TY  - JOUR
AU  - Csom, Gyula
AU  - Reiss, Tibor
AU  - Fehér, Sándor
AU  - Czifrus, Szabolcs
TI  - Thorium as an alternative fuel for SCWRs
JF  - ANNALS OF NUCLEAR ENERGY
J2  - ANN NUCL ENERGY
VL  - 41
PY  - 2012
IS  - 41
SP  - 67
EP  - 78
PG  - 12
SN  - 0306-4549
DO  - 10.1016/j.anucene.2011.11.007
UR  - https://m2.mtmt.hu/api/publication/2665956
ID  - 2665956
LA  - English
DB  - MTMT
ER  - 

TY  - JOUR
AU  - Reiss, Tibor
AU  - Csom, Gyula
AU  - Fehér, Sándor
AU  - Czifrus, Szabolcs
AU  - Szieberth, Máté
TI  - Full-core SSCWR calculations applying a fast computational method
JF  - PROGRESS IN NUCLEAR ENERGY
J2  - PROG NUCL ENERG
VL  - 52
PY  - 2010
IS  - 8
SP  - 767
EP  - 776
PG  - 10
SN  - 0149-1970
DO  - 10.1016/j.pnucene.2010.06.003
UR  - https://m2.mtmt.hu/api/publication/2664024
ID  - 2664024
AB  - 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.
LA  - English
DB  - MTMT
ER  - 

TY  - JOUR
AU  - Reiss, Tibor
AU  - Csom, Gyula
AU  - Fehér, Sándor
AU  - Czifrus, Szabolcs
TI  - The Simplified Supercritical Water-Cooled Reactor (SSCWR), a new SCWR design
JF  - PROGRESS IN NUCLEAR ENERGY
J2  - PROG NUCL ENERG
VL  - 52
PY  - 2010
IS  - 2
SP  - 177
EP  - 189
PG  - 13
SN  - 0149-1970
DO  - 10.1016/j.pnucene.2009.06.006
UR  - https://m2.mtmt.hu/api/publication/2664023
ID  - 2664023
LA  - English
DB  - MTMT
ER  -