• Title/Summary/Keyword: Code development

Search Result 2,643, Processing Time 0.029 seconds

Code development on steady-state thermal-hydraulic for small modular natural circulation lead-based fast reactor

  • Zhao, Pengcheng;Liu, Zijing;Yu, Tao;Xie, Jinsen;Chen, Zhenping;Shen, Chong
    • Nuclear Engineering and Technology
    • /
    • v.52 no.12
    • /
    • pp.2789-2802
    • /
    • 2020
  • Small Modular Reactors (SMRs) are attracting wide attention due to their outstanding performance, extensive studies have been carried out for lead-based fast reactors (LFRs) that cooled with Lead or Lead-bismuth (LBE), and small modular natural circulation LFR is one of the promising candidates for SMRs and LFRs development. One of the challenges for the design small modular natural circulation LFR is to master the natural circulation thermal-hydraulic performance in the reactor primary circuit, while the natural circulation characteristics is a coupled thermal-hydraulic problem of the core thermal power, the primary loop layout and the operating state of secondary cooling system etc. Thus, accurate predicting the natural circulation LFRs thermal-hydraulic features are highly required for conducting reactor operating condition evaluate and Thermal hydraulic design optimization. In this study, a thermal-hydraulic analysis code is developed for small modular natural circulation LFRs, which is based on several mathematical models for natural circulation originally. A small modular natural circulation LBE cooled fast reactor named URANUS developed by Korea is chosen to assess the code's capability. Comparisons are performed to demonstrate the accuracy of the code by the calculation results of MARS, and the key thermal-hydraulic parameters agree fairly well with the MARS ones. As a typical application case, steady-state analyses were conducted to have an assessment of thermal-hydraulic behavior under nominal condition, and several parameters affecting natural circulation were evaluated. What's more, two characteristics parameters that used to analyze natural circulation LFRs natural circulation capacity were established. The analyses show that the core thermal power, thermal center difference and flow resistance is the main factors affecting the reactor natural circulation. Improving the core thermal power, increasing the thermal center difference and decreasing the flow resistance can significantly increase the reactor mass flow rate. Characteristics parameters can be used to quickly evaluate the natural circulation capacity of natural circulation LFR under normal operating conditions.

Development of A Three-Dimensional Thermo-Hydraulic Computer Code for Incompressible Flows in Complex Geometries

  • Park, Seok-Ki;Lee, Yong-Bum;Hwang, Jong-Sun;Nam, Ho-Yun;Mann Cho
    • Proceedings of the Korean Nuclear Society Conference
    • /
    • 1996.05b
    • /
    • pp.173-178
    • /
    • 1996
  • A three-dimensional thermo-hydraulic computer code is developed for simulation of incompressible flows in complex geometries. The computer code employs a body-fitted, nonorthogonal grid system in order to efficiently handle the complex geometries encountered in many engineering applications. The finite volume method is used to discretize the governing equations and the convection term is treated by higher-order bounded schemes. The cell-centered, nonstaggered grid arrangement is adopted and the resulting checkerboard pressure oscillation is avoided by use of momentum interpolation practice. The computer code employs the SIMPLE algorithm for pressure and velocity coupling and the k-$\varepsilon$ turbulence for turbulent calculation. The computer code has been tested through application to a variety of test problems and some results are presented in this paper

  • PDF

Performance of PN Code Tracking Loop for a DS/CDMA System with Imperfect Power Control and Shadowing

  • Kim, Jin-Young
    • Proceedings of the IEEK Conference
    • /
    • 2000.07a
    • /
    • pp.501-504
    • /
    • 2000
  • In this paper, performance of a pseudonoise (PN) code tracking loop is analyzed and simulated for a direct-sequence/code-division multiple access ( DS/CDMA) system with imperfect power control in a multipath fading channel. A noncoherent first-order delay-locked loop (DLL) is considered as a PN code tracking loop. Power control error is modeled as a log-normally distributed random variable. From the simulation results, it is shown that for smaller discriminator offset, tracking jitter performance is improved while MTLL performance is degraded. It is shown that large power control error and heavy shadowing substantially degrade the PN tracking performance. The analysis in this paper can be applicable to design of PN code tracking loop for a DS/CDMA system.

  • PDF

Development of Code for Numerical Analysis of Interior Ballistics using Eulerian-Lagrangian Approach and SMART scheme (Eulerian-Lagrangian 접근법과 SMART scheme을 이용한 강내탄도 전산해석 코드 개발)

  • Sung, Hyung-Gun;Jang, Jin-Sung;Lee, Sang-Bok;Choi, Dong-Whan;Roh, Tae-Seong;Jang, Young-Jae
    • Journal of the Korea Institute of Military Science and Technology
    • /
    • v.13 no.3
    • /
    • pp.349-357
    • /
    • 2010
  • In this paper, a numerical code for the interior ballistics has been investigated. The Eulerian-Lagrangian approach and the SMART scheme have been used in the numerical code for the grain combustion. The translational kinetic energy of the projectile and work done against barrel friction have been considered only. The ghost cell extrapolation method has been used for the chamber change with the projectile movement. The calculation results of the numerical code have been compared and verified through those of IBHVG2 code.

