TY - CONF AU - German, Péter AU - Szieberth, Máté AU - Nagy, Lajos AU - Kópházi, József AU - Danny, Lathouwers TI - Calculation of the higher alpha-modes of the VENUS-F fast subcritical system T2 - M&C2017 PB - Korea Nuclear Society PY - 2017 PG - 8 UR - https://m2.mtmt.hu/api/publication/3216770 ID - 3216770 LA - English DB - MTMT ER - TY - CHAP AU - German, Péter AU - Szieberth, Máté AU - Aranyosy, Ádám ED - anon, null TI - Sensitivity and Uncertainty Studies for a Lead Cooled Fast Reactor Core T2 - 2017 International Conference on Advances in Nuclear Power Plants PB - Atomic Energy Society of Japan CY - Tokyo SN - 9784890471676 PY - 2017 PG - 10 UR - https://m2.mtmt.hu/api/publication/3216763 ID - 3216763 LA - English DB - MTMT ER - TY - JOUR AU - German, Péter AU - Fehér, Sándor AU - Czifrus, Szabolcs AU - Yamaji, Bogdán TI - Analysis of heat source distribution in internal circulating surface heat transfer molten salt reactor JF - PROGRESS IN NUCLEAR ENERGY J2 - PROG NUCL ENERG VL - 92 PY - 2016 SP - 155 EP - 163 PG - 9 SN - 0149-1970 DO - 10.1016/j.pnucene.2016.07.018 UR - https://m2.mtmt.hu/api/publication/3120750 ID - 3120750 AB - The Molten Salt Reactor (MSR) is one of the Generation IV nuclear reactor concepts that were selected by the Generation IV International Forum in 2000. The concept is based on liquid fuel instead of solid fuel assemblies. Besides the advantages, there are several aspects of operation that can hinder the realization of this reactor concept. In this paper, the authors investigate the neutronics behaviour of a new sub-concept that offers solutions for many of the technical problems. The analysis was performed using the particle transport code MCNPX 2.7. The paper focuses on the short-term and steady state heat source distribution in the fuel salt and in the graphite moderator. Accordingly, neither burn-up effects nor reactivity transients are considered. The sensitivity of the effective multiplication factor on different geometrical and material parameters was studied. The results obtained indicate that the main region of heat deposition is in the internal and external channels of the graphite moderator. Only a few percent of the total heat power is released in the graphite moderator, where the gamma and neutron related heat deposition is on the same scale. The results also prove that the heat source distribution does not change drastically upon the actuation of the control rods. © 2016 Elsevier Ltd LA - English DB - MTMT ER -