Log in

Relevant bibliographies by topics / Pebble bed reactors – Cooling / Journal articles

To see the other types of publications on this topic, follow the link: Pebble bed reactors – Cooling.

Journal articles on the topic 'Pebble bed reactors – Cooling'

Author: Grafiati

Published: 4 June 2021

Last updated: 8 February 2022

Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles

Select a source type:

Consult the top 50 journal articles for your research on the topic 'Pebble bed reactors – Cooling.'

Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.

You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.

Browse journal articles on a wide variety of disciplines and organise your bibliography correctly.

1

Song, Shixiong, Xiangzhou Cai, Yafen Liu, Quan Wei, and Wei Guo. "Pore Scale Thermal Hydraulics Investigations of Molten Salt Cooled Pebble Bed High Temperature Reactor with BCC and FCC Configurations." Science and Technology of Nuclear Installations 2014 (2014): 1–16. http://dx.doi.org/10.1155/2014/589895.

Full text

Abstract:

The present paper systematically investigated pore scale thermal hydraulics characteristics of molten salt cooled high temperature pebble bed reactor. By using computational fluid dynamics (CFD) methods and employing simplified body center cubic (BCC) and face center cubic (FCC) model, pressure drop and local mean Nusselt number are calculated. The simulation result shows that the high Prandtl number molten salt in packed bed has unique fluid-dynamics and thermodynamic properties. There are divergences between CFD results and empirical correlations’ predictions of pressure drop and local Nusse

APA, Harvard, Vancouver, ISO, and other styles

2

Langston, Lee S. "PBMR-A Future Failsafe Gas Turbine Nuclear Power Plant?" Mechanical Engineering 133, no. 08 (2011): 54–59. http://dx.doi.org/10.1115/1.2011-aug-5.

Full text

Abstract:

This article presents an overview of a pebble bed modular reactor (PBMR) power plant. A PBMR power plant is a gas turbine nuclear power plant that completely eliminates the possibility of a devastating loss-of-coolant accident. In a PBMR power plant, uranium dioxide nuclear fuel, coated with mass diffusion and radioactive fission product containment layers of pyrolytic carbon and silicon carbide, is formed into nuclear poppy seed-sized fuel particles. Some 15,000 of these are embedded in a tennis ball-sized graphite sphere, which is encased in a thin carbon shell, sintered, annealed and machin

APA, Harvard, Vancouver, ISO, and other styles

3

Moormann, Rainer. "Fission Product Transport and Source Terms in HTRs: Experience from AVR Pebble Bed Reactor." Science and Technology of Nuclear Installations 2008 (2008): 1–14. http://dx.doi.org/10.1155/2008/597491.

Full text

Abstract:

Fission products deposited in the coolant circuit outside of the active core play a dominant role in source term estimations for advanced small pebble bed HTRs, particularly in design basis accidents (DBA). The deposited fission products may be released in depressurization accidents because present pebble bed HTR concepts abstain from a gas tight containment. Contamination of the circuit also hinders maintenance work. Experiments, performed from 1972 to 88 on the AVR, an experimental pebble bed HTR, allow for a deeper insight into fission product transport behavior. The activity deposition per

APA, Harvard, Vancouver, ISO, and other styles

4

Sadeghi, H., and M. Habibi. "Design and simulation of a blanket module for TOKAMAK reactors." Modern Physics Letters A 34, no. 13 (2019): 1950103. http://dx.doi.org/10.1142/s0217732319501037.

Full text

Abstract:

In this paper, we simulated an appropriate model for an advanced breeding blanket of future TOKAMAK fusion reactors with solid breeder (Li4SiO4) building material in the form of pebble beds, ODS ferritic steel as structural material and Beryllium as neutron multiplier. With the MCNPX code, the efficiency of this proposed model for the production and self-sufficiency of tritium was investigated. Total tritium breeding ratio of 1.15 is achieved. The helium-cooled pebble bed system and parameters of temperature and pressure are investigated by COMSOL multiphysics simulating software. The temperat

APA, Harvard, Vancouver, ISO, and other styles

5

Strydom, Gerhard. "Uncertainty and Sensitivity Analyses of a Pebble Bed HTGR Loss of Cooling Event." Science and Technology of Nuclear Installations 2013 (2013): 1–16. http://dx.doi.org/10.1155/2013/426356.

