1. Current Status of Nuclear Data Processing Activities at KAERI Do Heon KIM Korea Atomic Energy Research Institute Consultants’ Meeting on “The New Evaluated Nuclear Data File Processing Capabilities” October 5-9, 2015 IAEA Headquarters, Vienna, Austria

2. - 2 - Introduction Introduction ACE-Format Library ACE-Format Library MATXS-Format Library MATXS-Format Library Covariance Data Library Covariance Data Library PWR Core Analysis Code Library PWR Core Analysis Code Library Nuclear Decay and FP Yield Library Nuclear Decay and FP Yield Library Summary Summary CONTENTS

3. - 3 - Introduction u Roles of NDC, KAERI F Generate several kinds of XS libraries for radiation transport/depletion codes such as MCNP/MCNPX, DANTSYS, DOORS, WIMS-D, and ORIGEN F Disseminate them to many researchers in domestic and foreign institutions F Fulfil nuclear data needs for R&D activities on advanced reactors F Verify and validate our new evaluated data u Nuclear Data Processing F No complete ND processing code package F NJOY99, NJOY2012, ERRORJ, AMPX, PREPRO F Auxiliary tools to ease NJOY processing and generate unique XS libraries for our own transport/depletion codes

4. - 4 - u KAERI/NDC (KN)-Series of ACE Libraries F MCNP/MCNPX, McCARD F NJOY99/NJOY2012 F As release of new source evaluated files F Application to various reactor developments (KALIMER, SMART, VHTR, Research Reactors, etc.) F http://atom.kaeri.re.kr ACE-Format Library KN LibrarySource DataTemperatureNote MCLIB-E6ENDF/B-VI.5300K, 600K, 900KNEA-1651 KNE62, KNE68, KNE70, KNE71 ENDF/B-VI.2, VI.8, VII.0, VII.1293.6K KNF30, KNF31, KNF311, KNF312, KNF32 JEFF-3.0, 3.1, 3.1.1, 3.1.2, 3.2293.6K KNJ33, KNJ40, KNJAC08JENDL-3.3, 4.0, JENDL/AC-2008293.6K

5. - 5 - u Multi-Temperature ACE Libraries F Reaction XS and thermal scattering libraries at certain temperatures, upon request F Analysis of reactivity coefficients for VHTR, Research Reactors, etc. F Cold neutron analysis for Hanaro research reactor u On-The-Fly Doppler Broadening (DB) F Traditional XS treatments for precise temperature analyses require a lot of ACE libraries at different temperatures. F Huge memory size requirement F Leal-Hwang DB and SIGMA1 Kernel Broadening methods have been implemented in McCARD and tested with initial XS libraries at 0K and 300K.

6. - 6 - u Auxiliary Tools F To ease NJOY input generation and running F Simple Linux script file, ANJOYMC, NIM

7. - 7 - u Shielding Libraries F DANTSYS, DOORS F NJOY97/NJOY99 F Temperatures of 300, 600, 1000, and 2100K F Application to various reactor shielding calculations MATXS-Format Library LibrarySource DataEnergy GroupNote KASHIL-E6ENDF/B-VI.5Neutron 175G, Photon 42GNEA-1649 KASHIL-E68ENDF/B-VI.8Neutron 199G, Photon 42G KASHIL-E70ENDF/B-VII.0 Neutron 199G, Photon 42G Neutron 175G, Photon 42G Neutron 80G, Photon 24G Neutron 47G, Photon 20G Neutron 44G, Photon 18G Neutron 30G, Photon 12G NEA-1818 KASHIL-F31JEFF-3.1.1Neutron 199G, Photon 42G KASHIL-J33JENDL-3.3Neutron 199G, Photon 42G

8. - 8 - u Fast Reactor Libraries F DANTSYS F NJOY94/NJOY99 F Weighting function of KALIMER-150 core flux F Temperatures of 300, 600, 900, and 1200K F Application to various fast reactor analyses (KALIMER) LibrarySource DataEnergy GroupNote KAFAX-F22JEF-2.2Neutron 80G, Photon 24GNEA-1650 KAFAX-E66ENDF/B-VI.6Neutron 150G, Photon 12G KAFAX-E70ENDF/B-VII.0Neutron 150G, Photon 12GNEA-1815 KAFAX-E71ENDF/B-VII.1Neutron 150G, Photon 12G KAFAX-F31JEFF-3.1Neutron 150G, Photon 12GNEA-1816 KAFAX-J33JENDL-3.3Neutron 150G, Photon 12GNEA-1817 KAFAX-JAC08JENDL/AC-2008Neutron 150G, Photon 12G

9. - 9 - u ISOTXS-Format microscopic XS Libraries F MUST (Multi-group Unstructured geometry S N Transport) Code F TRANSX post-processing of KASHIL libraries F Temperatures of 300, 600, 1000, and 2100K u Supplementation of KAFAX F Ultrafine energy group XS treatment to correct resonance overlap effect F Self-shielded XS treatment in URR

10. - 10 - u COVFIL-Format Covariance Libraries F DANTSYS/SUSD3D, McCARD, TSUNAMI F NJOY99, ERRORJ, PUFF-IV F Estimation of ND uncertainties to k-eff Covariance Data Library LibrarySource DataEnergy GroupNote GCovar-J33rRevision of JENDL-3.3Neutron 44G, Neutron 30G GCovar-J40 GCovar-J40u JENDL-4.0 JENDL-4.0 Update Neutron 44G, Neutron 33G Neutron 44G GCovar-E71ENDF/B-VII.1Neutron 44G

11. - 11 - u Multi-Group Libraries for PWR Core Analysis (KAERI) F Whole core analysis transport code, DeCART F Transport lattice transport codes, LIBERTE & KARMA F Application to PWR and SMART reactor developments PWR Core Analysis Code Library

12. - 12 - u Multi-Group Libraries for PWR Core Analysis (SNU) F Whole core analysis transport code, nTRACER F Application to PWR and SMART reactor developments

13. - 13 - u Nuclear Decay & Fission-Product Yield Libraries for SCALE-6.1.3 F Burnup/Depletion Module ORIGEN-S F In-house processing tool F Application to decay heat estimation after a fission event Nuclear Decay and FP Yield Library FP Yield LibrarySource DataNo. of FissionableNote YLD-E70ENDF/B-VII.030 YLD-E71ENDF/B-VII.130 YLD-J40JENDL-4.030 YLD-JFPY2011JENDL/FPY-201130 YLD-F311JEFF-3.1.119 YLD-K00KAERI3U-235, U-238, Pu-239 Decay LibrarySource DataNo. of FPsNote Dec-E71ENDF/B-VII.12238 Dec-K00KAERI24Mass chains 72 & 144

14. - 14 - Summary u Nuclear Data Processing Activities at KAERI F ACE-format library F MATXS-format library F Covariance data library F PWR core analysis code library F Nuclear decay and FP yield library u Suggestion F Inclusion of capability to deal with ultrafine energy groups in resonance range Enable to perform more accurate resonance treatment Useful for practical reactor core design/analysis applications