- Mission of the groups
- IAE-owned analysis code
- Recent major study results
- 1.Analysis on accident event progression behavior at Fukushima Daiichi NPS (entrusted by the Ministry of Economy, Trade and Industry (METI), FY2011 onward)
- 2.Analysis on pipe wall corrosion (subsidized by METI and entrusted by the Nuclear and Industrial Safety Agency, FY2005 to 2012)
- 3.Evaluation of solar light collecting systems (entrusted by the Ministry of the Environment, FY2010 to 2012)
- Implementation of safety analysis, research and study in response to needs
- Contact Person
Mission of the groups
Since the Fukushima nuclear accident, safety evaluations of nuclear power plants become more important than ever before. Safety Analysis Group & Fukushima Analysis Project Group are jointly carrying out safety evaluations of nuclear power plants through analysis work. These simulation capabilities of the group are also applied to the areas other than nuclear energy, for example, evaluation of solar light collecting systems, etc.
IAE-owned analysis code
The Institute of Applied Energy (IAE) owns the codes listed in the table below. In addition to analysis and evaluation work using these codes, IAE is developing new codes based on such technologies. The codes are built from mechanistic models that precisely describe physical phenomena. Also, the codes are able to simulate the physical phenomena of the obtained analysis results more in detail. In particular, the severe accident analysis code SAMPSON has been introduced in various benchmark analysis projects by the Organisation for Economic Co-operation and Development (OECD) and its analysis capability has been proved as one of the best analysis codes currently used in the world.
|Severe accident analysis code: SAMPSON||Analyze a series of severe accident events from normal operation of a light water reactor plant through events inside the reactor to events in containment vessel, by combining eleven independent modules.|
|Boiling transition analysis code: CAPE||Analyze a maximum output (critical power of BWR or DNB output of PWR) that realizes safe operation without excessively raising fuel assembly temperature.|
|Fluid-structure interaction analysis code: FLAVOR||Conduct a two dimensional analysis on flow-induced vibration of tube bundles under moving boundary conditions. Conduct a three dimensional analysis on pressure vibration at structure surface, if it is possible to neglect an effect of moving boundary conditions.|
|Fluid analysis code: PLASHY||Computational fluid dynamics code composed of three dimensional fluid analysis modules for single phase flow, two phase flow and mixed flow. Conduct an analysis on heat transfer and fluid behavior including transient changes.|
|Pipe wall thinning analysis code: DRAWTHREE||It is composed of three dimensional codes and one dimensional codes, that analyze phenomena such as pipe wall thinning or pin hall caused by corrosion or droplet collision in pipes where fluids run inside.|
Recent major study results
1.Analysis on accident event progression behavior at Fukushima Daiichi NPS (entrusted by the Ministry of Economy, Trade and Industry (METI), FY2011 onward)
Analysis and evaluation of the accident event progression behavior at Fukushima Daiichi NPS are underway as a national project. As an example, the analysis results of the accident progression at Unit 1 by SAMPSON code are shown in Fig. 1. Pressure reduction in the reactor core was caused by the vapor blowing from the core to the containment vessel, through ruptured in-core instrumentation tube. Water injection by fire engines into the reactor began about eight hours after the damage of bottom of the reactor vessel due to core meltdown. These facts can be learned from the analyses.
2.Analysis on pipe wall corrosion (subsidized by METI and entrusted by the Nuclear and Industrial Safety Agency, FY2005 to 2012)
In August 2004, the secondary system piping of Unit 3 of Mihama Power Station ruptured during normal operation, leading to an accident of five workers’ demise. The cause was pipe wall thinning due to corrosion. In the wake of this accident, the group has developed an analysis code for pipe wall corrosion. Fig. 2 shows a comparison between the analysis and the actually measured values on pipe wall thinning phenomenon due to corrosion. Relation between the flow accelerated corrosion (FAC) and the quality of cooling water were identified.
3.Evaluation of solar light collecting systems (entrusted by the Ministry of the Environment, FY2010 to 2012)
The group has also developed an analysis code for simulation of tracking light beams in the solar light collecting systems. Fig. 3 shows a simulation that light beams are reflected from many mirrors installed on the ground to the top of tower.
Implementation of safety analysis, research and study in response to needs
In addition to the above, the group has conducted surveys on the trends of water quality management in nuclear power plants, worldwide. In the areas other than nuclear energy, under request from private companies, the group has implemented thermohydraulic analysis of water-vapor two-phase flow and surveys on the trends of two-phase flow analysis technique and others, etc.
|Kenichi Tezuka, Director|