Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Seino, Takeshi*; Yamate, Kazuki*; Tamaki, Hitoshi
Proceedings of IAEA Topical Meeting on Advanced Safety Assessment Methods for Nuclear Reactors (CD-ROM), 5 Pages, 2007/10
For a nuclear reactor plant, a risk informed approach provides a formal structured procedure for defining the functional logic complex systems, assessing the public consequences of failure and deriving numerical estimates of risk from the operation. For fuel material handling process, this kind of techniques could be applied as useful complementary tools to support safety decision-making. This paper describes the basic concept on the practical application of risk information for safety maintenance management featured by graded significance of Items Relied On For Safety (IROFS) based on defining operation limits and conditions (OLCs) in simpler and less hazardous nuclear fuel material handling process, systems and facilities. The trial application the concept was carried out for a fuel storage rack system and sintering furnace system as examples.
Koshizuka, Seiichi*; Liu, J.*; Morita, Koji*; Arima, Tatsumi*; Zhang, S.*; Tobita, Yoshiharu; Yamano, Hidemasa; Ito, Takahiro*; Naito, Masanori*; Shirakawa, Noriyuki*; et al.
Proceedings of IAEA Topical Meeting on Advanced Safety Assessment Methods for Nuclear Reactors (CD-ROM), 9 Pages, 2007/10
A computer code, named COMPASS (Computer Code with Moving Particle Semi-implicit for Reactor Safety Analysis), is being developed for various complex phenomena of core disruptive accidents (CDAs) in sodium-cooled fast reactors (SFRs). Theoretical studies are performed about a unified algorithm for compressible and incompressible flows, fluid flow with solid debris, and algorithm improvement for free surface flows. Code verification and validation procedures are established by exploiting the past experiences in those of SIMMER-III code. COMPASS will be used for separated phenomena in CDAs, while the whole core will be analyzed by SIMMER-III. COMPASS is expected to clarify the detailed process in duct wall failure and fuel discharge to avoid re-criticality during CDAs in large size SFRs.