Research on Task Complexity Measurements in Human—Computer Interaction in Nuclear Power Plant DCS Systems Based on Emergency Operating Procedures
Abstract
:1. Introduction
2. Methodology
- (1)
- Task Execution Complexity (TEC): This quantifies the cognitive and operational load of the dynamic interactions between the operator and the interface. It is based on Halstead’s E measure, which statistically counts the types and usage frequencies of operators and operands to reflect the redundancy of interaction paths and the density of operational steps.
- (2)
- Task Logical Complexity (TLC): This measures the diversity of logical branches in the task process. It calculates the equivalent class distribution of nodes in the control flow graph of operational steps using first-order entropy. A higher entropy value indicates greater logical complexity.
- (3)
- Task Information Complexity (TIC): This evaluates the quantity and scale of information required for task execution. It is based on the second-order entropy calculation of the information structure diagram. A higher entropy value indicates greater information complexity.
- (4)
- Task Scale Complexity (TSC): This describes the volume characteristics of the task itself. It quantifies the number of operational steps and their logical dependencies using second-order entropy. A higher entropy value indicates a larger scale.
2.1. E Measurement
2.2. Entropy Measurement
- H represents information entropy.
- is the number of information sources.
- represents the ii-th information source.
- represents the probability of the ii-th information source occurring.
3. Case Study
3.1. Hierarchical Task Analysis
3.2. Complexity Measurement
4. Experimental Validation
4.1. Comparison of Task Complexity and NASA-TLX Scores
4.2. Comparison of Task Complexity and Operation Time
4.3. Analysis and Discussion
5. Summary and Prospects
Author Contributions
Funding
Institutional Review Board Statement
Data Availability Statement
Conflicts of Interest
Appendix A
Step | Task Content |
---|---|
1 | Confirm reactor trip |
2 | Check if the safety injection is activated |
3 | Confirm the isolation of feed-water |
4 | Confirm the operation of the auxiliary feed-water pump |
5 | Confirm the operation of the following equipment |
6 | Check whether the main steam pipeline should be isolated |
7 | Confirm that no containment spray is required |
8 | Confirm the safety injection flow rate |
9 | Confirm that the total flow rate of the auxiliary feed-water is normal |
10 | Check the pressurizer relief valve and spray valve |
11 | Check whether the main feed-water pump has stopped |
12 | Check whether the secondary side of the steam generator has a fault |
13 | Check whether the heat-transfer tubes of the steam generator are ruptured |
14 | Check the following pressures are normal |
15 | Check whether the secondary side pressure of the intact steam generator should be reduced to the system pressure |
16 | Check whether the main system is intact |
17 | Check the state of the pressurizer relief valve and its isolation valve |
18 | Check whether the safety injection can be terminated |
19 | Safety injection reset, containment ventilation isolation reset |
20 | Stop one high-pressure safety injection pump |
21 | Depressurize the main system to refill the pressurizer |
22 | Check whether one main pump should be started |
23 | Check whether one safety injection pump can be stopped |
24 | Check whether normal charging can be established |
25 | Establish normal charging and maintain the pressurizer water level |
26 | Check the operation status of the main pump |
27 | Confirm that no more safety injection flow is required |
28 | Check whether the safety injection tank should be isolated |
29 | Continuously cool and depressurize the main system |
30 | Continuously monitor the main system pressure and the pressurizer water level |
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Interaction Component | Abbreviation | Interactive Actions | Interactive Functionality Description |
---|---|---|---|
Valve | V | Click | Clicking the valve opens the operation window to perform related tasks |
Pump | P | Click | Clicking the pump opens the operation window to perform related tasks |
Controller | Ckg | Click | Clicking the controller opens the operation window to perform related tasks |
