@article{MTMT:2665956,
	title = {Thorium as an alternative fuel for SCWRs},
	url = {https://m2.mtmt.hu/api/publication/2665956},
	author = {Csom, Gyula and Reiss, Tibor and Fehér, Sándor and Czifrus, Szabolcs},
	doi = {10.1016/j.anucene.2011.11.007},
	journal-iso = {ANN NUCL ENERGY},
	journal = {ANNALS OF NUCLEAR ENERGY},
	volume = {41},
	unique-id = {2665956},
	issn = {0306-4549},
	year = {2012},
	eissn = {1873-2100},
	pages = {67-78}
}

@article{MTMT:2664024,
	title = {Full-core SSCWR calculations applying a fast computational method},
	url = {https://m2.mtmt.hu/api/publication/2664024},
	author = {Reiss, Tibor and Csom, Gyula and Fehér, Sándor and Czifrus, Szabolcs and Szieberth, Máté},
	doi = {10.1016/j.pnucene.2010.06.003},
	journal-iso = {PROG NUCL ENERG},
	journal = {PROGRESS IN NUCLEAR ENERGY},
	volume = {52},
	unique-id = {2664024},
	issn = {0149-1970},
	abstract = {The Supercritical Water-Cooled Reactor (SCWR) is a generation IV reactor concept which uses supercritical pressure water as coolant. By now, several versions of these concepts have been developed. A new thermal design called Simplified SCWR (SSCWR) was proposed in Reiss et al. (2010): the most important characteristics of the assembly are partial-length zirconium-hydride rods as extra moderator, axially varying fuel enrichment and a longer active length; also, the core had a smaller diameter compared to the original SCWR concept. This new type of assembly is optimized taking into account the neutronic and thermal-hydraulic properties. A one-pass core consisting of these assemblies is examined. Full-core calculations are computationally very expensive, thus a step-by-step homogenization process - complemented with extensive validation work - is applied using the code system SCALE6.0. This approach enabled a preliminary optimization of the one-pass core resulting in a favourable power distribution. This paper presents the outcome of the optimization of the assembly (fuel pin diameter 8.0 mm, pitch 10.12 mm, P/D 1.1), the developed fast computational method and the preliminary results of the full-core calculations (average fuel enrichment around 6.0%, radial power peaking below 1.3, maximum coolant temperature below 800 K and maximum cladding temperature below 850 K). © 2010 Elsevier Ltd. All rights reserved.},
	year = {2010},
	eissn = {1878-4224},
	pages = {767-776},
	orcid-numbers = {Szieberth, Máté/0000-0001-9192-0352}
}

@article{MTMT:2664023,
	title = {The Simplified Supercritical Water-Cooled Reactor (SSCWR), a new SCWR design},
	url = {https://m2.mtmt.hu/api/publication/2664023},
	author = {Reiss, Tibor and Csom, Gyula and Fehér, Sándor and Czifrus, Szabolcs},
	doi = {10.1016/j.pnucene.2009.06.006},
	journal-iso = {PROG NUCL ENERG},
	journal = {PROGRESS IN NUCLEAR ENERGY},
	volume = {52},
	unique-id = {2664023},
	issn = {0149-1970},
	year = {2010},
	eissn = {1878-4224},
	pages = {177-189}
}