Overall Instrumentation and Control Systems - Nuclear Power Plant Instrumentation and Control Systems for Safety and Security - page 298

ADDITIONAL READING

absorbers (absorber rods) which can be transferred
in the reactor core.
Emergency Protection: I&C function in-
tended for rapid transfer and long-term support
of the reactor core in a subcritical state, that is
characterized by the effective multiplication fac-
tor whose value is to be less than one, and a lack
of local criticality.
Facilities of Influence on Reactivity: Hard-
ware that provides change of core reactivity due
to change in position of neutron solid sorbents or
density change of fluid sorbents.
Modernization: Set of actions for improve-
ment of safety, functional abilities, reliability
and/or technical and economic measures of an
active I&C system, connected with replacement
of separate components by more up-to-date ones,
which requires changes to the accepted design and
/ or operational documentation. (The same term
is “modification”).
Preventive Protection: I&C function intended
for limitation or decrease of the reactor power to
a safe level in case of operational events.
Primary Circuit: A piping system, techno-
logical facilities, systems and elements intended
for circulation of the coolant through the reactor
core in operation modes and conditions specified
by the design.
Reactor Core: A part of the reactor facility,
in which nuclear fuel, moderator, absorber, cool-
ant, facilities, having an influence on reactivity
and structural elements, intended for a controlled
chain fission reaction and transmission of energy
to the coolant, are located.
Reactor Facility: A Complex of structures,
systems and components intended for conversation
of nuclear energy into thermal energy, including
a nuclear reactor, elements of the primary circuit,
emergency protection and proper I&C systems of
safety and normal operation and a nuclear fuel
reloading system.

Bakhmach, E., Siora, A., Bezsalyi, V., & Yas-
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(2011). Core knowledge on instrumentation and
control systems in nuclear power plants. IAEA
nuclear energy series, No. NP-T-3.12 . Vienna,
Austria: IAEA.

EPRI. (2005). 1011851. Guidance for the Design
and Use of Automation in Nuclear Power Plants .
Palo Alto, CA, USA: Electric Power Research
Institute.

EPRI. (2010). 1015313. Computerized Procedure
Systems: Guidance on the Design, Implementa-
tion, and Use of Computerized Procedure Systems,
Associated Automation, and Soft Controls . Palo
Alto, CA, USA: Electric Power Research Institute.

Kharchenko, V., & Sklyar, V. (Eds.). FPGA-based
NPP. Instrumentation and Control Systems:
Development and Safety Assessment. Research
and Production Corporation Radiy, National
Aerospace University KhAI, State Scientific and
Technical Center for Nuclear and Radiation Safety.
Kirovograd - Kharkov, 2008.

KEY TERMS AND DEFINITIONS

Control and Protection System: A complex
of interconnected safety and normal operation
I&C systems, providing safety control of a chain
nuclear fission reaction.
Control Area: A territory that may be affected
by radioactive releases and discharges from NPP
and where radiation monitoring is conducted.
Control Element: A reactivity control feature
that contains control rods with drives and neutron