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Products

Products

Digital Reactivity Computer System

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ADRCS
  • DRCS(Digital Reactivity Computer System) is a mandatory equipment used for LPPT(Low Power Physics Test)-ANS/ANSI 19.6.1_ in Korean PWR(Pressurized Water Reactor).
  • DRCS receives a rapidly changing signal from the Ex-Core(Uncompensated Ion Chamber or Fission Chamber), measured and processes digitally.
    (Significant improvement in the reliability of measurements over traditional analog installations)
  • The core operating variable of Reactivity, Neutron Flux and RCS(Reactor Coolant System) Temperature should be monitored in real time.
  • Reactor core characteristics are automatically analyzed using the analysis software, as well as safe monitoring of the reactor conditions.
    (Analysis Item : POAH(Point Of Adding Heat), BEP(Boron End Point), ITC(Isothermal Temperature Coefficient), Rod Worth Measurement(SWAP, DCRM))
  • Compatible for all PWR and PHWR(Heavy Water Reactor) use.
ADRCS — Digital Reactivity Computer System

On-line Neutron Inverse Count Rate Using Excore Detector

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ONICE
  • ONICE is capable of monitoring the sub-critical conditions of the core and raising an alarm when approaching to initial critical of core.
  • ONICE is used for the fuel loading and the initial critical access test of the reactor, and is used for real-time monitoring of the sub-critical conditions of the core.
  • ONICE is capable of continuously monitoring the core changes through real-time monitoring.
  • ONICE has improved user convenience by software(automating) the loading of fuel and the initial critical approach procedure.
ONICE system overview
ONICE hardware unit
ONICE system diagram

Temporary Neutron Monitoring System

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TNMS(TFLC)
  • TNMS is used to monitor the sub-critical multiplication during the initial core fuel loading of PWR.
  • The leakage rate of neutrons is very small during the fuel loading in the initial core, and we can not monitor it only with the ENFMS(Excore Neutron Flux Measurement System)
  • TNMS, a dunker built-in the neutron detector, monitors the subcritical conditions of the core in real time during fuel loading.
TNMs Dunker
TNMs Dunker
Signal Processor
Signal Processor
Monitoring Software
Monitoring Software

Auxiliary Ex-core Neutron Flux Monitoring System

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AENFMS
  • AENFMS is for monitoring the sub-critical of core and ensuring the stability of the reactor during fuel loading and initial critical approach.(FSAR : K=0.98, 0.5cps)
  • AENFMS plays the role of a start-up channel of ENFMS during initial fuel loading and initial critical approach.
  • AENFMS has improved measurement sensitivity by at least 10 times more than traditional equipment.
  • AENFMS is fixed using a support for the radius of reactor insulation located at 9 degrees clockwise from fission chamber A, D channel of ENFMS.
AENFMS — Auxiliary Ex-core Neutron Flux Monitoring System

CoSi

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CoSi
  • CoSi is and educational simulator for LPPT
  • CoSi enables realistic training by identical description of the actual MCR(Main Contorl Room) panel and characteristics of the low power section of the reactor.
  • CoSi accurately describes the core characteristics using a proven RAST-K
  • LPPT tranning is possible by linking CoSi and DRCS
CoSi simulator overview
CoSi MCR panel
CoSi monitoring display

Measurement Technic

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Boronometer
  • Existing boronometer have low measurement accuracy at high boron concentration.
  • High boron concentration reduces the neutron counts measured by absorption of neutrons.
  • To overcome the disadvantages in high boron concentration, high sensitivity detectors were add. And the conversion function was optimized using MCNP code.
Boronometer detector layout
Boronometer measurement data
Boronometer system

Existing System Detector : 0~5000 ppm → BF3 4ea
Improvement System Detector:
0 ~ 1500 ppm → BF3 4ea
1500 ~ 5000 ppm → BF3 4ea + He3 2ea

CoSi(Core Simulator)

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CoSi
  • Cosi is a system developed according to the need for education/training related to various nuclear reactors.
  • Unlike the existing full scope simulator, by modeling the nuclear reactor as the main target, the nuclear/thermal hydraulic phenomena of the actual nuclear reactor are accurately simulated.
  • 3D real-time analysis of neutron behavior in the reactor core is possible.
  • It is a core-only simulator that provides realistic education and training effects by providing screen composition and reactivity control functions similar to those of the nuclear reactor main control room.
CoSi 1st Generation
1st Generation
CoSi 2nd Generation
2nd Generation

Core Simulator – e-CORSIM

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E-CORSIM
  • The PC-based core simulator (e-CORSIM) can be directly used for reactor core design analysis and commissioning core management training.
  • Through this, it is possible to strengthen the educational capacity of core technology and improve the practical adaptability of domestic and foreign students majoring in nuclear energy and experts who will be engaged in the field of nuclear energy.
  • In addition, it contributes to fostering conditions for overseas advancement of domestic technologies.
e-CORSIM 1
e-CORSIM 2
e-CORSIM 3

Core Simulator – e-PASIM

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e-PASIM
  • Nuclear power plant analysis simulators for education were produced and supplied to universities in three Asian countries.
  • While developing the software for the nuclear power plant analysis simulator for education, a GUI in the form of a recent trend was incorporated, and convenience items were strengthened in addition to existing software functions.
  • Education through the developed simulator is expected to deliver more effective understanding and knowledge about nuclear power to trainees.
e-PASIM 1
e-PASIM 2
e-PASIM 3
e-PASIM 4

UCMS (Unified Core Management System)

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UCMS
  • Core design: Web-based core design GUI of APA (Alpha-Paragon-ANC) code system
UCMS 1
UCMS 2
UCMS 3
UCMS 4
UCMS 5
UCMS 6
MAP