Search Results

You are looking at 1 - 8 of 8 items for :

Clear All
Open access

Grzegorz Kępisty and Jerzy Cetnar

Abstract

In this paper, we compare the methodology of different time-step models in the context of Monte Carlo burnup calculations for nuclear reactors. We discuss the differences between staircase step model, slope model, bridge scheme and stochastic implicit Euler method proposed in literature. We focus on the spatial stability of depletion procedure and put additional emphasis on the problem of normalization of neutron source strength. Considered methodology has been implemented in our continuous energy Monte Carlo burnup code (MCB5). The burnup simulations have been performed using the simplified high temperature gas-cooled reactor (HTGR) system with and without modeling of control rod withdrawal. Useful conclusions have been formulated on the basis of results.

Open access

Natalia Szewczuk-Krypa, Marta Drosińska-Komor, Jerzy Głuch and Łukasz Breńkacz

BIBLIOGRAPHY 1. Baek J-K., Mistarihi Q., Yeo S., et al.: A Preliminary Study for Diffusion Experiments of Metallic Fission Products in Graphite for HTGR . Transaction of the Korean Nuclear Society Autumn Meeting Gyeongiu, Korea, October 29-30, 2015 2. Carlton J S., Smarta R., Jenkins V.: The nuclear propulsion of merchant ships: Aspects of engineering, science and technology . Journal of Marine Engineering & Technology 2011, pp. 47-59 3. Gardzilewicz A., Głuch J., Bogulicz M. (1994): DIAGAR manual for turbine set No. 3 at Kozienice Power Plant

Open access

Marcin Grodzki, Piotr Darnowski and Grzegorz Niewiński

. [12] Gas turbine-modular helium reactor (GT-MHR) conceptual design description report.Tech. Rep., General Atomics, 1996. [13] Zwaan S.J. de: Feasibility Study of the U-Battery, PNR-131-2007-004, 2007. [14] History and Evolution of the HTGR. General Atomic, 2007. [15] IAEA Current status and future development of modular high temperature gas cooled reactor technology. IAEA, 2001. [16] Prismatic coupled neutronic/thermal fluids transient benchmark of the MHTGR MW core design, Benchmark definition 2011

Open access

Natalia Szewczuk-Krypa, Anna Grzymkowska and Jerzy. Głuch

Abstract

This paper presents a comparative analysis of thermodynamic cycles of two ship power plant systems with a high-temperature helium-cooled nuclear reactor. The first of them is a gas system with recuperator, in which classical gas chamber is substituted for a HTGR reactor (High Temperature Gas-cooled Reactor). The second of the considered cycles is a combined gas-steam system where working medium flux from gas turbine outlet is directed into waste heat boiler and its heat is utilized for production of superheated steam to drive steam turbine. Preliminary calculations of the combine cycles showed that it is necessary to expand the system by adding to its steam part an inter-stage overheat for secondary steam, owing to that a required degree of steam dryness at outlet from the turbine can be reached, ensuring its correct operational conditions. The analyzed power systems were compared to each other with regard to efficiency of their thermodynamic cycles. Also, efficiency of particular cycles were subjected to optimization in respect to such parameters as : working gas temperature at outlet from reactor in gas system as well as steam pressure at outlet from waste heat boiler and partition pressure in steam part of combined system. Advantages of nuclear power plants compared with the classical power systems dominating currently in sea transport were also discussed.

Open access

Projects of High-Temperature Nuclear Reactors

(Overview. Part 2) / Augstas Temperatūras Kodolreaktoru Projekti

J. Ekmanis, E. Tomsons and N. Zeltiņš

Part 2 of the overview gives emphasis to the projects of high-temperature NRs, whose development is an area of active engagement for the specialists from the USA, France, Japan, Russia, China, the Netherlands, and Germany. Projects of several powerful NRs of the HTGR type for commercial use had been worked out in the USA and Germany already by 1970 but not yet implemented.

Open access

Daniela Marušáková, Jan Berka and Petr Sajdl

LITERATURA 1. Berka, J., Hlinčík, T., Víden, I., Hudský, T., Vít, J. Progress in Nuclear Energy 2015 , 85 , 156–163. 2. Berka, J., Matěcha, J., Černý, M., Víden, I., Sus, F., Hájek, P. Nuclear Engineering and Design 2012 , 251 , 203–207. 3. Natesan K., Purohit, A., Tam S. W.: report NUREG/CR-6824: Materials Behavior in HTGR Environments 2003, Office of Nuclear Regulatory Research, Washington. 4. Yun, M. H., Ennis, J. P., Nickel, H., Schuster, H. Journal of Nuclear Materials 1984 , 125, 258–272 5. Graham, W. L. Journal

Open access

J. Berka, D. Marušáková and J. Kalivodová

NUREG/CR-6824: Materials Behaviour in HTGR Environments, Office of Nuclear Regulatory Research , Washington, 2003. 6. Berka J., Víden I., Paliva 2014 , 6(1), 7–19. 7. Berka J., Černý M., Matěcha J., Paliva 2010 , 2, 64–70. 8. Berka J., Hlinčík T., Víden I., Hudský T., Vít J., Progress in Nuclear Energy 2015 , 85, 156–163. 9. Berka J., Matěcha J., Černý M., Víden I., Sus F., Hájek P., Nuclear Engineering and Design 2012 , 251, 203–207. 10. Hotař A., Palm M., Intermetallics 2010 , 18,1390–1395. 11. Berka J., Vilémová M

Open access

Adam Fic, Jan Składzień and Michał Gabriel

of hydrogen production systems using alternative nuclear energy technologies. Int. J. Hydrogen Energ. 31 (2006), 77–92. [5] Y anhui X., H uaiming J., D axin Z.: HTGR Process Heat Application Study . Tsinghua Science and Technology 10/19 (1996), 1, 40–44, ISSN 1007-2024. [6] K urh R.: HTR’s role in process heat applications. Nucl. Eng. Des. 238 (2008), 3013–3017. [7] M armier A., F üttererv M.A.: Nuclear powered heat pumps for near-term process heat applications . Nuc. Eng. Des. 238 (2008), 2272–2284. [8] H anuszkiewicz -D