2015-11-181 Status of Nuclear Data Processing Codes at CNDC China Nuclear Data Center(CNDC) China Institute of Atomic Energy(CIAE) P.O.Box 275-41,Beijing.

Slides:

Advertisements

Similar presentations

.NET Technology. Introduction Overview of.NET What.NET means for Developers, Users and Businesses Two.NET Research Projects:.NET Generics AsmL.

Advertisements

July 13th 2012 Leicester XSPEC, Fitting, and Atomic Data Keith Arnaud.

Programming Paradigms and languages

ITER Computational Shield Benchmark IAEA TM on Nuclear Data Library for Advanced Systems – Fusion Devices. Vienna, October 31 – November 2, 2007 U. Fischer,

EMERALD1: A Systematic Study of Cross Section Library Based Discrepancies in LWR Criticality Calculations Jaakko Leppänen Technical Research Centre of.

Total Monte Carlo and related applications of the TALYS code system Arjan Koning NRG Petten, the Netherlands Technical Meeting on Neutron Cross- Section.

1Managed by UT-Battelle for the U.S. Department of Energy Simulation of βn Emission From Fission Using Evaluated Nuclear Decay Data Ian Gauld Marco Pigni.

Boris Pritychenko Nuclear Physics Data Compilation for Nucleosynthesis Modeling, Trento, May 29 – June 1, 2007 MACS and Astrophysical Reaction Rates from.

Examination and Improvement of SHEM multigroup energy structure Tholakele P. Ngeleka Radiation and Reactor Theory, Necsa, RSA Ivanov Kostadin, Levine Samuel.

WORK ON CLUSTER HYBRILIT E. Aleksandrov 1, D. Belyakov 1, M. Matveev 1, M. Vala 1,2 1 Joint Institute for nuclear research, LIT, Russia 2 Institute for.

U N C L A S S I F I E D LA-UR Current Status of the NJOY Nuclear Data Processing Code System and Initial ENDF/B-VII Data Testing Results Presented.

Summary of Work Zhang Qiwei INFN - CIAE. Validation of Geant4 EM physics for gamma rays against the SANDIA, EPDL97 and NIST databases.

Beta F90 Version Status Nolan Anderson Date: July 26, 2011.

International Atomic Energy Agency Reference Input Parameter Library (RIPL)-Levels Marco Verpelli and Roberto Capote Noy IAEA - Nuclear Data Section NSDD.

Brookhaven Science Associates U.S. Department of Energy Covariance data: Status and Perspective at BNL D. Rochman, M. W. Herman, P. Obložinský National.

UKRNDC Activity on Nuclear Data Support to Meet the Requirements Connected with Fundamental Science and Applications Olena Gritzay, Oleksandr Kalchenko.

KENO Postprocessor Analysis and Plotting Capabilities 2002 ANS Winter Meeting Washington D.C. November , 2002 D. F. Hollenbach, L. M. Petrie, B.

JINRLIB program library Popkova L.B., Sapozhnikov A.P., Sapozhnikova T.F., Fedorova R.N. Joint Institute for Nuclear Research.

Programming With C.

Touchstone Automation’s DART ™ (Data Analysis and Reporting Tool)

Anti-neutrinos Spectra from Nuclear Reactors Alejandro Sonzogni National Nuclear Data Center.

China Nuclear Data Center (CNDC) Progress Report Zhuang Youxiang.

_______________________________________________________________CMAQ Libraries and Utilities ___________________________________________________Community.

Lawrence Livermore National Laboratory PREPRO Accomplishments Dermott “Red” Cullen Presented at the Nuclear Criticality Safety Program Technical Conference.

Forschungszentrum Karlsruhe in der Helmholz-Gemeinschaft Karlsruhe Institute of Technology Nuclear Data Library for Advanced Systems – Fusion Devices (FENDL-3)

ENDF/B-VI Coupled Photon-Electron Data for Use in Radiation Shielding Applications by Dermott E. Cullen Lawrence Livermore National Laboratory & Robert.

LLNL-PRES-?????? This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344.

                        University of Wisconsin – Madison Engine Research Center WAVE/Chemkin Interface May 2002 pg. 1 GTI.

RTF Update Kevin Smit Kelly Tarp ProCost Version 3.0 Modifications A registered professional engineering corporation with offices in the Seattle,

Radiation damage calculation in PHITS

Current Status of Nuclear Data Processing Activities at KAERI Do Heon KIM Korea Atomic Energy Research Institute Consultants’ Meeting on “The New Evaluated.

SAXS Scatter Performance Analysis CHRIS WILCOX 2/6/2008.

GRUCON Code Package: Status and Projects V.V.Sinitsa NRC “Kurchatov Institute” Moscow, Russia.

