
35733c614957d7aa1da20f27991710d0.ppt
- Количество слайдов: 14
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 -