Investor Presentaiton
NRA, Japan
Nuclear Regulation Authority
Analysis of Fukushima-Daiichi Accident:
SA Progression and Source Terms
Background:
■ JNES started the accident analysis
with MELCOR soon after the accident.
■ By using the source terms with
MELCOR, an environmental
consequence analysis was done in
JAEA.
■ S/NRA/R is participating in
OECD/NEA BSAF Project.
Recent Development:
■ Based on the MELCOR results,
CFD (Computational Fluid Dynamics)
calculation for inside the
containment is being done to
study the containment
failure mechanism and
location at Unit 1.
(K)
7.20e+02
7.00e+02
6.80e+02
6.60e+02
6.40e+02
6.20e+02
6.00e+02
Concentration of Cs 137
insol
1000円
1000-1000
100-1000
100-000
100-300
00-100
30-00
10 30
10
FUM
3000
89
M. Hirano, Presented at U.S.NRC RIC2014.
(m/s)
5.00e+00
4.75e+00
4.50e+00
4.25e+00
4.00e+00
3.750+00
3.50e+00
3.25e+00
3.00e+00
5.80e+02
2.75e+00
2.50e+00
5.60e+02
2.25e+00
5.40e+02
2.00e+00
1.75e+00
5.20e+02
1.50e+00
5.00e+02
1.25e+00
1.00e+00
4.80e+02
7.50e-01
5.00e-01
4.60e+02
2.50e-01
4.40e+02
4.20e+02
4.00e+02
3.80e+02
3.60e+02
3.40e+02
0.00e+00
13
Cs-137
Concentration
measured by
MEXT
(Nov. 5, 2011)
(Bq/m²)
3000k<
1000k-3000k
600k - 1000k
300k 600k
100k-300k
60k-100k
30k-60k
10k-30k
10k
were not obtained
Cylinder
Sphere
Steam leak from RPV to
CV is assumed to occur
5.4 hours after shutdown at gasket of SRV flange.View entire presentation