Current nuclear data processing status of JAEA JAEA Research Group for Reactor Physics and Standard Nuclear Code System Kenichi Tada 1.

CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority EAF-2010 – the best of a generation Jean-Christophe Sublet, Lee Packer Euratom/CCFE.

6-1 Lesson 6 Objectives Beginning Chapter 2: Energy Beginning Chapter 2: Energy Derivation of Multigroup Energy treatment Derivation of Multigroup Energy.

Luiz Leal, Wim Haeck, GAIA : Nuclear data processing for transport and criticality safety calculations at IRSN Luiz.

Benchmarks for Data Testing of Iron China Nuclear Data Center(CNDC) China Institute of Atomic Energy(CIAE) P.O.Box ,Beijing , P.R.China.

Interfacing the JQMD and JAM Nuclear Reaction Codes to Geant4 Stanford Linear Accelerator Center Koi, Tatsumi

Activities Nuclear Data Service Yolanda Rugama OECD/NEA.

Plans for Validation and General Observations Mohamed Sawan Fusion Technology Institute The University of Wisconsin-Madison 3 rd RCM on FENDL December.

V.Ivanchenko Salamanca1 Geant4: Hadronic Processes 1  Cross sections  Secondary generators  Nuclear interactions at rest  CHIPS model.

LLNL-PRES-XXXXXX This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344.

1 Transport and Activation files processing with NJOY-99 J-Ch. Sublet & C Jouanne 1 CEA Cadarache, DEN/DER/SPRC,13108 St Paul Lez Durance, France 1 CEA.

232 Th EVALUATION IN THE RESOLVED RESONANCE RANGE FROM 0 to 4 keV Nuclear Data Group Nuclear Science and Technology Division Oak Ridge National Laboratory.

CCFE is the fusion research arm of the United Kingdom Atomic Energy Authority Modern , d, p, n-Induced Activation Transmutation Systems EURATOM/CCFE.

Data Needs in Nuclear Astrophysics, Basel, June 23-25, 2006 Nuclear Astrophysics Resources of the National Nuclear Data Center B. Pritychenko*, M.W. Herman,

KIT – The cooperation of Forschungszentrum Karlsruhe GmbH and Universität Karlsruhe (TH) Institute for Neutron Physics and Reactor Technology Evaluation.

User’s Needs/Problems Fill out form by tomorrow for your data needs. Make website for regional climate modeling library (at least references). ICTP CD.

Pavel Oblozinsky NSDD’07, St. Petersburg June 11-15, 2007 ENDF/B-VII.0 Library and Use of ENSDF Pavel Oblozinsky National Nuclear Data Center Brookhaven.

Neutrons in gases Mary Tsagri CERN PH / SFT Tuesday, 23 February 2010 RD51 mini week.

IFMIF d-Li neutron source: Status of codes and nuclear data S.P. Simakov Institut für Reaktorsicherheit, Forschungszentrum Karlsruhe IEA Neutronics Meeting,

Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Association FZK-Euratom Review of IEAF-2001 Cross Section Data Libraries for IFMIF Activation.

KIT – The Research University in the Helmholtz Association INSTITUTE for NEUTRON PHYSICS and REACTOR TECHNOLOGY (INR) Nuclear Data for Calculation.

Automatic Generation of the Partial Wave Analysis Program For Physics Processes Jian-Xiong Wang Institute of High Energy Physics, Academia Sinica 1. Brief.

Neutron HP updates KOI, Tatsumi SLAC 9/19/20111Geant4 Collaboration Meeting.

Ciemat Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas D. Cano-Ott, 6 th Geant4 Space Users Workshop Evaluated neutron cross section.

E. Mendoza, D.Cano-Ott Nuclear Innovation Unit (CIEMAT)

NNDC Services B. Pritychenko National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY , USA.

Fusion Neutronics, Nuclear Data, Design & Analyses

Beginning Chapter 2: Energy Derivation of Multigroup Energy treatment

Covariance Processing at ORNL Using PUFF-IV/ERRORJ Code

Covariance Processing at ORNL Using PUFF-IV/ERRORJ Code

Collisions How does the momentum of the system before the collision compare to the momentum of the system after the collision? Purpose: To create graphical.

