10. REFERENCES
- K. Abe et Al.
"Overview of Development and Application of THALES Code System for Analyzing Progression of Core Meltdown Accident of LWR's"
Proc 2nd Int. Topical Mtg. on Nuclear Power Plant Thermal
Hydraulics and Operations, Tokyo (1986).
- K. Abe et Al.
"Development of Computer Code System THALES for Thermal-Hydraulic
Analysis of Core Meltdown Accidents (1) Outlines of Code System
and Analytical Models",
J. of Japanese Nuclear Society, Vol.27, No.11 (1985).
- M. Nishi et Al.
"The User's Manual of THALES Code System for Analyzing Progression of Core Meltdown Accident (Draft for discussion)",
JAERI-memo 62-400 (1987).
- K. Abe et Al.
"Development of THALES-CV2 Code for Analyzing Containment
Temperature and Pressure Response during Core Meltdown Accident"
Int. ANS/ENS Topical Mtg. on Thermal Reactor Safety, San Diego
(1986).
- K. Abe et Al.
"Thermal Response Analyses of PBF Severe Fuel Damage Tests with
THALES-MX Code",
JAERI-memo 59-355 (1984).
- M. Ida et Al.
"Discussion of Reactor Pressure Vessel Meltthrough Timing in PWR
Core Melt Accidents",
JAERI-memo 61-311 (1986).
- K. Abe et Al.
"Sensitivity Study on PWR Source Terms with THALES/ART Code
Package and Effects of In-Vessel Thermal-Hydraulics Models",
Int. SNS/ENS/ANS Topical Mtg. on Probsbilistic Safety Assessment
(PSA'87), Zurich (1987).
NEA-0774/01, included references:
- K. Kobayashi et al.:
Digital Computer Subroutine STEAM for JSME Steam Table
JAERI-M 6967 (31 January 1977) (in Japanese)
- M. Nishi et al.:
The User's Manual of THALES Code System for Analyzing Progression
of Core Meltdown Accident.
JW 219, Draft (October 1987)
