Analysis of Doppler coefficients for typical PWR UO2 and MTR U3Si2-Al fuels using ENDF/B-VI and VII

Kim, Kyung-O; Jo, Daeseong

doi:10.1016/j.anucene.2015.07.021

Cited by 5 publications

(3 citation statements)

References 7 publications

(3 reference statements)

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“…The safety performance of accident-tolerant cladding materials can be expressed in terms of the temperature coefficient of reactivity, αF, shown in Equation 2. The term αF represents the change in reactivity per unit change in fuel temperature (Kim and Jo, 2015).…”

Section: Methodsmentioning

confidence: 99%

Accident Tolerant Fuel Cladding Materials for Light Water Reactors: Analysis of Neutronic Characteristics

Aziz,

Rivai,

Panitra

et al. 2024

IJTech

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Nuclear reactor fuel is the basic component of all safety requirements associated with nuclear energy production. The neutronic characteristics of light water reactors with candidate accident-tolerant fuel cladding materials were investigated in this work to improve nuclear safety. The materials were chosen for their high-temperature strength, radiation resistance, and corrosion resistance, which will contribute to nuclear safety. The research was conducted using a deterministic neutronic code for reactor design and analysis. The neutronic properties of a light water reactor system with candidate cladding materials were analyzed and compared to those of the reference. The reference cladding material was Zircaloy-4, and the candidate fuel cladding materials examined were FeCrNi alloy, oxide dispersion strengthened steels of FeCrY2O3 and FeCrZrO2. The eigenvalues of the reactor were computed at various fuel temperatures and burnup stages. The results of the study revealed that employing candidate cladding materials led to a slightly hardened neutron spectrum, reducing initial excess reactivity and resulting in lower fuel burnup. This can be compensated by adding fuel enrichment up to 6%., which yields burnup value of 42000 MWd/T, which is higher than the reference of 40000 MWd/T with a reduced gap in initial excess reactivity from 28.4% to 25.4%. The candidate fuel cladding materials also showed better than reference reactivity loss properties in case of unwanted temperature increase. This demonstrated that the examined improved tolerant materials have the ability to increase the inherent safety of nuclear reactors.

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Section: Methodsmentioning

confidence: 99%

Accident Tolerant Fuel Cladding Materials for Light Water Reactors: Analysis of Neutronic Characteristics

Aziz,

Rivai,

Panitra

et al. 2024

IJTech

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“…Ordinary concrete contains more oxygen and silicon while heavy concrete contains more iron and barium. Compared to oxygen and silicon, the iron and barium elements have greater neutron cross-section [11][12][13] and higher density, thus their ability as a radiation shielding is much better. But heavy concrete is more expensive, so it is necessary to determine the optimal combination of shielding substances and dimensions.…”

Section: Theorymentioning

confidence: 99%

Evaluation of Radiation Dose Rate of RSG-Gas Reactor

Hamzah

Adrial

Subiharto

2018

urania

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EVALUATION OF RADIATION DOSE RATE OF RSG-GAS REACTOR. The RSG-GAS reactor has been operated for 30 years. Since the nuclear reactor has been operated for a long time, aging process on its components may occur. One important parameter for maintaining the safety level of the RSG-GAS reactor is to maintain radiation exposure as low as possible, especially in the working area. The evaluation results should be able to demonstrate that the radiation exposure of the RSG-GAS is still safe for workers, communities and the surrounding environments. The purpose of this study is to evaluate radiation exposure in the working area to ensure that the operation of RSG-GAS is still safe for the next 10 years. The scope of this work is confirming the calculation results with the measured radiation dose in the RSG-GAS reactor working area. Measurement of radiation exposure is done by using the installed equipments at some points in the RSG-GAS working area and a portable radiation exposure measurement equipment. The calculations include performance of a modeling and analysis of dose rate distribution based on the composition and geometry data of RSG-GAS by using MCNP. The analysis results show that the maximum dose rate at Level 0 m working area of RSG-GAS reactor is 3.0 mSv/h with a deviation of 6%, which is relatively close to the measurement value. The evaluation results show that the dose rate in RSG-GAS working area is below the limit value established by the Nuclear Energy Regulatory Agency of Indonesia (BAPETEN) of 10 mSv/h (for the average effective dose of 20 mSv/year). Therefore, it is concluded that the dose rate in RSG-GAS working area is safe for personnel..Kata kunci: dose rates, RSG-GAS, radiation safety, MCNP.

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“…Researchers have calculated the temperature effects in HFP, HZP, and CZP states by using NODAL3 and SRAC software, Serpent, and MCNP software [6][7][8]. Another scholar studied the Doppler effect of fuels at different temperatures [7][8][9][10][11]. However, most of the previous studies do not take into account the positive and negative reactivity coefficients of AP1000 cores at high temperatures.…”

Section: Introductionmentioning

confidence: 99%

Research on Neutronics Safety Parameters of the AP1000 Nuclear Reactor under Different Conditions

Niu,

Liu,

Dong

et al. 2023

Energies

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Changes in temperature during reactor operation may cause changes in physical parameters, leading to core overheating and accidents. It is essential to analyze and assess the safety parameters of the core under different operating conditions. This paper investigates the effects of fuel temperature, moderator density, boron concentration, and control rod state on AP1000 safety parameters. The study uses RMC and NJOY to calculate the changes in reactivity factor, effective delayed neutron fraction, and neutron generation time of the AP1000 reactor under different operating conditions. The changes in reactivity coefficients, neutron fluxes, and relative power densities of AP1000 reactors are analyzed for normal and accidental operating conditions. The results indicated that the reactivity coefficient remained negative under accident conditions, which ensured the safe operation of the reactor. The delayed neutron fraction, neutron flux, and power density distributions are affected by fuel temperature, moderator density, and control rod position. The control rod worth was sufficient for the emergency shutdown of the reactor under accidental conditions. It is demonstrated that the operation of the AP1000 reactor under study conditions is safe and controllable.

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Analysis of Doppler coefficients for typical PWR UO2 and MTR U3Si2-Al fuels using ENDF/B-VI and VII

Cited by 5 publications

References 7 publications

Accident Tolerant Fuel Cladding Materials for Light Water Reactors: Analysis of Neutronic Characteristics

Accident Tolerant Fuel Cladding Materials for Light Water Reactors: Analysis of Neutronic Characteristics

Evaluation of Radiation Dose Rate of RSG-Gas Reactor

Research on Neutronics Safety Parameters of the AP1000 Nuclear Reactor under Different Conditions

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