Full text

Abstract:

The Very High Temperature Reactor Methods Development group at the Idaho National Laboratory identified the need for a defensible and systematic uncertainty and sensitivity approach in 2009. This paper summarizes the results of an uncertainty and sensitivity quantification investigation performed with the SUSA code, utilizing the International Atomic Energy Agency CRP 5 Pebble Bed Modular Reactor benchmark and the INL code suite PEBBED-THERMIX. Eight model input parameters were selected for inclusion in this study, and after the input parameters variations and probability density functions wer

APA, Harvard, Vancouver, ISO, and other styles

6

Forsberg, Charles W., and Per F. Peterson. "FHR, HTGR, and MSR Pebble-Bed Reactors with Multiple Pebble Sizes for Fuel Management and Coolant Cleanup." Nuclear Technology 205, no. 5 (2019): 748–54. http://dx.doi.org/10.1080/00295450.2019.1573619.

Full text

APA, Harvard, Vancouver, ISO, and other styles

7

Sidi-Ali, Kamel, Khaled Oukil, Tinhinane Hassani, Yasmina Amri, and Abdelmoumane Alem. "Evaluation of radiation heat transfer in porous medial: Application for a pebble bed modular reactor cooled by CO2 gas." Nuclear Technology and Radiation Protection 28, no. 2 (2013): 118–27. http://dx.doi.org/10.2298/ntrp1302118s.

Full text

Abstract:

This work analyses the contribution of radiation heat transfer in the cooling of a pebble bed modular reactor. The mathematical model, developed for a porous medium, is based on a set of equations applied to an annular geometry. Previous major works dealing with the subject have considered the forced convection mode and often did not take into account the radiation heat transfer. In this work, only free convection and radiation heat transfer are considered. This can occur during the removal of residual heat after shutdown or during an emergency situation. In order to derive the governing equat

APA, Harvard, Vancouver, ISO, and other styles

8

Gonfiotti, Bruno, and Sandro Paci. "Normal and Accidental Scenarios Analyses with MELCOR 1.8.2 and MELCOR 2.1 for the DEMO Helium-Cooled Pebble Bed Blanket Concept." Science and Technology of Nuclear Installations 2015 (2015): 1–9. http://dx.doi.org/10.1155/2015/865829.

Full text

Abstract:

As for Light Water Reactors (LWRs), one of the most challenging accidents for the future DEMOnstration power plant is the Loss of Coolant Accident, which can trigger the pressurization of the confinement structures and components. Hence, careful analyses have to be executed to demonstrate that the confinement barriers are able to withstand the pressure peak within design limits and the residual cooling capabilities of the Primary Heat Transfer System are sufficient to remove the decay heat. To do so, severe accident codes, as MELCOR, can be employed. In detail, the MELCOR code has been develop

APA, Harvard, Vancouver, ISO, and other styles

9

Sun, Shiyan, Youjie Zhang, and Yanhua Zheng. "Research on Influence of Different Simulation Methods of Bypass Flow in Thermal Hydraulic Analysis on Temperature Distribution in HTR-10." Science and Technology of Nuclear Installations 2020 (June 26, 2020): 1–8. http://dx.doi.org/10.1155/2020/4754589.

Full text

Abstract:

In pebble-bed high temperature gas-cooled reactor, gaps widely exist between graphite blocks and carbon bricks in the reactor core vessel. The bypass helium flowing through the gaps affects the flow distribution of the core and weakens the effective cooling of the core by helium, which in turn affects the temperature distribution and the safety features of the reactor. In this paper, the thermal hydraulic analysis models of HTR-10 with bypass flow channels simulated at different positions are designed based on the flow distribution scheme of the original core models and combined with the actua

APA, Harvard, Vancouver, ISO, and other styles

10

Xie, F., W. Peng, J. Cao, et al. "Experimental Investigation of 14C in the Primary Coolant of the 10 MW High Temperature Gas-Cooled Reactor." Radiocarbon 61, no. 03 (2019): 867–84. http://dx.doi.org/10.1017/rdc.2019.6.

