TY - CHAP
T1 - Reactor physics and dynamics (READY)
T2 - ARES - a new BWR simulator
AU - Mattila, Riku
PY - 2002
Y1 - 2002
N2 - Coupling the three-dimensional Analytic Function Expansion Nodal (AFEN)
nodal model [1, 2] developed within the READY project in 2000-2001 with a
four-equation based stationary-state thermalhydraulics module [3] and a new
cross section model [4], a basis has been created for a sophisticated BWR
simulator code. Motivation for distilling the efforts into a new simulator,
named ARES (AFEN Reactor Simulator), can be summarized in three main points:
· Stationary-state analyses required by the safety authorities must be
independent from the calculations made by the power utilities. Using a
different simulator for some calculations is an effective method for
obtaining independent results. · In order to keep up with the development in
the core analysis field, a "test bench" is required for testing and
evaluating new ideas and models. In addition, accuracy of the commercial
codes and the models incorporated in them can be evaluated by benchmarking
them against the new simulator. · Writing a new program from scratch is
potentially a good way to transfer experience from the first generation of
Finnish nuclear engineers. It also gives the opportunity to re-evaluate some
of the ideas used in the older codes written in times of significantly
smaller computer capacity.
AB - Coupling the three-dimensional Analytic Function Expansion Nodal (AFEN)
nodal model [1, 2] developed within the READY project in 2000-2001 with a
four-equation based stationary-state thermalhydraulics module [3] and a new
cross section model [4], a basis has been created for a sophisticated BWR
simulator code. Motivation for distilling the efforts into a new simulator,
named ARES (AFEN Reactor Simulator), can be summarized in three main points:
· Stationary-state analyses required by the safety authorities must be
independent from the calculations made by the power utilities. Using a
different simulator for some calculations is an effective method for
obtaining independent results. · In order to keep up with the development in
the core analysis field, a "test bench" is required for testing and
evaluating new ideas and models. In addition, accuracy of the commercial
codes and the models incorporated in them can be evaluated by benchmarking
them against the new simulator. · Writing a new program from scratch is
potentially a good way to transfer experience from the first generation of
Finnish nuclear engineers. It also gives the opportunity to re-evaluate some
of the ideas used in the older codes written in times of significantly
smaller computer capacity.
M3 - Chapter or book article
SN - 951-38-6085-X
T3 - VTT Tiedotteita - Research Notes
SP - 134
EP - 138
BT - FINNUS: The Finnish Research Programme on Nuclear Power Plant Safety 1999-2002
PB - VTT Technical Research Centre of Finland
CY - Espoo
ER -