region berikutnya. Bahan bakar di region 10 dikeluarkan sedangkan pada region 1 akan diisi denga

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