Full text

Abstract:

ABSTRACTThe very high temperature reactor (VHTR) is a development of the high-temperature gas-cooled reactors (HTGRs) and one of the six proposed Generation IV reactor concept candidates. The 10 MW high temperature gas-cooled reactor (HTR-10) is the first pebble-bed gas-cooled test reactor in China. A sampling system for the measurement of carbon-14 (14C) was established in the helium purification system of the HTR-10 primary loop, which could sample 14C from the coolant at three locations. The results showed that activity concentration of 14C in the HTR-10 primary coolant was 1.2(1) × 102 Bq/

APA, Harvard, Vancouver, ISO, and other styles

11

Langston, Lee S. "Pebbles Making Waves." Mechanical Engineering 130, no. 02 (2008): 34–38. http://dx.doi.org/10.1115/1.2008-feb-3.

Full text

Abstract:

This paper describes various high-level nuclear researches including nuclear-fuelled pebbles that are being conducted across South Africa. The pebbles are ingenious industrial products, designed to passively limit the amount of heat unleashed by the nuclear fission reactions that drive the reactor. The spheres that give the pebble bed reactor its name enclose fissionable uranium inside layers that serve various roles, such as moderating fission, containing pressure, and accommodating deformation of the core. Nuclear-fuelled pebbles are introduced at the top of the reactor vessel and slowly wen

APA, Harvard, Vancouver, ISO, and other styles

12

Chen, Hongyu, Chuan Li, Haoyu Xing, and Chao Fang. "The R&D of HTR-STAC Program Package: Source Term Analysis Codes for Pebble-Bed High-Temperature Gas-Cooled Reactor." Science and Technology of Nuclear Installations 2018 (December 2, 2018): 1–9. http://dx.doi.org/10.1155/2018/7389121.

Full text

Abstract:

Source term analysis is important in the design and safety analysis of advanced nuclear reactor and also provides a radiation safety analysis basis for Modular High-Temperature Gas-Cooled Reactor (HTR). High-Temperature Gas-Cooled Reactor-Pebble-bed Modules (HTR-PM) design by China is a typical Gen-IV and due to different safety concepts and systems, the implements of source term analysis in light water reactors are not entirely applicable to HTR-PM. To solve this problem, HTR-PM Source Term Analysis Code (HTR-STAC) has been developed and related V&V has been finished. HTR-STAC consists of

APA, Harvard, Vancouver, ISO, and other styles

13

Ruppersberg, J. C., and R. T. Dobson. "Flow and heat transfer in a closed loop thermosyphon Part II – experimental simulation." Journal of Energy in Southern Africa 18, no. 4 (2007): 41–48. http://dx.doi.org/10.17159/2413-3051/2007/v18i4a3393.

Full text

Abstract:

A closed loop thermosyphon is an energy transfer device that employs thermally induced density gra-dients to induce circulation of the working fluid thereby obviating the need for any mechanical moving parts such as pumps and pump controls. This increases the reliability and safety of the cool-ing system and reduces installation, operation and maintenance costs. These characteristics make it a particularly attractive option for the cavity cooling system of the Pebble Bed Modular Reactor (PBMR). Loop thermosyphons are however, known to become unstable under certain initial and operating conditi

APA, Harvard, Vancouver, ISO, and other styles

14

du Toit, C. G., and H. J. van Antwerpen. "Effect of reactor vessel cooling insulation and reflector heat pipes on the temperatures of a pebble-bed reactor using a system CFD approach." Nuclear Engineering and Design 357 (February 2020): 110421. http://dx.doi.org/10.1016/j.nucengdes.2019.110421.

Full text

APA, Harvard, Vancouver, ISO, and other styles

15

Zakharenkov, Aleksandr V., Ivan A. Tupotilov, and Kirill V. Zhuravlev. "An Experimental Study of Thermohydraulic Processes in the Model of a Fuel Assembly with Micro Fuel Elements." Vestnik MEI 3, no. 3 (2021): 19–25. http://dx.doi.org/10.24160/1993-6982-2021-3-19-25.

