Page 451 - Fundamentals of Magnetic Thermonuclear Reactor Design

428 Fundamentals of Magnetic Thermonuclear Reactor Design

APPENDIX A.14.3 COMPUTER CODES USED IN ITER SAFETY
ANALYSIS

Code, version,
application Modification for Key fusion Code validation
field fusion applications status a
1 2 3 4
MELCOR 1.8.2 Range of water Analysis of in- Pressurisation in
Modelling parameters extended vessel/ ex-vessel air-filled volumes
of accident (to below the triple and in-cryostat and volume’s
progression point) Equations incidents and pressurisation
in light water of state for helium accidents as under vacuum:
reactors, and air and HTO well as LOCA, proven
transient thermal transport are added. LOVA and PCB experimentally.
hydraulics and Oxidation of the first events.
radionuclide wall materials by
transport. steam and radiation
heat transfer are
taken into account.
TRAC-PFI/mod1 Modified for the Analysis of The applicability
Thermal– analysis of LOCA deviations of the code has
hydraulics events involving from normal been compared
analysis for flooding. Models for operation and to results
boiling and radiation-induced events of the obtained with
pressurised heat transfer and LOCA, LP, and other codes and
water reactors chemical reactions PCB (‘dry’ and results of a LOCA
for W, C and Be ‘wet’ bypass) event analysis
with air and steam; type for a pressurised
special model for water reactor and
swirl tape effect experiments on
modelling. the ICE facility.
SAFALY Developed for ITER. Analysis of Plasma transient
Safety analyses Includes a 0-D processes behaviour has
of anomalous plasma dynamics related to loss of been compared
plasma model and 1-D heat plasma control to results
behaviour transfer model of in- and discharge predicted by the
including vessel components. termination, as UEDEG plasma
in-vessel well as ex-vessel code (1-D
components LOCA events. model).
heating
PACTITER Modified version Analysis of PACTITER results
Predicts of PACTOLE code events of the have been
formation, for the analysis of LOCA type. validated with
migration and corrosion product Assessment measurements
deposition formation and of corrosion made in PWRs
of activated behaviour. product and available
corrosion deposition on data in the
products in the cooling system literature, in
primary cooling pipes. the temperature
circuit. range around
300°C.