package „ncs 45“ for the transport of spent fuel rods · ¾leak tightness of ncs 45: 1e-5 pa...

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?