TY - GEN
T1 - HEXTRAN - a 3-D reactor dynamics code for VVER accident analyses
AU - Kyrki-Rajamäki, Riitta
PY - 1994
Y1 - 1994
N2 - The reactor dynamics calculation system of VTT Energy consists of models for both reactor types in Finland - the ABB Atom type BWRs in Olkiluoto and the VVER type PWRs in Loviisa. HEXTRAN is a three-dimensional hexagonal transient and accident analysis code developed in VTT for VVERs. Now it is possible to make fully realistic accident analyses starting from accurate core conditions. The thermal hydraulics model SMABRE is dynamically coupled with HEXTRAN for the primary and secondary circuit calculations. HEXTRAN coupled with SMABRE has been extensively applied to safety analyses of the Loviisa power station, of the new Russian VVER-91 concept, and of the Hungarian VVER-440 type NPP Paks. Main applications are the calculations of asymmetric accidents in the reactor core originating from neutronic or thermal hydraulic disturbances in core or cooling circuits. The main properties of HEXTRAN, its applications and plans for the development of its hydraulics model are presented in the paper.
AB - The reactor dynamics calculation system of VTT Energy consists of models for both reactor types in Finland - the ABB Atom type BWRs in Olkiluoto and the VVER type PWRs in Loviisa. HEXTRAN is a three-dimensional hexagonal transient and accident analysis code developed in VTT for VVERs. Now it is possible to make fully realistic accident analyses starting from accurate core conditions. The thermal hydraulics model SMABRE is dynamically coupled with HEXTRAN for the primary and secondary circuit calculations. HEXTRAN coupled with SMABRE has been extensively applied to safety analyses of the Loviisa power station, of the new Russian VVER-91 concept, and of the Hungarian VVER-440 type NPP Paks. Main applications are the calculations of asymmetric accidents in the reactor core originating from neutronic or thermal hydraulic disturbances in core or cooling circuits. The main properties of HEXTRAN, its applications and plans for the development of its hydraulics model are presented in the paper.
M3 - Conference article in proceedings
SN - 951-763-880-9
T3 - Lappeenrannan teknillinen korkeakoulu. Tieteellisiä julkaisuja
SP - 243
EP - 250
BT - French-Finnish colloquium on safety of French and Russian type nuclear power plants
PB - Lappeenranta University of Technology
CY - Lappeenranta
T2 - French-Finnish Colloquim on Safety of French and Russian Type Nuclear Power Plants
Y2 - 14 June 1994 through 16 June 1994
ER -