Current Status of Nuclear Data Processing Activities at

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

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

Introduction u Roles of NDC, KAERI F F u Generate several kinds of XS libraries for radiation transport/depletion codes such as MCNP/MCNPX, DANTSYS, DOORS, WIMS-D, and ORIGEN Disseminate them to many researchers in domestic and foreign institutions Fulfil nuclear data needs for R&D activities on advanced reactors Verify and validate our new evaluated data Nuclear Data Processing F F F No complete ND processing code package NJOY 99, NJOY 2012, ERRORJ, AMPX, PREPRO Auxiliary tools to ease NJOY processing and generate unique XS libraries for our own transport/depletion codes -3 -

ACE-Format Library u KAERI/NDC (KN)-Series of ACE Libraries F F F MCNP/MCNPX, Mc. CARD NJOY 99/NJOY 2012 As release of new source evaluated files Application to various reactor developments (KALIMER, SMART, VHTR, Research Reactors, etc. ) http: //atom. kaeri. re. kr KN Library Source Data Temperature Note NEA-1651 MCLIB-E 6 ENDF/B-VI. 5 300 K, 600 K, 900 K KNE 62, KNE 68, KNE 70, KNE 71 ENDF/B-VI. 2, VI. 8, VII. 0, VII. 1 293. 6 K KNF 30, KNF 311, KNF 312, KNF 32 JEFF-3. 0, 3. 1. 1, 3. 1. 2, 3. 2 293. 6 K KNJ 33, KNJ 40, KNJAC 08 JENDL-3. 3, 4. 0, JENDL/AC-2008 293. 6 K -4 -

u Multi-Temperature ACE Libraries F F F u Reaction XS and thermal scattering libraries at certain temperatures, upon request Analysis of reactivity coefficients for VHTR, Research Reactors, etc. Cold neutron analysis for Hanaro research reactor On-The-Fly Doppler Broadening (DB) F F F Traditional XS treatments for precise temperature analyses require a lot of ACE libraries at different temperatures. Huge memory size requirement Leal-Hwang DB and SIGMA 1 Kernel Broadening methods have been implemented in Mc. CARD and tested with initial XS libraries at 0 K and 300 K. -5 -

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

MATXS-Format Library u Shielding Libraries F F DANTSYS, DOORS NJOY 97/NJOY 99 Temperatures of 300, 600, 1000, and 2100 K Application to various reactor shielding calculations Library Source Data Energy Group KASHIL-E 6 ENDF/B-VI. 5 Neutron 175 G, Photon 42 G KASHIL-E 68 ENDF/B-VI. 8 Neutron 199 G, Photon 42 G KASHIL-E 70 ENDF/B-VII. 0 Neutron 199 G, Photon 42 G Neutron 175 G, Photon 42 G Neutron 80 G, Photon 24 G Neutron 47 G, Photon 20 G Neutron 44 G, Photon 18 G Neutron 30 G, Photon 12 G KASHIL-F 31 JEFF-3. 1. 1 Neutron 199 G, Photon 42 G KASHIL-J 33 JENDL-3. 3 Note NEA-1649 Neutron 199 G, Photon 42 G NEA-1818 -7 -

u Fast Reactor Libraries F F F DANTSYS NJOY 94/NJOY 99 Weighting function of KALIMER-150 core flux Temperatures of 300, 600, 900, and 1200 K Application to various fast reactor analyses (KALIMER) Library Source Data Energy Group Note KAFAX-F 22 JEF-2. 2 Neutron 80 G, Photon 24 G NEA-1650 KAFAX-E 66 ENDF/B-VI. 6 Neutron 150 G, Photon 12 G KAFAX-E 70 ENDF/B-VII. 0 Neutron 150 G, Photon 12 G KAFAX-E 71 ENDF/B-VII. 1 Neutron 150 G, Photon 12 G KAFAX-F 31 JEFF-3. 1 Neutron 150 G, Photon 12 G NEA-1816 KAFAX-J 33 JENDL-3. 3 Neutron 150 G, Photon 12 G NEA-1817 KAFAX-JAC 08 JENDL/AC-2008 Neutron 150 G, Photon 12 G NEA-1815 -8 -

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

Covariance Data Library u COVFIL-Format Covariance Libraries F F F DANTSYS/SUSD 3 D, Mc. CARD, TSUNAMI NJOY 99, ERRORJ, PUFF-IV Estimation of ND uncertainties to k-eff Library Source Data Energy Group GCovar-J 33 r Revision of JENDL-3. 3 Neutron 44 G, Neutron 30 G GCovar-J 40 u JENDL-4. 0 Update Neutron 44 G, Neutron 33 G Neutron 44 G GCovar-E 71 ENDF/B-VII. 1 Note Neutron 44 G - 10 -

PWR Core Analysis Code Library u Multi-Group Libraries for PWR Core Analysis (KAERI) F F F Whole core analysis transport code, De. CART Transport lattice transport codes, LIBERTE & KARMA Application to PWR and SMART reactor developments De. CART (2003) LIBERTE (2006) KARMA (2009) - 11 -

u Multi-Group Libraries for PWR Core Analysis (SNU) F F Whole core analysis transport code, n. TRACER Application to PWR and SMART reactor developments n. TRACER (2013) - 12 -

Nuclear Decay and FP Yield Library u Nuclear Decay & Fission-Product Yield Libraries for SCALE-6. 1. 3 F F F Burnup/Depletion Module ORIGEN-S In-house processing tool Application to decay heat estimation after a fission event Decay Library Source Data Dec-E 71 ENDF/B-VII. 1 Dec-K 00 KAERI FP Yield Library Source Data No. of FPs Note 2238 24 No. of Fissionable YLD-E 70 ENDF/B-VII. 1 30 YLD-J 40 JENDL-4. 0 30 YLD-JFPY 2011 JENDL/FPY-2011 30 YLD-F 311 JEFF-3. 1. 1 19 YLD-K 00 KAERI 3 Note 30 YLD-E 71 Mass chains 72 & 144 U-235, U-238, Pu-239 - 13 -

Summary u Nuclear Data Processing Activities at KAERI F F F u ACE-format library MATXS-format library Covariance data library PWR core analysis code library Nuclear decay and FP yield library 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 - 14 -