USE OF FISSION PRODUCT EXPERIMENTS FOR BURNUP CREDIT ... · U5+U8+H+O Cs-133 Sm-149 Sm-152 Gd-155 Rh-103 Nd Bias & Uncertainty, % BUC Workshop October 28, 2009 Cordoba, Spain Page

Tatiana IVANOVA, Nicolas LECLAIRE, Eric LETANG (IRSN)

Jean-François THRO (AREVA NC)

USE OF FISSION PRODUCT EXPERIMENTS FOR BURNUP

CREDIT VALIDATION

International Workshop on Advances in Applications of Burnup Credit for Spent Fuel Storage, Transport, Reprocessing, and Disposition

October 28, 2009 Cordoba, Spain

BUC Workshop October 28, 2009 Cordoba, Spain Page 2

Outline

• French Fission Product (FP) Experimental Program

• Modification to the adjustment technique to establish bias and bias uncertainty due to FPs

• FP credit validation for application systems of the present and future fuel cycle

• Summary


French FP Experimental Program

Wat

er R

efle

ctor

Driver array - UO2 rods in water

Central tank –water with or without FP

Wat

er R

efle

ctor


Central tank –water with or without FP

Wat

er R

efle

ctor


Central tank – UO2 or HTC rods in water or DUN with or without FP

Wat

er R

efle

ctor


Central tank – UO2 or HTC rods in water or DUN with or without FP

Wat

er R

efle

ctor

UO2 rods in DUN solution without FP or

HTC rods in DUN solution with or without FP

Wat

er R

efle

ctor

UO2 rods in DUN solution without FP or

HTC rods in DUN solution with or without FP

Series of 145 critical experiments referred to as the FP Experimental Program was performed in the Valduc facility (CEA, France) in 1998-2004 [Ref.] with Cs-133, Sm-149, Sm-152, Gd-155, Ph-103, and Nd-143 in solutions

[Ref.] N. Leclaire et al., “Fission Products Experimental Programme: Validation and Computational Analysis”, Nucl. Sci. Eng., 161, 2, pp. 188-215 (2009)

a) “Physical” b) “Elementary Dissolution” c) “Global Dissolution”


Sensitivity Comparison: an Example

-0.2

0.0

0.2

0.4

0.6

0.8

1.0

sm-1

49ca

ptur

e

u-23

8 fi

ssio

n

pu-2

39 f

issi

on

u-23

8 sc

atte

r

u-23

8 nu

bar

o-16

ela

stic

pu-2

39 n

ubar

h-1

capt

ure

u-23

5 ca

ptur

e

u-23

8 ca

ptur

e

u-23

5 fi

ssio

n

h-1

elas

tic

u-23

5 nu

bar

Isotope-Reaction

Inte

grat

ed S

ensi

tivi

tyPF002 Case 13

PF003 Case 59

PF005 Case 3

keff sensitivity* to FP are significantly smaller than sensitivities for major actinides and moderator materials

*Sensitivity coefficients calculated by TSUNAMI-3D code/ 44-group ENDF/B-V based library


Analysis of the FP Experiments: an Example (1/3)

Some Physical Type Configurations

Exp. No. FP C(FP) g/l r (g/cm3) H+ (N) ArrayNumber of

rods

Number of rods

removed °C Hc (mm)2834 2 103Rh 40 1.0916 0.97 25x25-25 600 0 19.9 6002835 3 103Rh 20 1.0454 0.49 25x25-25 600 0 20.3 5302811 8 133Cs 130 1.1383 0.014 25x25-25 600 0 20 5402809 11 133Cs 80 1.0809 0.014 25x25-25 600 0 20 5202812 13 133Cs 80 1.1483 2.04 25x25-25 600 0 19.5 5212817 14 133Cs 78 1.1463 2 25x25-25 600 0 19 5212821 16 Ndnat 120 1.2224 0.023 25x25-25 600 0 19 5402823 18 152Sm 50 1.088 0.011 25x25-25 600 0 19 7002844 28 Mixt. 1.0989 0.21 25x25-25 600 0 20 6002803 35 Water 0.9986 0.014 25x25-25 600 0 19.4 4602813 37 Water 0.9986 0.014 25x25-25 600 0 19.4 460


Some keff sensitivity profiles for configuration #2809 with 133Cs



Some keff difference sensitivity for configurations with (#2809) and without (#2803) 133Cs



Basic Equations for the “Adjustment” Method

S2=PtW-1P+(∆k-HP)tU-1(∆k-HP)

W – ND covariancesU – Experimental uncertainty correlation H – keff Sensitivities for experimentsD - keff Sensitivities for application systemsP – vector of corrections to cross sections∆K= kc-ke

ΔkUHH)UH(WP 1t11t1 −−−− +=11t1 H)UH(WW' −−− +=

Bias Uncertainty for Application System = DW’Dt

Bias for Application System = DP


Modification to the “Adjustment” Method

Standard Approach Modified Approach

W

W’

.

.

.

