Achievements : USERS

Achievements

TNMs Temporary Neutron Monitoring system

Temporary Neutron Monitoring system

The TNMs is installed core inside during fuel loading of initial core, and measures the neutron flux.
The initial core is loaded with only fresh fuel.
Therefore, the neutron Flux that leaks out of core is very low.
The sensitivity of the ENFMS is too low to monitor for low neutron flux during fuel loading of initial core.
According to requirements of fuel loading…
"The loading will be monitored by Two Temporary Fuel Loading Channels to ensure adequate monitoring of the subcritical multiplication status of the core."

System Specification

Detectors : BF3 Proportional Counter (2Ch, 1ea each Ch)
Signal Process Type : Pulse Count Mode
Neutron Sensitivity : 4.7cps/nv per Ch
Dunker 2set
Detector Assembly Cylinder
Preamplifier: Charge Sensitivity Preamplifier
Data Acquisition system:
- Monitoring data : Count rate, RT ICRR, Audible Counter

AENFMs Aux. Ex-core Neutron Flux Monitoring system

Auxiliary Ex-core Neutron Flux Monitoring System

ANFMS is a system for measuring the neutron flux for Initial critical approach in FOAK Reactor
According to FSAR requirements, The neutron count rates should be more than 0.5 cps at keff 0.98 when approach to initial critical
FSAR 14.2.7.1.2 : … Neutron count rate of 1 / 2cps is required when the multiplication factor is 0.98….
For newly NPP, a concerned a arise about dissatisfaction with FSAR requirements as ENFMS Startup Channel changes to fission chamber

System Specification

Detectors : BF3 Proportional Counter (2Ch, 2ea each Ch)
Signal Process Type : Pulse Count Mode
Neutron Sensitivity : 25.2 cps/nv per Ch
Guide thimble and Motor for position shift of Detector
Preamplifier: Charge Sensitivity Preamplifier
Data Acquisition system:
- Amplifier, Discriminator, Count/Timer, H.V Supplier, Control/Monitoring Display
- Monitoring data : Count rate, ICRR, Audible Counter

Spent Fuel Burn-up Measurement

Burn-up Measurement System

Detector cylindrical enclosure Spec
- Size : 128(W) x 128(L) x 358(D), 45Kg
- Water-Proof Design (2 Atm)
- Installation on the spent fuel rack
Detector Spec
- Detector Type : CZT Detector
- Crystal Size : 20mm³, 60mm³
- Energy resolution(FWHM) : 10 keV @ 662 kev peak
Collimator Spec.
- Material : Pb
- Size 1 - Length : 150mm(50 x 3), Hole : 2m
- Size 2 – Length : 150, Fan shape : 22.6°

Boronometer Boron concentration Monitoring

Technical Features

System Performance
- Measurement Range :
  - 0 – 1500 ppm (Narrow Range)
  - 0 – 5000 ppm (Wide Range)
- Reference accuracy
  - Less than 20 ppm for boron conc. < 1500 ppm
  - Less than 2% for boron conc. ≥ 1500 ppm
- Response time < 100 sec (depending on filter time)
Sensor Unit
- Neutron Source : Am-Be – 1Ci
- Neutron Detector :
- BF3 Proportional Detector : 4 ea
- He3 Proportional Detector : 2 ea
- Thermistor : 1ea

Spent Nuclear Fuel–Related Business

We have developed equipment that determines burnup by measuring gamma radiation emitted from spent nuclear fuel, and we provide spent nuclear fuel burnup measurement services using overseas burnup measurement systems. We are also carrying out a government-funded project to develop and establish a spent nuclear fuel safety information database system.

Technical Support for Zero-Power Reactor Physics Testing

During scheduled outages at light-water reactors, we provide technical support for the operation and testing of reactivity computers used in zero-power reactor physics testing to evaluate core characteristics.

Technical Support for Fuel Loading at Light-Water Reactors

During scheduled outages at light-water reactors, we provide operational support for subcriticality monitoring equipment used during fuel loading, as well as technical support for monitoring core conditions.

Technical Support for Initial Core Fuel Loading at Light-Water Reactors

During initial core fuel loading, neutron leakage is extremely low, making it difficult to accurately monitor core conditions using only the ex-core instrumentation used during refueling. Temporary in-core detectors must therefore be installed during fuel loading. We provide technical support for the installation and operation of this temporary in-core instrumentation.