Cku | Click | ||
Ckc | Click | ||
Navigation Icons | NI | Click | Click the navigation window icon to enter the system screen after powering on |
Shortcut Navigation Icons | SNI | Click | The quick navigation icon enables fast screen transitions within the system with a single click |
Execute Button | EB | Click | By clicking, confirm the execution of the operation |
Exit Button | EXB | Click | Exit the window by clicking |
Input Box | IB | Double-click | Select the window by double-clicking to enter data |
Keyboard | Kbd | Input | Enter data by typing |
Information Panels | IP | Check | Retrieve information by visual inspection |
Operation Window | OW | A secondary window superimposed over the system interface for the operation of related components | |
System Window | SW | System screen | |
Reset Button | RB | Long press | Perform the reset operation of the related components by long-pressing |
Switch Button | SB | Long press | Perform the on/off action of the related components by long-pressing |
M/A Button | MAB | Click | Toggling between automatic and manual modes for the component |
signal indicator light | SL | Check | “Determine system status by checking the signal lights.” |
Graph (a) | Class | Graph (b) | ||||
---|---|---|---|---|---|---|
In | Out | Node | In | Out | Node | |
0 | 2 | a | I | 0 | 2 | a |
1 | 1 | b,c,d,e | II | 1 | 1 | b,d,e |
2 | 2 | d | III | 1 | 2 | c |
2 | 0 | g | IV | 2 | 1 | f |
2 | 0 | g |
Graph (a) | Class | Graph (b) | ||
---|---|---|---|---|
Node | Neighbor Node | Node | Neighbor Node | |
a | b,c | I | a | b,c |
b,c | a,d | II | b | a,g |
d | b,c,e,f | III | c | a,d,c |
e,f | d,g | IV | d,e | c,f |
g | e,f | V | f | d,e,g |
VI | g | b,f |
Action or Expected Response | Unintended Response |
---|---|
Step 23: Check if a train of safety injection pumps can be stopped | |
a. Check the safety injection pumps-running | a. Execute Step 24 |
b. Determine the sub-cooling at the reactor core outlet required for pump shutdown according to Table XX | |
c. Reactor core outlet sub-cooling-greater than the sub-cooling required by Table XX | c. Execute Step 27 |
d. Pressurizer water level-greater than 2.0 m | d. Do not stop the safety injection pump and return to Step 21 |
e. Stop a train of safety injection pumps | |
f. Return to Step 23 a | |
Step 24: Check if normal charging can be established | |
a. Check the following items: | a. Execute Step 27 |
- All safety injection pumps are stopped | |
- Centrifugal charging pump: one in operation and one on standby | |
b. Reactor core outlet sub-cooling-greater than 20°C | b. If the reactor core outlet sub-cooling is less than 20 °C, start a high-pressure safety injection pump |
c. Pressurizer water level-greater than 2 m | c. Return to Step 21 |
Step 25: Establish normal charging and maintain the pressurizer water level | |
a. Place the RRA to RCV flow control valve in manual | |
b. Check if the safety injection has been reset | b. Manually reset the safety injection |
c. Manually fully open the charging valve | |
d. Check the status of the following valves: | d. Restore the valves to the correct status |
- Minimum flow valve of the charging pump-open | |
- Charging line isolation valve-open | |
- Boron injection isolation valve-closed | |
e. Adjust the charging flow to maintain the pressurizer water level |
Task Information | Operator Actions | Components and Information |
---|---|---|
1. Place the flow—control valve for RRA to RCV in manual mode. | 1. Switch the valve to manual. | Valve: Data type B |
2. Check if the safety injection has been reset. | 2. Confirm that the safety-injection signal is cut off. | Signal indicator light: Data type B |
3. Manually fully open the charging valve. | 4.1 Set the charging valve to manual mode. 4.2 Adjust the charging-flow data. | Operating mode: Data type B Valve: Data type B |
4. Check the status of the following valves. | 4.1 Check that the minimum-flow pipeline isolation valve of the charging pump is in the open state. 4.2 Check that the charging-line isolation valve is in the open state. 4.3 Check that the boric-acid injection isolation valve is in the closed state. | Valve: Data type B Valve: Data type B Valve: Data type B |
