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Session Chair: Belle Upadhyaya, University of Tennessee, Knoxville, United States of America Session Chair: Bassam Khuwaileh, University of Sharjah, United Arab Emirates
Introduction of PCTRAN/ACP100 - A PC-based Simulator for the Chinese Small Modular Reactor ACP100
Li-Chi Cliff Po1, Belle Upadhyaya2, Bassam Abdullah Ayed Khuwaileh3, Huifang Miao4
1Micro-Simulation Technology; 2University of Tennessee at Knoxville; 3Sharjah University; 4Xiamen University
ACP100 is designed by China Central Nuclear Power Corporation – a 330 MW thermal pressurized water reactor with integral steam generators and passive core and containment cooling systems. In 2016 IAEA issued the world first final safety review report for the SMR. The unit can generate 100 MW electric, provide 450 t/h district heating and up to 120,000 t/day fresh water. Based on technical information published in the public domain, we have developed a PC-based simulator for training and education. Our PCTRAN/ACP100 has an integral reactor vessel containing 16 once-through steam generators (OTSG) lumping into two, a pressurizer, pressure relief valves for the Automated Depressurization System (ADS), in-containment water tank, core makeup tank, accumulator, steel shell containment and passive residual heat removal system (PRHR) outside the containment. The basic specifications are:
Thermal power 310 MWt
Electric power 100 MWe
Coolant inlet temperature 281˚ C
Coolant outlet temperature 324˚ C
Operation pressure 15 MPa
SG pressure 4 MPa
Fresh water production 120,000 tons/day
Steady states at various power levels can be reached by manual or automatic controls. In addition to electrical power generation, portion of the steam is used for sea water desalination via MED/TVC (Multiple-stage Evaporation Desalination/Thermal Vapor Compression) units. Accident for loss of co0lant accident is mitigated by automatic reactor scram, initiation of the core makeup tank and accumulator. A station blackout (SBO) for losing both AC and DC power is further cooled down by the passive residual heat removal (PRHR) system by opening the OTSG secondary steam and condensate return valve. Natural circulation removes the core decay up to three days. The simulator can be used for training and education of the SMR.
A Five-Year Soluble Boron Free iPWR Core Design
Assil Anis Halimi, Koroush Shirvan
Massachusetts Institute of Technology
In order to offer long cycle capability and facilitate nuclear power supply for remote grids and developing countries, a five-year cycle core design for an integral PWR is proposed in this paper. A single batch refueling strategy is considered and a burnup of 37.4 MWD/kgU is reached with a rated thermal power of 459 MW. To expedite licensing, a standard 17x17 PWR fuel assembly is considered with below 5% enrichment. The designed core is once-through soluble boron free and is composed of 77 reduced-height fuel assemblies, where a control rod cluster is present for each fuel assembly. The commercial reactor physics package from STUDSVIK was utilized to simulate core performance. Core peaking factors were optimized by using a combination of fuel burnable poisons and different control rod material and sequence strategy. The fuel composition is further tailored in the axial direction and the assembly position is optimized within the core. The reflector material and thickness were also optimized through a parametric study. The core performance and transient behavior indicators such as Minimum Departure from Nucleate Boiling Ratio (MDNBR), maximum fuel temperatures, shutdown margins and reactivity coefficients were evaluated throughout the cycle. By leveraging the typically lower rated power density of the reference SMR core (60 kW/L) that allows to tolerate higher local peaking factors, the target of 5-year lifetime is reached. The five-year cycle length is reached assuming 2% forced outage rate and 15 days refueling outage period per cycle leading to longer maintenance schedules in comparison to existing commercial fleet.