TY - BOOK
T1 - Severe accident assessment
T2 - Results of the reactor safety research project VAHTI
A2 - Sairanen, Risto
PY - 1997
Y1 - 1997
N2 - The report provides a summary of the publicly funded
nuclear reactor safety research project "Severe Accident
Management" (VAHTI). The project has been conducted at
the Technical Research Centre of Finland (VTT) during the
years 1994-96. The main objective of the project was to
assist the severe accident management programmes of the
Finnish nuclear power plants, but the project scope also
included thermal hydraulic development.
The project consisted of several subprojects. The thermal
hydraulic subprojects have validated models of the
Advanced Process Simulation Environment, APROS. APROS
thermal hydraulic description has been extended to plant
shutdown conditions. The project has also contributed
improvements in APROS containment modeling for severe
accident simulation and calculation of tests done with
the PACTEL thermal hydraulic facility. The RELAP5 code
has been used to support APROS development.
A computer code PASULA has been developed for analysis of
core melt-pressure vessel interactions. The code has been
applied to pressure vessel penetration analysis. The
results showed the importance of the nozzle construction
to the pressure vessel failure mode. A creep model and
possibility to simulate porous debris have been added
into the PASULA code.
Cooling of a degraded core and BWR recriticality aspects
have been studied as joint Nordic projects with a set of
severe accident codes. The core was estimated coolable if
maximum cladding temperature at the beginning of
reflooding was below 1800 K. Reflooding could not
terminate accident progression in the lower head after
dryout. Reflooding of a core partly free of control rods
gives a power peak of a high amplitude, but short
duration.
Aerosol experiments have been conducted with the AHMED
test vessel. The experiments were successful, achieving
homogeneous temperature and humidity. 17 aerosol test
were performed using NaOH, CsOH, CsI and Ag aerosol
species. The data have been used by developers of aerosol
models. A CSNI calculation exercise has been arranged
based on the AHMED tests.
AB - The report provides a summary of the publicly funded
nuclear reactor safety research project "Severe Accident
Management" (VAHTI). The project has been conducted at
the Technical Research Centre of Finland (VTT) during the
years 1994-96. The main objective of the project was to
assist the severe accident management programmes of the
Finnish nuclear power plants, but the project scope also
included thermal hydraulic development.
The project consisted of several subprojects. The thermal
hydraulic subprojects have validated models of the
Advanced Process Simulation Environment, APROS. APROS
thermal hydraulic description has been extended to plant
shutdown conditions. The project has also contributed
improvements in APROS containment modeling for severe
accident simulation and calculation of tests done with
the PACTEL thermal hydraulic facility. The RELAP5 code
has been used to support APROS development.
A computer code PASULA has been developed for analysis of
core melt-pressure vessel interactions. The code has been
applied to pressure vessel penetration analysis. The
results showed the importance of the nozzle construction
to the pressure vessel failure mode. A creep model and
possibility to simulate porous debris have been added
into the PASULA code.
Cooling of a degraded core and BWR recriticality aspects
have been studied as joint Nordic projects with a set of
severe accident codes. The core was estimated coolable if
maximum cladding temperature at the beginning of
reflooding was below 1800 K. Reflooding could not
terminate accident progression in the lower head after
dryout. Reflooding of a core partly free of control rods
gives a power peak of a high amplitude, but short
duration.
Aerosol experiments have been conducted with the AHMED
test vessel. The experiments were successful, achieving
homogeneous temperature and humidity. 17 aerosol test
were performed using NaOH, CsOH, CsI and Ag aerosol
species. The data have been used by developers of aerosol
models. A CSNI calculation exercise has been arranged
based on the AHMED tests.
KW - nuclear reactor accidents
KW - nuclear reactor safety
KW - nuclear reactors
KW - nuclear reactor cores
KW - accident prevention
KW - radiation hazards
M3 - Report
SN - 951-38-5160-5
T3 - VTT Tiedotteita - Meddelanden - Research Notes
BT - Severe accident assessment
PB - VTT Technical Research Centre of Finland
CY - Espoo
ER -