Technical Support for Measuring the Reactivity Worth of the Liquid Zone Control System in Heavy-Water Reactors

Following major plant modifications, we measure the reactivity worth of the liquid zone control system used to control core power. We have completed the development of a reactivity computer for measuring the reactivity worth of the liquid zone control system at Wolsong Unit 1.

Technical Support for Heavy-Water Reactor Flux Scans

We provide technical support for the operation and testing of the movable in-core detector system used to measure the core neutron flux distribution.

Technical Support for Subcriticality Monitoring Equipment During Initial Criticality Approach at Heavy-Water Reactors

We provide technical support for subcriticality monitoring equipment used to monitor subcritical multiplication during the initial approach to criticality in heavy-water reactors.

Technical Support for Auxiliary Ex-Core Neutron Flux Monitoring Systems for Initial Cores at Light-Water Reactors

We provide technical support for auxiliary ex-core neutron flux monitoring systems used for initial cores in light-water reactors.

Technical support for LPPT (Low Power Physics Test)

During scheduled maintenance of PWR plants, we provide technical support for the operation and testing of the Digital Reactivity Computer System (DRCS) used in LPPT testing.

Technical support for nuclear fuel loading

During scheduled maintenance of PWR plants, we support the operating technology of the subcritical monitoring system (ONICE) used for nuclear fuel loading.

Technical support for initial core fuel loading

We support the installation and operation of the Temporary Neutron Monitoring System (TNMS) for initial core fuel loading.

Technical support for PHWR liquid zone control system reactivity worth measurement

We develop reactivity computers for PHWR and provide on-site technical support.

Technical support for PHWR neutron flux scanning

We provide technical support for the operation and testing of the mobile in-core detector system used to measure neutron flux distribution.

Technical support for PHWR-type subcritical monitoring equipment

We provide technical support for the PHWR subcritical monitoring system during the initial approach to criticality.

Technical support for the initial core Auxiliary Ex-core Neutron Flux Monitoring System (AENFMS)

