Measurement and simulation of thermal neutron flux distribution in the RTP core

Rabir, Mohamad Hairie; Bayar, Abi Muttaqin B. Jalal; Hamzah, Naim Syauqi; Mustafa, Muhammad Khairul Ariff; Karim, Julia Abdul; Zin, Muhammad Rawi B. Mohamed; Ismail, Yahya B.; Hussain, Mohd Huzair; Husin, Mat Zin B. Mat; Dan, Roslan B. Md; Ismail, Ahmad Razali; Husain, Nurfazila Bt.; Khan, Zareen Khan B. Abdul Jalil; Yakin, Shaiful Rizaide B. Mohd; Saad, Mohamad Fauzi; Masood, Zarina

doi:10.1088/1757-899x/298/1/012029

Cited by 4 publications

(3 citation statements)

References 2 publications

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“…However, by referring to the control rod worth behaviour graph for RTP in [41], both conventional CRSA and SCAR have almost identical total of reactivity worth value which is $8.498. Total maximum reactivity worth value to fully liftup all the control rods (at 381 mm) is about $13.144.…”

Section: Experimental Setup Results and Discussionmentioning

confidence: 99%

“…The advantage of this conventional CRSA is to minimize the moving distance of each control rod or known as balancing position control rod method. However, it suffers during transient and fine-tuning in steady-state to regulate reactor power due to differences in control rod worth value for each control rod at RTP and can be found in [41].…”

Section: Control Rod Selection Algorithm (Crsa)mentioning

confidence: 99%

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An improved control rod selection algorithm for core power control at TRIGA PUSPATI Reactor

Minhat

Subha

Hassan

et al. 2020

JMES

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The 1 MWth TRIGA PUSPATI Reactor known as RTP undergoes more than 37 years of operation in Malaysia. The current core power control utilized Feedback Control Algorithm (FCA) and a conventional Control Rod Selection Algorithm (CRSA). However, the current power tracking performance suffers and increase the workload on Control Rod Drive Mechanism (CRDM) if the range between minimum and maximum rod worth value for each control rod has a significant difference. Thus, it is requiring much time to keep the core power stable at the power demand value within the acceptable error bands for the safety requirement of the RTP. In conventional CRSA, regardless of the rod worth value, the lowest position of the control rod is selected for up-movement to regulate the reactor power with 2% chattering error. To improve this method, a new CRSA is introduced named Single Control Absorbing Rod (SCAR). In SCAR, only one rod with highest reactivity worth value will be selected for coast tuning during transient and the lowest reactivity worth value will be selected for fine-tuning rod movement during steady-state. The simulation model of the reactor core is represented based on point kinetics model, thermal-hydraulic models and reactivity model. The conventional CRSA model included with control rod position dynamic model and actual reactivity worth curve data from RTP. The FCA controller is designed based on Proportional-Integral (PI) controller using MATLAB Simulink simulation. The core power control system is represented by the integration of a reactor core model, CRSA model and FCA controller. To manifest the effectiveness of the proposed SCAR algorithm, the results are compared to the conventional CRSA in both simulation and experimentation. Overall, the results shows that the SCAR algorithm offers generally better results than the conventional CRSA with the reduction in rising time up to 44%, workload up to 35%, settling time up to 26% and chattering error up to 18% of the nominal value.

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Section: Experimental Setup Results and Discussionmentioning

confidence: 99%

Section: Control Rod Selection Algorithm (Crsa)mentioning

confidence: 99%

An improved control rod selection algorithm for core power control at TRIGA PUSPATI Reactor

Minhat

Subha

Hassan

et al. 2020

JMES

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“…2.7 has been studied on how far neutron flux gave the impart burn-up effect onto irradiated fuel [11]. In other study, thermal neutron flux distribution by using Monte Carlo code MCNP was examined the agreement between calculation and measurement to be met [12]. Meanwhile, both TRIGLAV and MCNP code has been used in investigation of the design and verification for RTP core by manipulation neutron flux calculation [13].…”

Section: Introductionmentioning

confidence: 99%

TRIGA PUSPATI reactor: model analysis and accuracy

Abdullah

Soh

Noor

et al. 2020

IJEECS

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<p>There are many challenging issues with research reactor, such as time variation and uncertainty. Since its first criticality in 1982, the biggest changes in TRIGA PUSPATI Reactor system is the replacement of instrumentation and control console system from analogue to digital in 2013. Apart from providing methods of controlling the power reactor via the control rod movement, the Instrumentation and Control Console System also provides monitoring and display for all reactor parameters to protect the reactor from undue influences or abnormal circumstances. Meanwhile, the simulation model of the TRIGA PUSPATI Reactor system has been developed in the Simulink-MATLAB. The simulation model development is based on the research reactor mathematical representatives and the real plant parameters of TRIGA PUSPATI Reactor. However, the performance of this simulation model needs to be evaluated. Since there is no report or paper work found on the performance of the simulation model to represent the real system of RTP, the present study aims to carry out an analysis for more rigorous understanding of the TRIGA PUSPATI Reactor model simulation through validation and verification methods. After analysing the result, it was found that the simulation model has a good representation of a real plant.</p>

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