W1

W2 ; W1’

W1’

W2’; W1’

W: covariance data for

U-235, U-238, H, O, FPs

W1: covariance data for U-235, U-238, H, OW2 : covariance data for FP-1, W3: covariance data for FP-2…

W3 ; W1’ W3’; W1’

W7 ; W1’ W7’; W1’


Some ND Covariance Before/After the “Adjustment”

Before

After

U-238 Capture Nd-143 Capture Rh-103 Capture44-group ND covariance data for Cs-133, Sm-149, Sm-152, Gd-155, Ph-103, Nd-143 from ENDF/B-V.rec (SCALE5.1)


keff Bias for the FP Configurations

0,993

0,994

0,995

0,996

0,997

0,998

0,999

1

1,001

1,002

1,003

1,004

1,005

1,006

1,007

Cs-

133(

1)

Cs-

133(

2)

Cs-

133(

3)

Cs-

133(

4)

Cs-

133(

5)

Cs-

133(

6)

Cs-

133(

7)

Cs-

133(

8)

Cs-

133(

9)

Cs-

133(

10)

Gd-

155(

1)

Gd-

155(

2)

Gd-

155(

3)

Gd-

155(

4)

Gd-

155(

5)

Nd-

143(

1)

Nd-

143(

2)

Rh-

103(

2)

Rh-

103(

3)

Rh-

103(

4)

Rh-

103(

5)

Sm

-149

(1)

Sm

-149

(2)

Sm

-152

(1)

Sm

-152

(2)

Sm

-152

(3)

Sm

-152

(4)

FP Experiment

k eff

1) Original keff

2) (1) + Corrections from adjusted cross sections for major actinides

0,9930,9940,9950,9960,9970,9980,999

11,0011,0021,0031,0041,0051,0061,007

Cs-

133(

1)

Cs-

133(

2)

Cs-

133(

3)

Cs-

133(

4)

Cs-

133(

5)

Cs-

133(

6)

Cs-

133(

7)

Cs-

133(

8)

Cs-

133(

9)

Cs-

133(

10)

Gd-

155(

1)

Gd-

155(

2)

Gd-

155(

3)

Gd-

155(

4)

Gd-

155(

5)

Nd-

143(

1)

Nd-

143(

2)

Rh-

103(

2)

Rh-

103(

3)

Rh-

103(

4)

Rh-

103(

5)

Sm

-149

(1)

Sm

-149

(2)

Sm

-152

(1)

Sm

-152

(2)

Sm

-152

(3)

Sm

-152

(4)

FP Experiment

k eff

1) Original keff2) (1) + Corrections from adjusted cross sections for major actinides3) (2) + Corrections from adjusted cross sections for FP


Uncertainty Assessment for Typical Application SystemSimplified models of storage in accidental condition for UO2 fuel with initial enrichment of 5% burned to 40 GWd/MTU and 60 GWd/MTU

The composition of the spent fuel was calculated by CESAR4 code

Application Case- Spent (40 GWd/tU) Fuel Storage

-0.10

-0.05

0.00

0.05

0.10

0.15

0.20

0.25

0.30

0.35

U5+U8+H+O Cs-133 Sm-149 Sm-152 Gd-155 Rh-103 Nd

Bia

s &

Unc

erta

inty

, %

Application Case- Spent (60 GWd/tU) Fuel Storage

-0.10

-0.05

0.00

0.05

0.10

0.15

0.20

0.25

0.30

0.35

U5+U8+H+O Cs-133 Sm-149 Sm-152 Gd-155 Rh-103 Nd

Bia

s &

Unc

erta

inty

, %


Uncertainty Assessment for Future Application System

Simplified model of MOX fuel for GFR burned to ~120 GWd/MTU and flooded by water [Ref.]

-0.2

0.0

0.2

0.4

0.6

0.8

1.0

1.2

Cs-133 Sm-149 Sm-152 Gd-155 Rh-103 Nd-143

FP

Bia

s &

Unc

erta

inty

, %∆

k/k

The composition of the spent fuel was calculated by ORIGEN code

[Ref.] P. N. Alekseev et al., Nuclear facility with the gas cooled fast reactor BGR-1000 using coated particles and technologies of light water reactors, Proc. of International Congress on Advances in Nuclear Power Plants (ICAPP 2007) "The Nuclear Renaissance at Work", Volume 3, pp.1657-1663 (2008)


From Present to Future Fuel Cycle Applications

-0.10.00.10.20.30.40.50.60.70.80.91.01.1

Cs-133 Sm-149 Sm-152 Gd-155 Rh-103 Nd-143

FP

Bia

s &

Unc

erta

inty

, %∆

k/k

Spent Fuel of GFR Spent Fuel of LWR


Summary

The methodology is proposed and tested to establish bias and bias uncertainty for FPs;

FP validation study is performed for typical and innovative application systems;

For the present test application the FP biases are small, as expected, and comparable with the bias uncertainties;

The significant bias for Sm-149 is established for the innovative (FR) application system;

The presented results show that the proposed method is useful in design and safety studies for innovative systems;

The FP experiments provide valuable information to assess FP credit for configurations containing fuel of both the present LWR and the future FR.

Documents

USE OF FISSION PRODUCT EXPERIMENTS FOR BURNUP CREDIT ... · U5+U8+H+O Cs-133 Sm-149 Sm-152 Gd-155 Rh-103 Nd Bias & Uncertainty, % BUC Workshop October 28, 2009 Cordoba, Spain Page