Full text

Abstract:

The test section design of the TVS-MEI experimental setup intended for studying the hydrodynamics and heat transfer in a fuel assembly with micro fuel elements is developed, and the setup hydraulic circuit is modernized. The setup process characteristics correspond to the operational parameters of VVER-1000 reactor plants (a pressure up to 16 MPa and coolant temperature up to 350°C). The internal heat release in the bed of metal pebbles is obtained by high-frequency induction heating. A technology for compacting the test section made of high-strength alundum ceramics and a special clamping dev

APA, Harvard, Vancouver, ISO, and other styles

16

Li, Hua, Suizheng Qiu, Guanghui Su, Wenxi Tian, and Youjia Zhang. "ICONE19-43215 NUMERICAL RESEARCH ON THE THERMAL HYDRAULICS OF THE COOLANT IN A PEBBLE BED REACTOR CORE BY CFD." Proceedings of the International Conference on Nuclear Engineering (ICONE) 2011.19 (2011): _ICONE1943. http://dx.doi.org/10.1299/jsmeicone.2011.19._icone1943_86.

Full text

APA, Harvard, Vancouver, ISO, and other styles

17

Husnayani, Ihda, and Pande Made Udiyani. "RADIONUCLIDE CHARACTERISTICS OF RDE SPENT FUELS." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 20, no. 2 (2018): 69. http://dx.doi.org/10.17146/tdm.2018.20.2.4101.

Full text

Abstract:

Reaktor Daya Eksperimental (RDE) is a 10 MWth pebble-bed High Temperature Gas-cooled Reactor that is planned to be constructed by National Nuclear Energy Agency of Indonesia (BATAN) in Puspiptek complex, Tangerang Selatan. RDE utilizes low enriched UO2 fuel coated by TRISO layers and loaded into the core by means of multipass loading scheme. Determination of radionuclide characteristics of RDE spent fuel; such as activity, thermal power, neutron and photon release rates; are very important because those characteristics are crucial to be used as a base for evaluating the safety of spent fuel ha

APA, Harvard, Vancouver, ISO, and other styles

18

Suikkanen, Heikki, Jouni Ritvanen, Payman Jalali, and Riitta Kyrki-Rajamäki. "Discrete element modelling of pebble packing in pebble bed reactors." Nuclear Engineering and Design 273 (July 2014): 24–32. http://dx.doi.org/10.1016/j.nucengdes.2014.02.022.

Full text

APA, Harvard, Vancouver, ISO, and other styles

19

Avramenko, A. A., N. P. Dmitrenko, М. M. Kovetskaya, and Yu Yu Kovetskaya. "EFFECT OF PERMEABILITY OF PEBLE BED ON HEAT TRANSFER IN THE CORE OF NUCLEAR REACTOR WITH HELIUM COOLANT." Industrial Heat Engineering 39, no. 4 (2017): 55–60. http://dx.doi.org/10.31472/ihe.4.2017.08.

Full text

Abstract:

Heat and mass transfer in a model of the core of a nuclear reactor with spherical fuel elements and a helium coolant was studied. The effect of permeability of the pebble bed zone and geometric parameters on the temperature distribution of the coolant in the reactor core is analyzed.

APA, Harvard, Vancouver, ISO, and other styles

20

Moses, David L. "Nuclear safeguards considerations for pebble bed reactors (PBRs)." Nuclear Engineering and Design 251 (October 2012): 216–21. http://dx.doi.org/10.1016/j.nucengdes.2011.10.043.

Full text

APA, Harvard, Vancouver, ISO, and other styles

21

Park, H., D. A. Knoll, D. R. Gaston, and R. C. Martineau. "Tightly Coupled Multiphysics Algorithms for Pebble Bed Reactors." Nuclear Science and Engineering 166, no. 2 (2010): 118–33. http://dx.doi.org/10.13182/nse09-104.

Full text

APA, Harvard, Vancouver, ISO, and other styles

22

Ronen, Yigal, Menashe Aboudy, Dror Regev, and Erez Gilad. "Proliferation Resistant Fuel for Pebble Bed Modular Reactors." Nuclear Science and Engineering 175, no. 2 (2013): 149–56. http://dx.doi.org/10.13182/nse12-84.

Full text

APA, Harvard, Vancouver, ISO, and other styles

23

Kadak, Andrew C. "A future for nuclear energy: pebble bed reactors." International Journal of Critical Infrastructures 1, no. 4 (2005): 330. http://dx.doi.org/10.1504/ijcis.2005.006679.

