Transient analyses of the Jordanian 5 MW research reactor under LOEP accident

Al-Yahia, Omar S.; Lee, Ho; Jo, Daeseong

doi:10.1016/j.anucene.2015.10.021

Cited by 8 publications

(2 citation statements)

References 10 publications

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“…e coolant flows downward at a rate of 170 kg/s, with an inlet temperature of around 37°C and exits the core with an outlet temperature of 44.2°C. e average heat flux is 17.3 W/cm 2 , with a maximum of 51.9 W/cm 2 , and the power peaking factor is 2.54 [14][15][16][17]. e main design characteristics of the JRTR reactor are listed in Table 1.…”

Section: Reactor Descriptionmentioning

confidence: 99%

Source Term Derivation and Radioactive Release Evaluation for JRTR Research Reactor under Severe Accident

Xoubi

2020

Science and Technology of Nuclear Installations

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The source term for the JRTR research reactor is derived under an assumed hypothetical severe accident resulting in generation of the most severe consequences. The reactor core is modeled based on the reactor technical design specifications, and the fission products inventory is calculated by using the SCALE/TRITON depletion sequence to perform burnup and decay analyses via coupling the NEWT 2-D transport lattice code to the ORIGEN-S fuel depletion code. Fifty radioisotopes contributed to the evaluation, resulting in a source term of 3.7 × 1014 Bq. Atmospheric dispersion was evaluated using the Gaussian plume model via the HOTSPOT code. The plume centerline total effective dose (TED) was found to exceed the IAEA limits for occupational exposure of 0.02 Sv; the results showed that the maximum dose is 200 Sv within 200 m from the reactor, under all the weather stability classes, after which it starts to decrease with distance, reaching 0.1 Sv at 1 km from the reactor. The radiation dose plume centerlines continue to the exceed international basic safety standards annual limit of 1 mSv for public exposure, up to 80 km from the reactor.

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Section: Reactor Descriptionmentioning

confidence: 99%

Source Term Derivation and Radioactive Release Evaluation for JRTR Research Reactor under Severe Accident

Xoubi

2020

Science and Technology of Nuclear Installations

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“…Excessive insertion of reactivity can cause accidents leading to fuel clad meltdown. In the past, many researchers conducted analysis on the reactivity insertion accidents (RIA) under controlled and un-controlled conditions, and they compiled the results in safety analysis reports [9][10][11][12].…”

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confidence: 99%

Safety Analysis of the TRIGA 2000 U3Si2-Al Fuel Core Under Reactivity Insertion Accidents

2020

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The TRIGA 2000 reactor in Bandung is planned to change its fuel type from the TRIGA fuel rod type to the U 3 Si 2-Al plate type of low enriched uranium of 19.75 % with uranium density of 2.96 gU/cc. A study on the neutronic parameters from the equilibrium core has been done. To ensure safe operation of the new fuel, thermodynamic evaluation of the core needs to be done. The purpose of this study is to conduct a reactor safety analysis of reactivity insertion during withdrawal of the control rod and to study the effect of this reactivity insertion on the power and the maximum temperature of the fuel and the cladding. Reactivity insertion accident is the main factor of the design basis accidents in nuclear reactor design. A simulation of transient for reactivity insertion has been carried out using a coupled neutronic and thermal-hydraulic MTR-DYN code. The code was developed based on threedimensional multigroup neutron diffusion theory. The coupled space and timedependent problem were solved by adiabatic model. Transient analysis was performed for a reactivity insertion of 32.33 pcm/s with the assumption that all of the control rods were rapidly withdrawn. For the insertion at a low power of 100 W, the maximum power achieved was 2.74 MW while a maximum power of 2.3 MW was achieved for the power transient of 1 MW. The maximum temperature of the coolant, the cladding, and the fuel for TRIGA 2000 core does not exceed the allowable safety limit for reactivity insertions.

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Preliminary study on thermal–hydraulic behavior of loss-of-flow accident in deep pool-type nuclear reactor

Wang

Yue

Sun

et al. 2022

Annals of Nuclear Energy

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Transient analyses of the Jordanian 5 MW research reactor under LOEP accident

Cited by 8 publications

References 10 publications

Source Term Derivation and Radioactive Release Evaluation for JRTR Research Reactor under Severe Accident

Source Term Derivation and Radioactive Release Evaluation for JRTR Research Reactor under Severe Accident

Safety Analysis of the TRIGA 2000 U3Si2-Al Fuel Core Under Reactivity Insertion Accidents

Preliminary study on thermal–hydraulic behavior of loss-of-flow accident in deep pool-type nuclear reactor

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