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

Córdoba, Spain, 27-30 October, 2009

Organized by the Nuclear Safety Council of Spain (CSN) in cooperation with the International Atomic Energy Agency (IAEA). Co-sponsored by ENUSA Industrias Avanzadas S.A. and Empresa Nacional de Residuos Radiactivos S.A. (ENRESA)

SESSION I: INTERNATIONAL AND NATIONAL REPORTS

Co-Chairs: J.-C. Neuber (AREVA), J. M. Conde (CSN)

1.1

“IAEA Activities on Spent Fuel Management”
Zvonko Lovasic(IAEA)

 

Slides

 

1.2

“Lessons Learned from International Investigations of Burnup Credit Criticality”
M. C. Brady-Raap (PNNL), J. Gulliford (NNL), L. Markova (NRI), H. Okuno (JAEA), G. O’Connor (UK DfT), P. H. Liem (NAIS)

Abstract

Slides

Paper

1.3

“Activities of the OECD/NEA Expert Group on Assay Data for Spent Nuclear Fuel”
Ian C. Gauld (ORNL), Y. Rugama (NEA)

Abstract

Slides

Paper

1.4

“Burnup Credit Development and Implementation in the Slovak Republic”
Juraj Vaclav (NRA SR)

Abstract

Slides

Paper

1.5

“Applying Burn-up Credit Technology for Spent Fuel Storage in China”
Guoshun You, Qingfu Zhu, Chuanwen Hu (CIAE)

Abstract

 

 

1.6

“National program for BUC application in India”
A. K. Pandey,(NPCIL)

 

Slides

 

1.7

“Research Activities of JAEA Considering the Future Needs of Japan in Burnup Credit Implementation”
H. Okuno, K. Tonoike, K. Suyama, K. Ohkubo, G. Uchiyama (JAEA)

Abstract

Slides

Paper

1.8

“Review of Technical Studies in the United States in Support of Burnup Credit Regulatory Guidance”
J. C. Wagner, C. V. Parks, D. E. Mueller, I. C. Gauld (ORNL)

Abstract

Slides

 

1.9

”Latest Studies Related to the Use of Burnup Credit in France”
L. Jutier, I. Ortíz de Echevarría and S. Evo (IRSN), E. Guillou and J. Jaunet (AREVA), A. Bonne (EDF)

Abstract

Slides

Paper

SESSION II: CALCULATION METHODS
II.A      Codes and methods
Co-Chairs: S. Evo (IRSN), John C. Wagner (ORNL)

 

Chair overview of the status and the main challenges in burnup credit depletion calculation

Abstract

 

 

2.1

“Enhancements to the Burnup Credit Criticality Safety Analysis Sequence in SCALE”
G. Radulescu, Ian C. Gauld (ORNL)

Abstract

Slides

Paper

2.2

“Assessment of the MCNP+ACAB Code System for Burnup Credit Analysis”
N. García-Herranz, O. Cabellos, J. Sanz (UPM)

Abstract

Slides

Paper

2.3

“Convergence issues in Best-estimate Monte Carlo Depletion Calculations”
Y. Richet, W. Haeck, B. Cochet and J. Miss (IRSN), O. Jacquet (Consultant)

Abstract

Slides

 

2.4

“Peak Reactivity Characterization and Isotopic Inventory Calculations for BWR Criticality Applications”
C. Casado, J. Sabater, J. F. Serrano (ENUSA)

Abstract

Slides

Paper


II.B      Nuclear and assay data
Co-Chairs: A. Santamarina (CEA), R. D. McKnight (ANL)

 

Chair overview of the main improvements in nuclear data with respect to burnup credit nuclides and on the availability of assay data

 

Slides

 

2.5

“Correction Factors Derived from French Experiments with the Recent JEFF3.1.1 Library for PWR-UOx BUC Applications”
C. Riffard, A. Santamarina, and L. San Felice (CEA), J.-F. Thro (AREVA NC)

Abstract

Slides

 

2.6

“Study of Burnup Reactivity and Isotopic Inventory in REBUS Program”
T. Yamamoto and Y. Ando (JAEA), K. Sakurada and Y. Hayashi (Toshiba)

Abstract

Slides

Paper

2.7

“PWR and BWR Fuel Assay Data Measurements”
C. Alejano and J.M. Conde (CSN), M. Quecedo and M. Lloret (ENUSA), P. Zuloaga and F. J. Fernández (ENRESA), J. A. Gago
(ENDESA)

Abstract

Slides

Paper

II.C      Sensitivity/Uncertainty analyses
Co-Chairs: J.-C. Neuber (AREVA), T. Ivanova (IRSN)

 

Chair overview of the objectives, key concepts, and methods

 

Slides

 