Full text

APA, Harvard, Vancouver, ISO, and other styles

24

Englert, Matthias, Friederike Frieß, and M. V. Ramana. "Accident Scenarios Involving Pebble Bed High Temperature Reactors." Science & Global Security 25, no. 1 (2017): 42–55. http://dx.doi.org/10.1080/08929882.2017.1275320.

Full text

APA, Harvard, Vancouver, ISO, and other styles

25

Grimod, Maurice, Richard Sanchez, and Frédéric Damian. "A dynamic homogenization model for pebble bed reactors." Journal of Nuclear Science and Technology 52, no. 7-8 (2015): 932–44. http://dx.doi.org/10.1080/00223131.2015.1037809.

Full text

APA, Harvard, Vancouver, ISO, and other styles

26

Mphahlele, Ramatsemela, Abderrafi M. Ougouag, Kostadin N. Ivanov, and Hans D. Gougar. "Spectral zone selection methodology for pebble bed reactors." Annals of Nuclear Energy 38, no. 1 (2011): 80–87. http://dx.doi.org/10.1016/j.anucene.2010.08.014.

Full text

APA, Harvard, Vancouver, ISO, and other styles

27

Gong, Baoping, Hao Cheng, Yongjin Feng, Xiaofang Luo, Long Wang, and Xiaoyu Wang. "Effect of Pebble Size Distribution and Wall Effect on Inner Packing Structure and Contact Force Distribution in Tritium Breeder Pebble Bed." Energies 14, no. 2 (2021): 449. http://dx.doi.org/10.3390/en14020449.

Full text

Abstract:

In the tritium breeding blanket of nuclear fusion reactors, the heat transfer behavior and thermal-mechanical response of the tritium breeder pebble bed are affected by the inner packing structure, which is crucial for the design and optimization of a reliable pebble bed in tritium breeding blanket. Thus, the effect of pebble size distribution and fixed wall effect on packing structure and contact force in the poly-disperse pebble bed were investigated by numerical simulation. The results show that pebble size distribution has a significant influence on the inner packing structure of pebble be

APA, Harvard, Vancouver, ISO, and other styles

28

Rostamian, Maziar, Gabriel P. Potirniche, Joshua J. Cogliati, Abderrafi Ougouag, and Akira Tokuhiro. "Computational prediction of dust production in pebble bed reactors." Nuclear Engineering and Design 243 (February 2012): 33–40. http://dx.doi.org/10.1016/j.nucengdes.2011.12.011.

Full text

APA, Harvard, Vancouver, ISO, and other styles

29

Valko, J., P. V. Tsvetkov, and J. E. Hoogenboom. "Calculation of the Dancoff Factor for Pebble Bed Reactors." Nuclear Science and Engineering 135, no. 3 (2000): 304–7. http://dx.doi.org/10.13182/nse00-a2143.

Full text

APA, Harvard, Vancouver, ISO, and other styles

30

Fratoni, Massimiliano, and Ehud Greenspan. "Equilibrium Core Composition Search Methodologies for Pebble Bed Reactors." Nuclear Science and Engineering 166, no. 1 (2010): 1–16. http://dx.doi.org/10.13182/nse09-66.

Full text

APA, Harvard, Vancouver, ISO, and other styles

31

Rostamian, M., S. Arifeen, G. P. Potirniche, and A. Tokuhiro. "Initial prediction of dust production in pebble bed reactors." Mechanical Sciences 2, no. 2 (2011): 189–95. http://dx.doi.org/10.5194/ms-2-189-2011.

Full text

Abstract:

Abstract. This paper describes the computational simulation of contact zones between pebbles in a pebble bed reactor. In this type of reactor, the potential for graphite dust generation from frictional contact of graphite pebbles and the subsequent transport of dust and fission products can cause significant safety issues at very high temperatures around 900 °C in HTRs. The present simulation is an initial attempt to quantify the amount of nuclear grade graphite dust produced within a very high temperature reactor.

