Environmental Engineering Reference
In-Depth Information
REFERENCES
The development and implementation of SHC
RG&IC-R involves preservation of algorithms,
priorities of control functions, control rod drive
management principles, connections with other
power unit I&C systems and peripheral equipment
used in the operational rod group and individual
control systems at Ukrainian NPPs. Modern infor-
mation technologies, new electronic components
and computer systems for data processing, storage,
display and recording have improved consumer
properties and operational reliability of the sys-
tem upgraded on the basis of SHC RG&IC-R.
All main and a number of auxiliary functions are
based on field programmable gate arrays (FPGA),
the electronic designs of which were developed
and implemented by RPC “Radiy.” The use of
FPGA ensured high flexibility comparable with
the capabilities of programmable computer aids
and, at the same time, adequate predictability of
the behavior and testability typical of hard-wired
technologies.
Compliance with requirements of applicable
nuclear and radiation safety regulations and
standards is confirmed by the Ukrainian Nuclear
Safety Regulatory Authority based on state review
of the documentation and validation of deliverable
complete set SHC RG&IC-R.
The modernization of the rod group and indi-
vidual control system by replacement of obsolete
and physically aging equipment of the central part
of these systems with new software-hardware
complexes is a promising area in ensuring the
reliability, safety, and effectiveness of Ukrainian
NPPs.
The software-hardware complex SHC RG&IC-R
can also be recommended as a technical base for
modernization of the rod group and individual
control systems at WWER-1000 NPPs operated
in other countries (see Chapter 8) and at new
power units, including designs with an increased
number of control rods.
Gorochov, A. et al. (2004). Explanation of neutron-
physical and radiation parts in WWER design .
Moscow: Akademkniga.
GOST. (1991). GOST 29216. Electromagnetic
compatibility of technical means: Man-made noise
from information technology equipment: Limits
and test methods.
GOST. (1998). GOST 30546.1. Common require-
ments for seismic resistance of equipment, devices
and other technical items and methods of their
calculations .
IAEA. (1999). INSAG-12. Basic safety principles
for nuclear power plants (75-INSAG-3, Rev. 1) .
Vienna, Austria: IAEA.
IAEA. (2000). NS-R-1. Safety of nuclear power
plants: Design: Safety requirements . Vienna,
Austria: IAEA.
IAEA. (2002). NS-G-1.3. Instrumentation and
control systems important to safety in nuclear
power plants: Safety guide . Vienna, Austria:
IAEA.
IEC. (2011). IEC 61513. Nuclear power plants -
Instrumentation and control important to safety
- General requirements for systems .
Nikituk, V. et al. (2004). WWER control rod drives
for nuclear power plants . Moscow: Akademkniga.
NP. (2000). NP 306.5.02/3.035. Requirements for
nuclear and radiation safety information and con-
trol systems important to safety of nuclear power
plants . Kiev, Ukraine: State Nuclear Regulatory
Committee.
NP. (2008a). NP 306.2.141. General provisions on
the safety of nuclear power plants . Kiev, Ukraine:
State Nuclear Regulatory Committee.
NP. (2008b). NP 306.2.145. Nuclear safety regu-
lations the reactors nuclear power plants with
pressurized water reactors . Kiev, Ukraine: State
Nuclear Regulatory Committee.
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