A Preliminary Report on Static Analysis of C Code for Nuclear Reactor Protection System

نویسندگان

  • Jong-Hoon Lee
  • Eui-Sub Kim
  • Junbeom Yoo
  • Jang-Soo Lee
چکیده

Cybersecurity regulations require new I&C (Instrumentation & Control) systems in nuclear power plants to develop software in accordance with secure software development methodology to prevent the digital systems from cyber attacks. One of the common aspects of various secure software development methodologies is that widely-accepted practices should be followed throughout programming. As PLC (Programmable Logic Controller) is used to implement digital I&Cs, C programs are often translated automatically from design specifications such as FBD programs. This paper tries to analyze a part of preliminary version of C codes of a Korean I&C system with a static source code analysis tool of Microsoft. It shows that the automatic translator from FBD to C had a few critical defects, not concerned with security directly. It also recommends to select appropriate analysis tools and rule sets to check best practices in secure programming, even if the C code is produced mechanically.

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

Radiation Safety Assessment of the New Neutron Radiography System at Tehran Research Reactor

Recently, a new Neutron Radiography (NR) beam line has been designed, constricted, installed and tested based on the use of E-beam tube of Tehran Research Reactor (TRR). Initial tests have been shown that the system can be used for different samples and purposes such as nuclear plates and rods fuels.  For this end the system need a suitable irradiation room which should be installed at the NR b...

متن کامل

Flow Blockage Accident Analysis of Tehran Research Reactor Fuel Assembly

Tehran Research Reactor (T.R.R.) is a pool-type, 5 MW thermal research reactor. One probable event is that if some external objects or debris fall down into the reactor core and cause obstruction of the coolant flow through one of the fuel assemblies, decreasing the surface flow area, ceases the coolant flow, and also raises the fuel and sheaths tempe...

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

Ageing Research for Upgrades Using Digital I&c Systems of Nuclear Power Plant

The paper describes the studies on the ageing research for upgrades using digital I&C system. After the ageing analysis of QNPP reactor protection system, we will upgrade the analog reactor protection system using digital system. The paper also describes the digital modernization oAf QNPP reactor protection system and the ageing study of the QNPP digital reactor protection system.

متن کامل

Status Report on SHARP Coupling Framework

This report presents the software engineering effort under way at ANL towards a comprehensive integrated computational framework (SHARP) for high fidelity simulations of sodium cooled fast reactors. The primary objective of this framework is to provide accurate and flexible analysis tools to nuclear reactor designers by simulating multiphysics phenomena happening in complex reactor geometries. ...

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 2013