APA, Harvard, Vancouver, ISO, and other styles

32

Boer, B., J. L. Kloosterman, D. Lathouwers, and T. H. J. J. van der Hagen. "In-core fuel management optimization of pebble-bed reactors." Annals of Nuclear Energy 36, no. 8 (2009): 1049–58. http://dx.doi.org/10.1016/j.anucene.2009.06.008.

Full text

APA, Harvard, Vancouver, ISO, and other styles

33

Liem, P. H. "Design procedures for small pebble-bed high temperature reactors." Annals of Nuclear Energy 23, no. 3 (1996): 207–15. http://dx.doi.org/10.1016/0306-4549(95)00018-1.

Full text

APA, Harvard, Vancouver, ISO, and other styles

34

Lee, Kyoung O., and Robin P. Gardner. "Prediction of Pebble Motion in Pebble-Bed Reactors Using Monte Carlo Molecular Dynamics Simulation." Nuclear Science and Engineering 174, no. 3 (2013): 264–85. http://dx.doi.org/10.13182/nse12-23.

Full text

APA, Harvard, Vancouver, ISO, and other styles

35

Auwerda, G. J., J. L. Kloosterman, D. Lathouwers, and T. H. J. J. van der Hagen. "Effects of random pebble distribution on the multiplication factor in HTR pebble bed reactors." Annals of Nuclear Energy 37, no. 8 (2010): 1056–66. http://dx.doi.org/10.1016/j.anucene.2010.04.008.

Full text

APA, Harvard, Vancouver, ISO, and other styles

36

Yang, Xingtuan, Yu Li, Nan Gui, Xinlong Jia, Jiyuan Tu, and Shengyao Jiang. "Some Movement Mechanisms and Characteristics in Pebble Bed Reactor." Science and Technology of Nuclear Installations 2014 (2014): 1–10. http://dx.doi.org/10.1155/2014/820481.

Full text

Abstract:

The pebblebed-type high temperature gas-cooled reactor is considered to be one of the promising solutions for generation IV advanced reactors, and the two-region arranged reactor core can enhance its advantages by flattening neutron flux. However, this application is held back by the existence of mixing zone between central and peripheral regions, which results from pebbles’ dispersion motions. In this study, experiments have been carried out to study the dispersion phenomenon, and the variation of dispersion region and radial distribution of pebbles in the specifically shaped flow field are s

APA, Harvard, Vancouver, ISO, and other styles

37

Kloosterman, J. L., and A. M. Ougouag. "Comparison and Extension of Dancoff Factors for Pebble-Bed Reactors." Nuclear Science and Engineering 157, no. 1 (2007): 16–29. http://dx.doi.org/10.13182/nse07-a2710.

Full text

APA, Harvard, Vancouver, ISO, and other styles

38

Fratoni, Massimiliano, and Ehud Greenspan. "Neutronic Feasibility Assessment of Liquid Salt–Cooled Pebble Bed Reactors." Nuclear Science and Engineering 168, no. 1 (2011): 1–22. http://dx.doi.org/10.13182/nse10-38.

Full text

APA, Harvard, Vancouver, ISO, and other styles

39

Hassan, Yassin A. "Large eddy simulation in pebble bed gas cooled core reactors." Nuclear Engineering and Design 238, no. 3 (2008): 530–37. http://dx.doi.org/10.1016/j.nucengdes.2007.02.041.

Full text

APA, Harvard, Vancouver, ISO, and other styles

40

SEKIMOTO, Hiroshi, Tohru OBARA, Shigeru YUKINORI, and Eiichi SUETOMI. "New Method to Analyze Equilibrium Cycle of Pebble-Bed Reactors." Journal of Nuclear Science and Technology 24, no. 10 (1987): 765–72. http://dx.doi.org/10.1080/18811248.1987.9735880.

Full text

APA, Harvard, Vancouver, ISO, and other styles

41

Vergari, Lorenzo, and Massimiliano Fratoni. "Spent fuel management strategies for fluoride-cooled pebble bed reactors." Nuclear Engineering and Design 378 (July 2021): 111189. http://dx.doi.org/10.1016/j.nucengdes.2021.111189.

Full text

APA, Harvard, Vancouver, ISO, and other styles

42

Sun, Sida, Hong Li, and Sheng Fang. "The Optimization of Radiation Protection in the Design of the High Temperature Reactor-Pebble-Bed Module." Science and Technology of Nuclear Installations 2017 (2017): 1–15. http://dx.doi.org/10.1155/2017/3984603.