5. Adjust the charging flow to maintain the pressurizer water level. | 5. Adjust the flow of the charging-flow valve and constantly monitor the pressurizer water level. | Charging flow: Data type P (process variable) Pressurizer water level: Data type P (process variable) |
Step | TIC | TLC | TSC | TEC | Step | TIC | TLC | TSC | TEC |
---|---|---|---|---|---|---|---|---|---|
1 | 0.566 | 0.590 | 1.991 | 0.464 | 16 | 1.006 | 1.928 | 1.991 | 0.521 |
2 | 0.201 | 0.690 | 1.406 | 0.173 | 17 | 2.164 | 1.928 | 2.396 | 1.953 |
3 | 1.668 | 2.874 | 2.724 | 1.568 | 18 | 3.417 | 2.500 | 4.308 | 2.715 |
4 | 0.820 | 0.983 | 1.298 | 0.588 | 19 | 0.566 | 0.590 | 1.991 | 0.775 |
5 | 1.556 | 1.928 | 2.530 | 1.376 | 20 | 1.931 | 2.518 | 2.141 | 1.145 |
6 | 1.668 | 2.500 | 2.413 | 1.769 | 21 | 2.371 | 2.591 | 2.413 | 2.820 |
7 | 1.899 | 3.021 | 2.044 | 0.641 | 22 | 2.558 | 3.121 | 2.860 | 1.385 |
8 | 2.371 | 2.874 | 1.991 | 1.067 | 23 | 2.558 | 2.545 | 2.234 | 2.347 |
9 | 0.000 | 0.978 | 1.296 | 0.051 | 24 | 2.371 | 1.398 | 2.640 | 1.037 |
10 | 2.001 | 1.398 | 1.991 | 0.558 | 25 | 3.322 | 3.121 | 4.434 | 3.523 |
11 | 2.371 | 2.152 | 2.413 | 2.102 | 26 | 0.566 | 0.590 | 0.000 | 1.124 |
12 | 0.891 | 1.928 | 2.389 | 0.508 | 27 | 2.164 | 2.152 | 1.991 | 0.096 |
13 | 2.371 | 0.859 | 2.234 | 1.174 | 28 | 1.668 | 0.000 | 2.530 | 1.357 |
14 | 1.931 | 1.398 | 2.141 | 1.441 | 29 | 2.371 | 0.768 | 1.860 | 0.793 |
15 | 4.468 | 3.948 | 4.807 | 3.971 | 30 | 1.006 | 0.590 | 0.196 | 0.000 |
Step | NASA-TLX | STC | Step | NASA-TLX | STC |
---|---|---|---|---|---|
1 | 59.86 | 0.56 | 16 | 48.22 | 0.74 |
2 | 39.55 | 0.40 | 17 | 59.28 | 1.06 |
3 | 65.50 | 1.13 | 18 | 72.10 | 1.67 |
4 | 41.07 | 0.49 | 19 | 41.67 | 0.58 |
5 | 44.85 | 0.95 | 20 | 58.25 | 0.99 |
6 | 42.58 | 1.05 | 21 | 64.52 | 1.28 |
7 | 53.28 | 1.02 | 22 | 60.05 | 1.27 |
8 | 71.10 | 1.07 | 23 | 72.52 | 1.21 |
9 | 44.17 | 0.40 | 24 | 62.58 | 1.00 |
10 | 52.32 | 0.81 | 25 | 76.93 | 1.83 |
11 | 69.32 | 1.14 | 26 | 43.48 | 0.35 |
12 | 59.90 | 0.80 | 27 | 56.52 | 0.91 |
13 | 63.97 | 0.91 | 28 | 62.53 | 0.85 |
14 | 57.07 | 0.89 | 29 | 58.02 | 0.82 |
15 | 80.55 | 2.17 | 30 | 40.88 | 0.30 |
Index | Mean | Standard Deviation | Lower Limit of 95% Confidence Interval | Upper Limit of 95% Confidence Interval |
---|---|---|---|---|
NASA-TLX score | 57.42 | 11.61 | 53.08 | 61.75 |
Operation time | 44.47 | 34.48 | 31.59 | 57.35 |
Model | Degrees of Freedom | F | Significance | R | R2 |
---|---|---|---|---|---|
Regression | 1 | 59.281 | 0.001 | 0.824 | 0.678 |
Residual | 28 | ||||
Total | 29 |
Step | Operation Time (unit:S) | STC | Step | Operation Time (unit:S) | STC |
---|---|---|---|---|---|
1 | 14.23 | 0.56 | 16 | 22.55 | 0.74 |
2 | 8.20 | 0.40 | 17 | 26.74 | 1.06 |
3 | 36.65 | 1.13 | 18 | 74.33 | 1.67 |
4 | 18.74 | 0.49 | 19 | 21.48 | 0.58 |
5 | 34.86 | 0.95 | 20 | 66.34 | 0.99 |
6 | 44.64 | 1.05 | 21 | 67.45 | 1.28 |
7 | 20.12 | 1.02 | 22 | 48.96 | 1.27 |
8 | 69.34 | 1.07 | 23 | 83.44 | 1.21 |
9 | 15.67 | 0.40 | 24 | 48.69 | 1.00 |
10 | 28.74 | 0.81 | 25 | 135.59 | 1.83 |
11 | 63.41 | 1.14 | 26 | 18.86 | 0.35 |
12 | 16.40 | 0.80 | 27 | 21.44 | 0.91 |
13 | 49.48 | 0.91 | 28 | 59.97 | 0.85 |
14 | 14.56 | 0.89 | 29 | 43.45 | 0.82 |
15 | 150.89 | 2.17 | 30 | 9.00 | 0.30 |
Model | Degrees of Freedom | F | Significance | R | R2 |
---|---|---|---|---|---|
Regression | 1 | 96.706 | 0.001 | 0.880 | 0.785 |
Residual | 28 | ||||
Total | 29 |
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Pang, E.; Dai, L. Research on Task Complexity Measurements in Human—Computer Interaction in Nuclear Power Plant DCS Systems Based on Emergency Operating Procedures. Entropy 2025, 27, 600. https://doi.org/10.3390/e27060600
Pang E, Dai L. Research on Task Complexity Measurements in Human—Computer Interaction in Nuclear Power Plant DCS Systems Based on Emergency Operating Procedures. Entropy. 2025; 27(6):600. https://doi.org/10.3390/e27060600
Chicago/Turabian StylePang, Ensheng, and Licao Dai. 2025. "Research on Task Complexity Measurements in Human—Computer Interaction in Nuclear Power Plant DCS Systems Based on Emergency Operating Procedures" Entropy 27, no. 6: 600. https://doi.org/10.3390/e27060600
APA StylePang, E., & Dai, L. (2025). Research on Task Complexity Measurements in Human—Computer Interaction in Nuclear Power Plant DCS Systems Based on Emergency Operating Procedures. Entropy, 27(6), 600. https://doi.org/10.3390/e27060600