Method of evaluating aerosol removal rate by steam condensation in steel containment
US-12366514-B2 · Jul 22, 2025 · US
US2018019029A1 · US · A1
| Field | Value |
|---|---|
| Publication number | US-2018019029-A1 |
| Application number | US-201715617487-A |
| Country | US |
| Kind code | A1 |
| Filing date | Jun 8, 2017 |
| Priority date | Jul 15, 2016 |
| Publication date | Jan 18, 2018 |
| Grant date | — |
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A system for simulating maintenance of a reactor core protection system that has at least two or more channels, includes: a simulation signal generation unit for generating a simulation state signal including a normal state or an abnormal state, a communication unit connected to each of the channels of the reactor core protection system to transmit the state signal to the channel, and a control unit for receiving a result signal output from the channel in response to the input simulation state signal and confirming whether the reactor core protection system normally determines a reactor core state by analyzing the result signal.
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What is claimed is: 1 . An apparatus for simulating maintenance of a reactor core protection system including at least two or more channels, the apparatus comprising: a simulation signal generation unit configured to generate a simulation state signal including a normal state or an abnormal state, a communication unit connected to each of the channels of the reactor core protection system and configured to transmit the state signal to each of the channels, and a control unit configured to receive a result signal output from each of the channels in response to the input simulation state signal and to confirm whether the reactor core protection system normally determines a reactor core state by analyzing the result signal. 2 . The apparatus according to claim 1 , wherein the simulation signal generation unit generates the simulation state signal including at least any one of a reactor temperature, a reactor pressure, a hot leg temperature, a pump rotation speed, a neutron level, a flow rate and a reactor control rod position. 3 . The apparatus according to claim 2 , wherein the simulation signal generation unit generates first to fourth simulation state signals for the reactor control rod position, and the communication unit transmits the first simulation state signal to a first channel, the second simulation state signal to a second channel, the third simulation state signal to a third channel and the fourth simulation state signal to a fourth channel. 4 . The apparatus according to claim 3 , wherein the first simulation state signal includes twenty-three signals, and the second simulation state signal includes seventy signals. 5 . The apparatus according to claim 1 , wherein the simulation signal generation unit generates a simulation state signal of a form including at least any one of a ramp signal, a step signal, an impulse signal, a pulse signal and a sinusoidal signal. 6 . The apparatus according to claim 1 , wherein the reaction core protection system includes first to fourth channels, and the communication unit transmits the simulation state signal to all of the first to fourth channels of the reactor core protection system. 7 . The apparatus according to claim 1 , wherein the communication unit is connected to the reactor core protection system through a connector. 8 . The apparatus according to claim 1 , further comprising a response time test unit configured to measure a time taken from transmission of the simulation state signal and reception of the result signal. 9 . The apparatus according to claim 8 , wherein if the response time is delayed longer than a preset standard response time after the response time test unit measures the response time, the control unit analyzes corresponding content. 10 . The apparatus according to claim 1 , further comprising a control rod position determination unit configured to receive a control rod position signal of the reactor core protection system. 11 . The apparatus according to claim 10 , further comprising a control rod drop time test unit configured to measure a drop time of a control rod when the control rod of the reactor core protection system is shut down according to a simulation abnormal state signal generated by the simulation signal generation unit. 12 . The apparatus according to claim 11 , wherein the control rod drop time test unit measures and stores all of the drop time of the control rod for each of the channels. 13 . The apparatus according to claim 11 , wherein the control unit determines whether the reactor core protection system normally determines a reactor core state according to the measured drop time of the control rod. 14 . A system for simulating maintenance of a reactor core protection system, the simulation system comprising: a simulation apparatus configured to generate a simulation state signal including a normal state or an abnormal state, and first to n-th channels included in the reactor core protection system and respectively connected to the simulation apparatus, wherein the first to n-th channels receive the generated simulation state signal, output a result signal, and transmit the result signal to the simulation apparatus, and the simulation apparatus confirms whether the reactor core protection system normally determines a reactor core state by analyzing the result signal. 15 . A method of simulating maintenance of a reactor core protection system, the method comprising the steps of: generating, using a simulation signal generation unit, a simulation state signal including a normal state or an abnormal state; transmitting, using a communication unit, the simulation state signal to at least two or more channels respectively connected to the reactor core protection system; receiving, using a control unit, a result signal output from each of the channels in response to the input simulation state signal; and confirming, using the control unit, whether the reactor core protection system normally determines a reactor core state by analyzing the result signal.
for nuclear physics, e.g. nuclear reactors, radioactive fall {(processing of scintigraphic or other radio-isotope data G01T1/1647, G01T1/2992)} · CPC title
Safety arrangements (emergency protection of reactor G21C9/00) · CPC title
Mechanical simulators (electrical or magnetic simulators G06G7/54) · CPC title
Power analysis or power optimisation · CPC title
Core design; core simulations; core optimisation · CPC title
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