Wonder 2026: 7th edition of the International Workshop On Nuclear Data Evaluation for Reactor Applications

Session

Processing and Benchmarking

Jul 3, 2026, 9:00 AM

Conveners

Processing and Benchmarking

• Oscar Cabellos (Universidad Politécnica de Madrid)

Processing and Benchmarking

• Cédric Jouanne (CEA Saclay)

71. Impact of JEFF-4.0 on full core calculations

Simon Ravaux (Framatome)

7/3/26, 9:00 AM

43. JEFF-4.0 gamma-production evaluations and validation of gamma-heating in Zero Power Reactor

David Bernard (CEA/DES/IRESNE/DER/SPRC/LEPh)

7/3/26, 9:25 AM

54. Development of D1S Calculation System

Young-Sik Cho (Korea Atomic Energy Research Institute)

7/3/26, 9:45 AM

37. Further improvements to the nuclear data processing code GALILÉE-1

Cédric Jouanne (CEA Saclay)

7/3/26, 10:35 AM

The GALILÉE-1 code developed at CEA Saclay has now reached a level of maturity that enables it to produce application libraries for the Monte Carlo transport code TRIPOLI-4. The two recent libraries JEFF-4 and ENDF/B-VIII.1 are now fully processed by GALILÉE-1, whereas previously it was necessary to use NJOY and CALENDF.
New representations of thermal scattering laws (TSL), including the...

39. Assessment of evaluated nuclear data consistency using integral damage and heating cross sections

Shengli Chen (Sun Yat-sen University)

7/3/26, 10:55 AM

Verification and validation is a key step in ensuring the quality of nuclear data. However, unexpected inconsistencies are sometimes found in evaluated nuclear data files due to errors during data or file preparation, inadequate assignment of key parameters, and unverified model calculations. While some issues can be identified and corrected prior to official release by means of format checks...

46. Impact of Nuclear Data Processing Parameters on Cross Sections and Criticality Safety Benchmarks

Vaibhav Jaiswal (ASNR)

7/3/26, 11:15 AM

This work assesses the impact of nuclear data processing parameters on processed cross sections and criticality safety benchmark results obtained using the nuclear data processing code NJOY. The study focuses on the RECONR and BROADR modules, which govern resonance reconstruction and Doppler broadening, respectively. The main parameters of these modules, including reconstruction tolerance,...

56. Porting Open-Source Multiple-Temperature Nuclear Data Libraries for Reactor Physics Applications with MCNP, Serpent, and OpenMC

Danila Roubtsov (Canadian Nuclear Laboratires, Chalk River, ON, Canada)

7/3/26, 11:35 AM

Code to code comparison is a widely used approach for verification, validation, and benchmarking in nuclear reactor physics analyses. Such exercises typically require that the participating code to employ a common or a common-source nuclear data library in order to ensure consistency and isolate code specific effects. Furthermore, high fidelity Monte Carlo neutron transport simulations and...

13. Impact of Thermal Scattering Law Uncertainty on Benchmarks Sensitive to Polyethylene

Aitor Bengoechea Fernández (ASNR)

7/3/26, 11:55 AM