Full text

Abstract:

The optimization of radiation protection is an important task in both the design and operation of a nuclear power plant. Although this topic has been considerably investigated for pressurized water reactors, there are very few public reports on it for pebble-bed reactors. This paper proposes a routine that jointly optimizes the system design and radiation protection of High Temperature Reactor-Pebble-Bed Module (HTR-PM) towards the As Low As Reasonably Achievable (ALARA) principle. A systematic framework is also established for the optimization of radiation protection for pebble-bed reactors.

APA, Harvard, Vancouver, ISO, and other styles

43

Bernnat, W., and W. Feltes. "Models for reactor physics calculations for HTR pebble bed modular reactors." Nuclear Engineering and Design 222, no. 2-3 (2003): 331–47. http://dx.doi.org/10.1016/s0029-5493(03)00036-0.

Full text

APA, Harvard, Vancouver, ISO, and other styles

44

Ananich, P. I., A. P. Akhramovich, V. T. Kazazyan, et al. "Possibility of developing low-power reactors with a pebble-bed core." Atomic Energy 97, no. 3 (2004): 598–603. http://dx.doi.org/10.1007/s10512-005-0037-5.

Full text

APA, Harvard, Vancouver, ISO, and other styles

45

Ho, Hai Quan, and Toru Obara. "Burnup performance of OTTO cycle pebble bed reactors with ROX fuel." Annals of Nuclear Energy 83 (September 2015): 1–7. http://dx.doi.org/10.1016/j.anucene.2015.04.001.

Full text

APA, Harvard, Vancouver, ISO, and other styles

46

Merzari, Elia, Haomin Yuan, Misun Min, et al. "Cardinal: A Lower-Length-Scale Multiphysics Simulator for Pebble-Bed Reactors." Nuclear Technology 207, no. 7 (2021): 1118–41. http://dx.doi.org/10.1080/00295450.2020.1824471.

Full text

APA, Harvard, Vancouver, ISO, and other styles

47

Bakhshayesh, Moshkbar, and Naser Vosoughi. "A simulation of a pebble bed reactor core by the MCNP-4C computer code." Nuclear Technology and Radiation Protection 24, no. 3 (2009): 177–82. http://dx.doi.org/10.2298/ntrp0903177b.

Full text

Abstract:

Lack of energy is a major crisis of our century; the irregular increase of fossil fuel costs has forced us to search for novel, cheaper, and safer sources of energy. Pebble bed reactors - an advanced new generation of reactors with specific advantages in safety and cost - might turn out to be the desired candidate for the role. The calculation of the critical height of a pebble bed reactor at room temperature, while using the MCNP-4C computer code, is the main goal of this paper. In order to reduce the MCNP computing time compared to the previously proposed schemes, we have devised a new simul

APA, Harvard, Vancouver, ISO, and other styles

48

Keppler, Istvan. "Failure analysis of pebble bed reactors during earthquake by discrete element method." Nuclear Engineering and Design 258 (May 2013): 102–6. http://dx.doi.org/10.1016/j.nucengdes.2013.01.028.

Full text

APA, Harvard, Vancouver, ISO, and other styles

49

Rycroft, Chris H., Abdel Dehbi, Terttaliisa Lind, and Salih Güntay. "Granular flow in pebble-bed nuclear reactors: Scaling, dust generation, and stress." Nuclear Engineering and Design 265 (December 2013): 69–84. http://dx.doi.org/10.1016/j.nucengdes.2013.07.010.

Full text

APA, Harvard, Vancouver, ISO, and other styles

50

Ougouag, Abderrafi M., Jan Leen Kloosterman, Wilfred F. G. van Rooijen, Hans D. Gougar, and William K. Terry. "Investigation of bounds on particle packing in pebble-bed high temperature reactors." Nuclear Engineering and Design 236, no. 5-6 (2006): 669–76. http://dx.doi.org/10.1016/j.nucengdes.2005.12.006.

Full text

APA, Harvard, Vancouver, ISO, and other styles

We offer discounts on all premium plans for authors whose works are included in thematic literature selections. Contact us to get a unique promo code!