2.8

“Sensitivity/uncertainty Analysis applied to the Phase VII Benchmark”
O. Cabellos, B. Cabellos and N. García-Herranz (UPM), J. Sanz (UNED), P. Ortego (SEA)

Abstract

Slides

Paper

2.9

“Use of French Fission Product Experiments for Burnup Credit Validation”
T. Ivanova, N. Leclaire, E. Létang (IRSN), J.-F. Thro (AREVA NC)

Abstract

Slides

 

2.10

“General hierarchical Bayesian procedure for calculating  the bias and the a posteriori uncertainty of neutron multiplication factors”
J.-C. Neuber, A. Hoefer (AREVA)

Abstract

Slides

Paper

2.11

“Usage of TSUNAMI in a Hierarchical Bayesian Procedure for Calculating the Bias and the a posteriori Uncertainty of keff”
J.-C. Neuber, A. Hoefer (AREVA)

Abstract

Slides

Paper

Note: Papers 2.10 and 2.11 were merged into one. The slides and paper files are the same for both.

II.D      Verification and validation
Co-Chairs: M. Brady-Raap (PNNL), Ian C. Gauld (ORNL)

 

Chair overview of the available data and methods

 

 

 

2.12

“Determination of a Depletion Uncertainty from Fuel Management Experience”
D. B. Lancaster (NuclearConsultants.com), C. T. Rombough (CTR)

Abstract

Slides

Paper

2.13

“Sufficiency of Available MOX Experiments for Criticality calculation validation of VVER Burnup Credit Application”
G. Hordosy (KFKI), S. Patai Szabo (ANANDOR)

Abstract

Slides

Paper

2.14

“Evaluation of Fission Product Critical Experiments and Associated Biases for Burnup Credit Validation”
D. E. Mueller, B. T. Rearden, D. A. Reed (ORNL)

 

 

 

2.15

“Regulatory Perspective on Computer Code Validation for Burnup Credit Criticality Analyses for Spent Nuclear Fuel Transportation
Packages”
M. Rahimi, Z. Li, M. Call (USNRC)

 

 

 

2.16

“SCALE Validation Experience using an Expanded Isotopic Assay Database for Spent Nuclear Fuel”
I. C. Gauld, G. Radulescu, G. Ilas (ORNL)

 

 

 

SESSION III: APPLICATIONS AND IMPLEMENTATION
Co-Chairs: J. Gulliford (NNL), A. Barto (USNRC)

 

Chair overview of reactor operations impacting the spent fuel reactivity and the burnup distribution

Text

 

 

3.1

“Regulatory  Perspective on  Confirmatory Burnup  Measurements for  Burnup  Credit  in  Spent  Nuclear  Fuel  Transportation
Packages”
A. Barto, N. Jordan (USNRC)

Abstract

Slides

Paper

3.2

“Fuel Burnup Plant Records: Generation and Accuracy”
M. Aissa (USNRC)

Abstract

Slides

Paper

3.3

“Recommended Bounding Axial Burnup  Profiles  In  BUC Applications  From Actual  Burnup  Measurement Of French PWR Assemblies”
C. Riffard and A. Santamarina (CEA), J.-F. Thro (AREVA-NC), F. Lavaud (EdF)

Abstract

Slides

Paper

3.4

“Inventory Prediction and BUC Calculations Related to MEU/LEU IRT Fuels of LVR-15 Research”
L. Markova, F. Havluj, M. Marek (NRI)

Abstract

Slides

Paper

3.5

“Fuel Depletion Calculation in MTR-LEU NUR Reactor”
Z. Fodil (COMENA)

Abstract

 

 

3.6

“Burnup Credit in the Swedish Interim Storage Facility (CLAB)”
L. Agrenius (Agrenius Ingenjörsbyra AB)

Abstract

Slides

 

3.7

“Lessons Learnt from OECD/NEA Phase II-C through Phase II-E Benchmarks”
J.-C. Neuber (AREVA)

Abstract

Slides

Paper

3.8

“Review of results for the OECD/NEA Phase VII Benchmark: Study of the Spent Fuel Compositions for Long Term disposal”
G. Radulescu, J. Wagner (ORNL)

Abstract

Slides

 

3.9

“Burnup Credit Approach for the Proposed United States Repository at Yucca Mountain”
J. M. Scaglione, J. C. Wagner (ORNL)

Abstract

Slides

Paper

3.10

“Regulatory Issues for Final Disposal”
J.-C. Neuber (AREVA)

Abstract

Slides

Paper

3.11

“Burnup Credit in the Canister for Final Disposal of Spent Nuclear Fuel”
L. Agrenius (Agrenius Ingenjörsbyra AB)

Abstract

Slides

 


Last reviewed: 19 August 2013