Integration of the microplane constitutive model into the EPIC code

  • Littlefield, David;Walls, Kenneth C.;Danielson, Kent T.
    • Computers and Concrete
    • /
    • v.7 no.2
    • /
    • pp.145-158
    • /
    • 2010
  • In this work the implementation of a production-level port of the Microplane constitutive model for concrete into the EPIC code is described. The port follows guidelines outlined in the Material Model Module (MMM) standard used in EPIC to insure a seamless interface with the existing code. Certain features of the model were not implemented using the MMM interface due to compatibility reasons; for example, a separate module was developed to initialize, store and update internal state variables. Objective strain and deformation measures for use in the material model were also implemented into the code. Example calculations were performed and illustrate the veracity of this new implementation.

STRAUM-MATXST: A code system for multi-group neutron-gamma coupled transport calculation with unstructured tetrahedral meshes

  • MyeongHyeon Woo;Ser Gi Hong
    • Nuclear Engineering and Technology
    • /
    • v.54 no.11
    • /
    • pp.4280-4295
    • /
    • 2022
  • In this paper, a new multi-group neutron-gamma transport calculation code system STRAUM-MATXST for complicated geometrical problems is introduced and its development status including numerical tests is presented. In this code system, the MATXST (MATXS-based Cross Section Processor for SN Transport) code generates multi-group neutron and gamma cross sections by processing MATXS format libraries generated using NJOY and the STRAUM (SN Transport for Radiation Analysis with Unstructured Meshes) code performs multi-group neutron-gamma coupled transport calculation using tetrahedral meshes. In particular, this work presents the recent implementation and its test results of the Krylov subspace methods (i.e., Bi-CGSTAB and GMRES(m)) with preconditioners using DSA (Diffusion Synthetic Acceleration) and TSA (Transport Synthetic Acceleration). In addition, the Krylov subspace methods for accelerating the energy-group coupling iteration through thermal up-scatterings are implemented with new multi-group block DSA and TSA preconditioners in STRAUM.

Study on the Effect on the Development Design of Headed Deformed Bars by change of ACI 318-19 (ACI 318-19 변경에 따른 확대머리철근 정착설계의 영향분석)

  • Lee, Byung Soo
    • Proceedings of the Korean Institute of Building Construction Conference
    • /
    • 2019.11a
    • /
    • pp.110-111
    • /
    • 2019
  • In ACI 318-19 published recently, the conditions and development length equation to use the headed deformed bars were changed considerably. Although the use of the larger-diameter(No.14 and 18) headed deformed bars isn't yet permitted, the use of the high strength(80,000psi) headed deformed bars is permitted and the effect of bar-diameter($d_b$) on the development length is increased considerably. Therefore, structures using larger-diameter headed deformed bars will be expected to be affected by this code change. We will study the effect of the code change on the development design and find out the design optimization method to minimize the effect of the changed conditions and development length equation.

  • PDF

A simulation code generator for AGVS design (무인운반차시스템의 설계를 위한 시뮬레이션 코-드 작성시스템)

  • 김갑환;김판수;배종욱
    • Korean Management Science Review
    • /
    • v.11 no.1
    • /
    • pp.1-21
    • /
    • 1994
  • We usually use the simulation technique in the evaluation and the test of a design alternative of Automated Guided Vehicle System. In this paper, we introduce a simulation code generator which can assist simulation programmer in model development and programming. It consists of user interface, program editor, and program sorter. SIMAN is used as the target language.

  • PDF

Usefulness of CFD code in plasma equipment development (플라즈마 장치 개발에서 CFD code의 유용성)

  • Ju, Jeong-Hun
    • Proceedings of the Korean Institute of Surface Engineering Conference
    • /
    • 2007.04a
    • /
    • pp.22-23
    • /
    • 2007
  • 3차원 모델이 가능한 전산유체역학에 기초를 둔 유체 플라즈마 모델링 소프트웨어가 플라즈마 장치 개발에 어떤 도움을 줄 수 있을 것인지 고찰하였다. 몇 가지의 유도 결합 플라즈마용 안테나 구조와 유동의 역할, 공간 및 표면 화학반응의 결과에 대한 자동 최적화 계산의 유용성에 대해서 논한다.

  • PDF