Analysis of AP1000 Small-Break Loss-of-Coolant Accident Using Reactor Transient Simulator
Author:
Affiliation:
1. University of Idaho, 1776 Science Center Drive, Idaho Falls, Idaho 83402
2. Idaho National Laboratory, 2525 Fremont Avenue, Idaho Falls, Idaho 83415-2209
Funder
U.S. Department of Energy Advanced Reactor Demonstration Project
Risk Reduction Pathway
Publisher
Informa UK Limited
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295450.2024.2342168
Reference36 articles.
1. “Westinghouse AP1000 Design Control Document Rev. 19 ” Westinghouse Electric Company; https://www.nrc.gov/docs/ML1117/ML11171A500.html (accessed Nov. 5 2023).
2. Westinghouse AP1000 advanced passive plant
3. SIMULATED AP1000 RESPONSE TO DESIGN BASIS SMALL-BREAK LOCA EVENTS IN APEX-1000 TEST FACILITY
4. Simulation and analysis on 10-in. cold leg small break LOCA for AP1000
5. Modeling of AP1000 and simulation of 10-inch cold leg small break LOCA using the CESAR thermal-hydraulic module of ASTEC
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