package „ncs 45“ for the transport of spent fuel rods · ¾leak tightness of ncs 45: 1e-5 pa...
TRANSCRIPT
Package
„NCS 45“
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 1
for the Transport of spent fuelrods
NRC meeting June 02, 2011
Content of the Presentation
Definition of the content
Package design of the NCS 45
Licensing status
Containment issues
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 2
Encapsulation
Shielding analysis
Criticality analysis
Way forward in the U.S.A
Definition of the content
Content 1: Irradiated Uranium fuel rods (R.0+1)
6 different contents
1 content max. 3.4 wt% enrichment
3 contents max. 5.3 wt.% enrichment
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 3
2 contents max. 7.0 wt. % enrichment
burn-up up to 120 GWd/tHM
cooling times down to 120 days
fissile material max. 6.5 kg U-235 (3.4%),
4.0 kg U-235 (5.3%), 5.25 (7%, steel tubes)
Definition of the content
Content 2: Irradiated MOX fuel rods (Rev. 2)
1 content
max. 100 wt.% Pu-tot
max. 94.0 wt. %Pu-fiss
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 4
max. 94.0 wt. % enrichment
burn-up up to 120 GWd/tHM
cooling times down to 120 days
fissile material max. 8.25 kg (Pu-fiss + U-235) (restricted diameter 120 mm)
Definition of the content
Content 5: Fissile excepted material (Rev. 0+1)
structural material
fissile material max. 15 g
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 5
Package Design „NCS 45“
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 6
Package Design „NCS 45“
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 7
D/4347/B(U)F-96 Rev .0
issued December 04, 2008
US DOT-Validation USA/0762/B(U)F-96
issued January 22 2010
Licensing status
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 8
issued January 22, 2010
D/4347/B(U)F-96 Rev .1 (Otto Hahn content)
issued March 25, 2010
Rev. 0 expires March 26, 2011
D/4347/B(U)F-96 Rev .2 expected July 2011
Containment analysis
Leak tightness of NCS 45: 1E-5 Pa m**3/s
Analysis according to ISO 12807
Two approaches used
NUREG-6487
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 9
subatmospheric pressure in cavity (SPC)
Burn-up steps: 33, 62, 120 GWd/MgHM
Cooling time steps: 120, 730, 3650 days
Definition of HM masses
to fulfill NCT containment criteria 1E-6A2/h
Containment analysis
Results:
Safety factors NCT
NUREG-6487: 1.0
SPC: > 1.9
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 10
Safety factors ACT
NUREG-6487: > 58
SPC: > 23
Shielding analysis
Criteria according to TS-R-1
2000 µSv/h at the surface
100 µSv/h in 2 m distance from vehicle
Analysis with SCALE/SAS4
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 11
Approach to use formulas in the package approval
Dose rate (formula) ≤ limit (TS-R-1)
Shielding analysis
Dose rate (formula) = function of
gamma source intensity
neutron source intensity
gamma source spectrum
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 12
(neutron source spectrum is consid. const.)
conversion factors dose rate/source intensity
source length factors
dose points (surface, 2m distance)
Shielding analysis
Dose rate criteria:
DR(SF) = S(G) x w(G,SF) x f (H,G,SF) + S(N) x w(N SF) x f (H N SF) ≤ 2000μSv/h
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 13
+ S(N) x w(N,SF) x f (H,N,SF) ≤ 2000μSv/h
DR(2m) = S(G) x w(G,2m) x f (H,G,2m) + S(N) x w(N,2m) x f (H,N,2m) ≤ 100μSv/h
Shielding analysis
What needs a user to know?
gamma source intensity -> SCALE
neutron source intensity -> SCALE
gamma source spectrum -> SCALE
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 14
source length -> measurement/data
all other information is contained in the certificate
Criticality analysis
Criterion: keff + 3 σ ≤ 0.95 NCT + ACT
Analysis with SCALE/KENO VI
original analysis by NCS
amended due to questions from Sweden ( t t 1 4)
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 15
(content 1.4)
amended due to questions from France (all contents, IRSN)
amended due to questions from USA (all contents, NRC, Docket no. 71-3084)
volume approx. 250 pages
Criticality analysis
Separate analysis for each content
For single package
NCT + ACT
variation of water flooding
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 16
rearrangement of content if not restricted
variation of pin diameter
variation of debris size
inhomogeneous arrangements
baskets and cladding mostly neglected
Criticality analysis
For infinite array of packages
ACT – shock absorbers neglected
assumed remaining water after drying
assumed inleakage of water due to leakage t
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 17
rate
assumed leakage of water out of damaged pins
variation of distance/water between packages
drying out of thermal insulation
Criticality analysis
Results: criticality safety proofed for
16.4 g U-235, 5.3 wt.% enr.
dia. 18 cm, 5.3 wt. % enr.
1380 g U-235, 5.3 wt.% enr.
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 18
0.25 mm cladding, 3.4 wt.% enr.
steel tubes dia. 20x1.5 mm, 7.0 wt. % enr.
1250 g U-235, 7.0 wt.% enr.
dia. 12 cm, 94 wt. % Pu-fiss or U-235
Rev. 1 shall not be validated
Rev. 2 validation will be applied in July
Full DOT validation of all contents
How to proceed for a NRC license?
Way forward in the U.S.A
Franz Hilbert, NCS, „NCS 45“, NRC-meeting June 02,2011 Seite 19
How to proceed for a NRC license?