Thermal-Hydraulic Analysis of SWAMUP Facility Using ATHLET-SC Code

نویسندگان

  • Zidi Wang
  • Zhen Cao
  • Xiaojing Liu
چکیده

*Correspondence: Xiaojing Liu, School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 800 Dongchuan Road, Shanghai 200240, China e-mail: [email protected] During the loss of coolant accident (LOCA) of supercritical water-cooled reactor (SCWR), the pressure in the reactor system will undergo a rapid decrease from the supercritical pressure to the subcritical condition. This process is called trans-critical transients, which is of crucial importance for the LOCA analysis of SCWR. In order to simulate the trans-critical transient, a number of system codes for SCWR have been developed up to date. However, the validation work for the trans-critical models in these codes is still missing.The test facility Supercritical WAter MUltiPurpose loop (SWAMUP) with 2 × 2 rod bundle in Shanghai Jiao Tong University (SJTU) will be applied to provide test data for code validation. Some pre-test calculations are important and necessary to show the feasibility of the experiment. In this study, trans-critical transient analysis is performed for the SWAMUP facility with the system code ATHLET-SC, which is modified in SJTU, for supercritical water system. This paper presents the system behavior, e.g., system pressure, coolant mass flow, cladding temperature during the depressurization. The effects of some important parameters such as heating power, depressurization rate on the system characteristics are also investigated in this paper. Additionally, some sensitivities study of the code models, e.g., heat transfer coefficient, critical heat flux correlation are analyzed and discussed. The results indicate that the revised system code ATHLET-SC is capable of simulating thermal-hydraulic behavior during the trans-critical transient. According to the results, the cladding temperature during the transient is kept at a low value. However, the pressure difference of the heat exchanger after depressurization could reach 6 MPa, which should be considered in the experiment.

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

ATHLET Framework for Embedding/Extending: An Efficient, Flexible & Easy-to-use Python Framework to a Large FORTRAN Code

— Over the years, large scientific code packages have been successfully developed using FORTRAN. Today, maintaining and extending these codes is a challenging task and often forbids several possibilities. Rewriting legacy code packages is almost prohibitive due to lacking resources and inertia against changing functional codes. One way of tackling these challenges is to integrate scripting lang...

متن کامل

Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model

Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the distribution of heat sources, which is needed to perform the thermal-hydraulic analysis. In this study single heated channel model as a very f...

متن کامل

Simulation of the OECD NEA Kalinin-3 benchmark (phase 2) by the ATHLET-KIKO3D code system

As a logical continuation of the former benchmark activity of AER devoted to the VVER reactor physics [1-3], now there is a rather large interest of the Kalinin-3 benchmark recently completed and published by the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD) [4]. The goals of these exercises were the evaluation of the prediction capability of ad...

متن کامل

Benchmarking of the 3d Cfd Code Gasflow Ii with Containment Thermal Hydraulic Tests from Hdr and Thai

A good understanding of the thermal hydraulic conditions resulting from steam-hydrogen releases in nuclear reactor containments is required for all aspects of accident management and for the design of mitigation measures. The GASFLOW II code has been developed at Forschungszentrum Karlsruhe (FZK) for analysis of such scenarios. It solves the three dimensional compressible transient Navier Stoke...

متن کامل

Optimised BNCT facility based on a compact D-D neutron generator

Background: Boron Neutron Capture Therapy (BNCT) is a very promising treatment for patients suffering gliobastoma multiforme, an aggressive type of brain cancer, where conventional radiation therapies fail. Thermal neutrons are suitable for the direct treatment of cancers which are located at near-tissue-surface deep-seated tumors need harder, epithermal neutron energy spectra. Materials and Me...

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 2015