Project References

No.	Project Title	Period	Client
63	U2RFO3 Reactivity Computer Technical Support	2026.05.19 ~ 2026.06.09	Nawah Energy
62	U3RFO2 Reactivity Computer Technical Support	2025.11.12 ~ 2025.11.27	Nawah Energy
61	U4RFO1 Reactivity Computer Technical Support	2025.08.13 ~ 2025.08.30	Nawah Energy
60	U1RFO3 Reactivity Computer Technical Support	2025.03.24 ~ 2025.04.23	Nawah Energy
59	Advancement of Web-Based Core Operation Support Technology and Development of an In-House Code Design Verification System	2026.01.20 ~ 2029.01.19	Korea Hydro & Nuclear Power Co., Ltd.
58	Preliminary Review Service for the Development of In-Core Neutron Flux Monitoring Equipment for Fuel Loading	2025.12.24 ~ 2027.12.13	Korea Atomic Energy Research Institute
57	Development of In-Core Instrumentation System Diagnostic Equipment for Nuclear Power Plant Field Use	2024.08.01 ~ 2026.07.31	Ministry of SMEs and Startups
56	Development of a Multi-Purpose High-Precision Measurement System for Improved Autonomous Operation Performance and Safety	2023.04.01 ~ 2027.12.31	Ministry of Science and ICT
55	U2RFO2 Reactivity Computer Technical Support	2024.09.27 ~ 2024.10.27	Nawah Energy
54	Supply of Reactivity Computer and Subcritical Monitoring Equipment for Hanul Units 3 and 4	2024.05.23 ~ 2024.09.30	Korea Hydro & Nuclear Power Co., Ltd.
53	U3RFO1 Reactivity Computer Technical Support	2024.04.13 ~ 2024.05.11	Nawah Energy
52	BNPP Unit 4 TFLC Installation and Maintenance Services	2023.10.25 ~ 2023.12.31	KEPCO KPS Co., Ltd.
51	Supply of APR1400 Core Simulator	2023.09.01 ~ 2023.10.31	Korea Hydro & Nuclear Power Co., Ltd.
50	Services of Calibration and Testing of ADRCS for BNPP Unit 2 Cycle 2	2023.03.15 ~ 2023.04.14	Nawah Energy
49	Development of an Integrated Core Database for APR1400 Nuclear Power Plants and Technical Support for Reactor Characteristic Tests	2022.08.10 ~ 2025.02.16	Korea Hydro & Nuclear Power Co., Ltd.
48	Services of Calibration and Testing of ADRCS for BNPP Unit 1 Cycle 2	2022.05.26 ~ 2022.07.26	Nawah Energy
47	BNPP Unit 3 TFLC Installation and Maintenance Services	2022.04.22 ~ 2022.07.05	KEPCO KPS Co., Ltd.
46	Spent Nuclear Fuel Burnup Measurement and Result Analysis	2022.03.03 ~ 2022.11.30	KEPCO Nuclear Fuel Co., Ltd.
45	Development of a Monitoring System for Fuel Transfer Status in Light Water Reactor Nuclear Power Plants	2021.11.01 ~ 2022.10.31	Ministry of SMEs and Startups
44	Development of a Visualization Tool for the Molten Material Pool in a Calandria Tank	2021.08.10 ~ 2021.10.08	Korea Atomic Energy Research Institute
43	Standardization of Safety Information Lists and Development of an Information System for the Entire Spent Nuclear Fuel Cycle	2021.08.02 ~ 2026.12.31	Ministry of Trade, Industry and Energy
42	BNPP Unit 2 TFLC Installation and Maintenance Services	2021.01.25 ~ 2022.03.25	KEPCO KPS Co., Ltd.
41	Improvement of Reactivity Computer for Reactor Characteristic Tests and Development of Training Tools	2020.08.13 ~ 2022.01.31	Korea Hydro & Nuclear Power Co., Ltd.
40	Localization of High-Performance In-Core Detector Signal Measurement System and Development of Fundamental Technology Based on Prompt Response Measurement	2020.05.01 ~ 2023.04.30	Ministry of Trade, Industry and Energy
39	BNPP Unit 1 TFLC Installation and Maintenance Services	2020.01.02 ~ 2020.07.14	KEPCO KPS Co., Ltd.
38	Maintenance and Operation Services for Shin Hanul Units 1 and 2 TNMS	2019.12.18 ~ 2021.03.31	Korea Hydro & Nuclear Power Co., Ltd.
37	Development of Multi-Cycle Optimal Core Design Technology Based on Simulated Annealing	2019.03.20 ~ 2021.02.28	Korea Hydro & Nuclear Power Co., Ltd.
36	Development of an Automated Analysis and History Management Database System for Core Fuel Operation Data	2017.07.03 ~ 2018.08.31	Korea Hydro & Nuclear Power Co., Ltd.
35	Development of Core Technology for a Sensor Transfer System for Dry Cask Storage System Inspection of Spent Nuclear Fuel	2017.05.01 ~ 2020.04.30	Ministry of Trade, Industry and Energy
34	Supply of TDAS for Shin Hanul	2017.03.07 ~ 2017.06.30	Korea Hydro & Nuclear Power Co., Ltd.
33	Technical Support for Initial ZPPT (Zero Power Physics Test) at UAE Barakah Nuclear Power Plant	2016.12.16 ~ 2020.06.15	Korea Hydro & Nuclear Power Co., Ltd.
32	Supply of Reactivity Computer and Subcritical Multiplication Monitoring Equipment for UAE Barakah Nuclear Power Plant	2016.05.16 ~ 2017.02.28	Korea Hydro & Nuclear Power Co., Ltd.
