Development and assessment of U.S. nuclear regulatory commission thermal-hydraulic system computer codes

被引：1
|
作者：
Shotkin, LM
机构：
[1] U.S. Nuclear Regulatory Commission, Mail Stop T-10E37, Washington
来源：
NUCLEAR TECHNOLOGY | 1996年 / 116卷 / 02期
关键词：
thermal-hydraulic; computer codes; NRC;
D O I：
10.13182/NT96-A35303
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
A review is provided of the reasons why the U.S. Nuclear Regulatory Commission needs thermal-hydraulic system computer codes, the assumptions and approximations contained within these codes, and the reasons why test data are required to assess the accuracy of the codes. Specific examples of codes and test programs are given. The use of computer codes assessed against data from scaled test facilities to predict the full-scale plant response is discussed. A method to help focus resources and the need for quantifying code uncertainties are discussed.
引用
收藏
页码：231 / 244
页数：14
相关论文
共 50 条
  • [1] Overview of U.S. nuclear regulatory commission security activities
    Harris, T.
    Layton, M.
    Journal of Nuclear Materials Management, 2010, 38 (04): : 36 - 39
  • [2] U.S. Nuclear regulatory commission activities in the next 25 years
    Radwaste Solutions, 2013, 20 (02): : 6 - 7
  • [3] NEW YORK V. U.S. NUCLEAR REGULATORY COMMISSION
    Harnett, Hillary H.
    HARVARD ENVIRONMENTAL LAW REVIEW, 2013, 37 (02) : 589 - 605
  • [4] LESSONS LEARNED FROM THE U.S. NUCLEAR REGULATORY COMMISSION'S DIGITAL SYSTEM RISK RESEARCH
    Arndt, Steven A.
    Kuritzky, Alan
    NUCLEAR TECHNOLOGY, 2011, 173 (01) : 2 - 7
  • [5] Integral Test Facilities and Thermal-Hydraulic System Codes in Nuclear Safety Analysis
    Umminger, Klaus
    Del Nevo, Alessandro
    SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS, 2012, 2012
  • [6] Materials engineering perspective on license renewal at the U.S. Nuclear Regulatory Commission
    Banic, Merrilee
    Nuclear Engineer, 1999, 40 (03): : 75 - 79
  • [7] FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics
    Ahn, S. H.
    Aksan, N.
    Austregesilo, H.
    Bestion, D.
    Chung, B. D.
    D'Auria, F.
    Emonot, P.
    Gandrille, J. L.
    Hanninen, M.
    Horvatovic, I.
    Kim, K. D.
    Kovtonyuk, A.
    Petruzzi, A.
    NUCLEAR ENGINEERING AND DESIGN, 2015, 281 : 103 - 113
  • [8] Status and trends of thermal-hydraulic system codes for nuclear power plants with pressurized water reactors
    State Nuclear Power Technology Corporation Ltd., Beijing 100140, China
    不详
    Yuanzineng Kexue Jishu, 2009, 11 (966-972):
  • [9] Uncertainties in Predictions by System Thermal-Hydraulic Codes: The CASUALIDAD Method
    Petruzzi, A.
    D'Auria, F.
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 2B, 2014,
  • [10] Development of the Subchannel Flow Mixing Model into a Nuclear Thermal-Hydraulic System Code
    Kim, Dong Wi
    Jeong, Jae Jun
    TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS B, 2018, 42 (10) : 665 - 674
12345