Visual Studio 2005 Options for Release Mode: C++, Fortran, Linker

Next Version of JENDL General Purpose File

Safety Demonstration of Advanced Water Cooled Nuclear Power Plants

Improvements of Nuclear Fuel Cycle Simulation System (NFCSS) at IAEA

The TALYS nuclear model code II

Presentation transcript:

Status of Nuclear Data Processing Codes at CNDC China Nuclear Data Center(CNDC) China Institute of Atomic Energy(CIAE) P.O.Box ,Beijing , P.R.China Liu Ping

Contents Introduction Nuclear Data Processing Code - Data processing code based on NJOY - Ruler Preparation of Data Library Summary

1. Introduction

The purpose of our data processing activities - Nuclear data Verification and Validation for CENDL - Preparation of application libraries from evaluated data files The current commonly used data processing codes NJOY - Version: NJOY The most widely used applied code system PREPRO2015 Ruler - Our own nuclear data processing code - Partial modules of Ruler have been used for processing data files

To meet the requirement of improving nuclear data processing capability, some activities are being carried out at CNDC, including: Development of nuclear data processing code system based on NJOY Improvement of Ruler Updating ACER module of NJOY99 Preparation of application libraries in specified format

2. Nuclear Data Processing Code

Data processing codes based on NJOY Only NJOY (NJOY99.396) NJOY can be used to generate - ACE format data files - WIMS-D format data files - MATXS format data files - Other format data files

Data processing codes based on NJOY NJOY plus the interface code AMPX format dada files Specified format data files

Basic way API-centric Code Structure Our own data processing code -Ruler

Ruler ModuleFunctionPriorityContents MainMain codeLowMain code ENDF_IOI/O of ENDF filesHighRead and write ENDF, PENDF and GENDF files PUB_SUBPublic subroutinesLowPublic subroutines needed for other modules MATHCommon mathematics functionsLowCommon mathematics functions needed for other modules RXSPResonance reconstructionLowReconstruct resonance cross sections from resonance parameters DOPPLERDoppler-broadenedLowGenerate Doppler-broadened cross sections NURDUnresolved resonance self-shieldedHighProduce effective self-shielded cross sections in unresolved energy range TSCThermal scattering data processingHighGenerate point-wise scattering cross sections in the thermal energy range KDCHeating processingHighGenerate heat production cross sections and damage energy production GACProduction of multi-group constantsHighProduce multi-group cross sections, group-to-group scattering matrices GWIMSWIMS interfaceHighPrepare libraries for the reactor physics codes WIMS

Ruler Flow chart for generating data library

Ruler The characteristics of Ruler Independent ENDF I/O module/library Easy for maintenance and extension Relatively easy for modification when the ENDF format is changed Running environment WindowsLinux Operation systemWinXP SP3 and its higher versionCentOS 5 and its higher version Compilation environment Visual Studio Intel Parallel Studio XE 2013 Intel Visual Fortran v9 Memory≥2G

Ruler Ruler physics Ruler can be used for - Generating WIMS-D/WIMS-D + format data files - Generating continues energy point format cross sections - Processing resonance parameters with R-matrix Limited format

Ruler ENDF_I/O The I/O consists of two parts, data type and user interface ENDF files types

Ruler User interface and function of ENDF_IO InterfaceFunction Subroutine read_endf_file(fin,endf,mat)Read data from(P)ENDF files Subroutine read_gendf_file(fin,endf,mat)Read data from GENDF files Subroutine write_endf_file(fout,endf,overwrite)Write onto a(P)ENDF files Subroutine write_gendf_file(fout,endf,overwrite)Write onto aGENDF files Subroutine del_endf(endf)Release memory space Subroutine del_gendf(gendf)Release memory space Interface insert_mtInsert file onto specified position Interface find_mtFind specified MT file

Ruler The differences of Ruler and NJOY Processing way - Ruler: API-centric - NJOY: File-centric Computation time Nuclide Running time (s) DOPPLER/RulerBROADR/NJOY 232 Th U U U Pu Nuclide Running time (s) GAC/RulerGROUPR/NJOY 130 I Ac U

Ruler

Ruler Different capture KERMA calculation formula HEATR/NJOY (1) (estimates the recoil duo to capture using conservation of momentum. ) KDC/Ruler Using conservation of kinetic energy (2) The deexcitation energy is the excitation energy ( ) According to the conservation of kinetic energy, then (3)

There are big differences between NJOY and Ruler in the low energy region Ruler

3. Preparation of Data Library

The processed data format ACE format WIMS-D/WIMS-D + format AMPX format Specified format The application codes using processed data MCNP PASC WIMSD5B SCALE4.3 Other code

The characteristics of group structure Using fixed group structure of NJOY - Continuous energy point for ACE libraries - Multi-group for deterministic code 69, 172, 171, 238 etc. Designing the group structure The basic method is using fine group structure for main library, and broader group structure for working library - Main library with hundreds of group - Working library with less group

4. Summary

Current CNDC activities on nuclear data processing code were presented Possible work to be made: Application of Ruler - More test of code is needed Internal test Public test - Code release? Function extension of Ruler - Add photon processing module in Ruler - Add more interface modules Modification of ENDF_IO module for new data format