31	Provision of Educational Simulators and Training for Nuclear Workforce Development at Three Asian Universities	2016.01.01 ~ 2017.08.31	Hanyang University
30	Development of GUI for Educational Core Simulator	2015.07.01 ~ 2016.04.30	Korea Atomic Energy Research Institute
29	Development of Reactor Coolant Boron Concentration Monitoring Equipment	2015.09.01 ~ 2018.08.31	Ministry of Trade, Industry and Energy
28	Evaluation of Initial Characteristics of Low-Burnup Spent Nuclear Fuel	2015.03.01 ~ 2019.09.30	Ministry of Trade, Industry and Energy
27	Supply of TNMS Equipment for UAE Barakah Nuclear Power Plant	2015.01.26 ~ 2018.01.01	Korea Hydro & Nuclear Power Co., Ltd.
26	Development of an Operation Monitoring System for Overseas Power Plants	2015.01.01 ~ 2015.09.30	KEPCO Research Institute
25	Supply of Auxiliary Ex-Core Neutron Flux Monitoring Equipment for UAE Barakah Nuclear Power Plant	2014.11.10 ~ 2017.03.31	Doosan Heavy Industries & Construction
24	Development of Educational Neutron Flux Simulation Software	2014.08.21 ~ 2014.10.20	Korea Hydro & Nuclear Power Co., Ltd.
23	Localization Development of Ex-Core Neutron Flux Monitoring Equipment for Pressurized Water Reactors	2013.12.01 ~ 2016.09.20	Ministry of Trade, Industry and Energy
22	Development of Boron-Free Operation System Design Technology and Suitable Materials Technology	2013.06.01 ~ 2018.05.30	Ministry of Trade, Industry and Energy
21	Maintenance and Operation Services for Shin Kori Units 3 and 4 TNMS	2012.12.08 ~ 2019.12.31	Korea Hydro & Nuclear Power Co., Ltd.
20	Development of a Core Design Support and Verification System	2012.10.16 ~ 2015.04.30	Korea Hydro & Nuclear Power Co., Ltd.
19	Development of Reactor Characteristic Test System for APR1400 Nuclear Power Plants	2012.09.15 ~ 2014.01.31	Korea Hydro & Nuclear Power Co., Ltd.
18	Operation Services for Temporary Neutron Measurement Equipment at Shin Wolsong Unit 2	2012.06.28 ~ 2014.12.17	Korea Hydro & Nuclear Power Co., Ltd.
17	Development of Suitability and Analysis Methodology for Reactivity Computer Algorithms for APR+ Core	2012.06.15 ~ 2012.12.11	KEPCO Nuclear Fuel Co., Ltd.
16	Operation of Temporary Neutron Measurement Equipment at Shin Wolsong Unit 1	2011.07.01 ~ 2011.09.30	Korea Hydro & Nuclear Power Co., Ltd.
15	Development of Subcritical Neutron Multiplication Monitoring Software for CANDU Nuclear Power Plants	2011.03.21 ~ 2011.06.30	KEPCO E&C
14	Maintenance of Temporary Neutron Measurement Equipment at Shin Kori Unit 2	2011.03.17 ~ 2011.12.23	Korea Hydro & Nuclear Power Co., Ltd.
13	Maintenance of Reactivity Computer and Subcritical Monitoring Equipment for Reactor Characteristic Tests	2011.01.10 ~ 2018.12.31	Korea Hydro & Nuclear Power Co., Ltd.
12	Development of a Three-Dimensional Core Analysis and Operation Support System	2010.06.08 ~ 2011.10.31	Korea Hydro & Nuclear Power Co., Ltd.
11	Development of Turbine Generator Weight Balancing Simulation Program	2009.08.18 ~ 2009.11.17	Korea Electric Power Corporation
10	Development of Reactivity Computer for CANDU Nuclear Power Plants	2009.07.20 ~ 2011.01.19	Korea Electric Power Corporation
9	Maintenance of Reactivity Computer for Reactor Characteristic Tests	2009.01.01 ~ 2010.12.31	Korea Hydro & Nuclear Power Co., Ltd.
8	Development of Reactivity Computer and Training System for OPR-1000 Nuclear Power Plants	2008.07.02 ~ 2010.04.30	Korea Electric Power Corporation
7	Development of Process Simulation System for Large-Capacity Coal-Fired Boilers	2008.03.19 ~ 2008.06.13	Korea Electric Power Corporation
6	Development of APR-1400 Core Model Production and Design Automation Program	2008.01.02 ~ 2008.11.30	Korea Electric Power Corporation
5	Development of Power Plant Dynamic Model and Performance Diagnosis System	2007.10.15 ~ 2009.04.14	Korea Electric Power Corporation
4	Development of CIM-Based AMR Model System and Information Service Portal	2007.10.15 ~ 2008.02.13	Korea Electric Power Corporation
3	Development of a Westinghouse Core Nuclear Design Code Integration Tool for SMART Core Calculation	2007.04.10 ~ 2007.07.09	Korea Electric Power Corporation
2	Development of Core Model Input Data Reflecting Power Uprate for Yeonggwang Units 1 and 2 Simulators	2006.11.01 ~ 2007.11.30	Korea Electric Power Corporation
1	Development of an Automatic Input Constants Generation Program for Core Models of Yeonggwang Units 1 and 2 Simulators	2005.03.02 ~ 2005.07.31	Korea Electric Power Corporation