NUREG/IA-0215 "Spatial Effects and Uncertainty Analysis for Rod Ejection Accidents in a PWR."

نویسندگان

  • A. Avvakumov
  • V. Malofeev
  • V. Sidorov
چکیده

DISCLAIMER: This report was prepared under an international cooperative agreement for the exchange of technical information. Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, apparatus, product or process disclosed in this publication, or represents that its use by such third party would not infringe privately owned rights. NRC publications in the NUREG series, NRC regulations, and Title 10, Energy, in the Code of Federal Regulations may also be purchased from one of these two sources. are updated periodically and may differ from the last printed version. Although references to material found on a Web site bear the date the material was accessed, the material available on the date cited may subsequently be removed from the site. Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions, Federal Register notices, Federal and State legislation, and congressional reports. Such documents as theses, dissertations, foreign reports and translations, and non-NRC conference proceedings may be purchased from their sponsoring organization. Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at— The NRC Technical Library Two White Flint North 11545 Rockville Pike Rockville, MD 20852–2738 These standards are available in the library for reference use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American Legally binding regulatory requirements are stated only in laws; NRC regulations; licenses, including technical specifications; or orders, not in NUREG-series publications. The views expressed in contractor-prepared publications in this series are not necessarily those of the NRC. The NUREG series comprises (1) technical and administrative reports and books prepared by the staff (NUREG–XXXX) or agency contractors (NUREG/CR–XXXX), (2) proceedings of conferences (NUREG/CP–XXXX), (3) reports resulting from international agreements (NUREG/IA–XXXX), (4) brochures (NUREG/BR–XXXX), and (5) compilations of legal decisions and orders of the Commission and Atomic and Safety Licensing Boards and of Directors' decisions under Section 2.206 of NRC's regulations (NUREG–0750). ABSTRACT A rod ejection accident is a design-basis event for a pressurized water reactor. It is well known that spatial effects play a very important role in this accident. In this study four cases using a model of Three …

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

NUREG/IA-0175, Analysis of Pin-by-Effects for LWR Rod Ejection Accident

This study was undertaken to demonstrate capabilities of the pin-by-pin model used by the BARS code and to understand various effects of intra-assembly pin-by-pin representation of fuel power, bumup and temperature in calculational analysis of light water reactor rod ejection accidents (LWR REAs). Effects of pin-by-pin fuel power and bumup representation were investigated on the basis of calcul...

متن کامل

NUREG/CR-6706 "Capacity of Steel and Concrete Containment Vessels with Corrosion Damage" S103109

Corrosion damage has been found in a number of nuclear power plant containment structures, and this could degrade the pressure capacity of the vessel. This has prompted concerns regarding the capacity of corroded containments to withstand accident loadings. For the low-carbon, low-strength steels used in containments, the effect of corrosion on material properties is discussed in this report, a...

متن کامل

NUREG/IA-0477, "International Agreement Report - Thermal Hydraulic and Fuel Rod Mechanical Combination Analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP Interface."

.............................................................................................................................. iii FOREWORD ............................................................................................................................. V LIST OF FIGURES ....................................................................................................................

متن کامل

A Relap/nestle Engineering Simulator for Shared-memory Multiprocessors

The RELAP5/MOD3.2 R/T engineering quality plant simulation code has been developed based on the system thermal-hydraulics code RELAP5 and the nodal spatial kinetics code NESTLE. Preliminary validation of the code as an engineering simulator was performed using a series of NEA PWR control rod ejection and withdrawal problems. Real time performance for simulator applications was demonstrated for ...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 1999