The implication of Thorium fraction on neutronic parameters of pebble bed reactor

Zuhair, Zuhair; Dwijayanto, R. Andika Putra; Suwoto, Suwoto; Setiadipura, Topan

doi:10.48129/kjs.v48i3.9984

Cited by 13 publications

(5 citation statements)

References 13 publications

(1 reference statement)

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“…The structural components of the reactor core such as graphite reflectors were easily modeled while the coolant in the reflector side and especially, the reactor shutdown and control systems require special effort in modeling. The modeling and calculations performed in this study were demonstrated successfully in various publications [11][12][13][14][15][16][17][18][19][20][21][22].…”

Section: Pebbles In Core Modelingmentioning

confidence: 76%

Effects of Fuel Density on Reactivity Coefficients and Kinetic Parameters of Pebble Bed Reactor

Suwoto¹,

Dwijayanto²,

Luthfi³

et al. 2022

urania

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EFFECTS OF FUEL DENSITY ON REACTIVITY COEFFICIENTS AND KINETIC PARAMETERS OF PEBBLE BED REACTOR. Few decades ago a large number of nuclear reactors were designed to use HEU as the fuel. But the use of HEU is being discouraged since it can be used as a nuclear explosive material which makes its proliferation potential. Most of the HEU-fueled nuclear reactors in the world are either closed or converted into other types that have LEU fuel with 235U enrichment below 20%. To extend lifetime, LEU fuel with high density is developed. The change in fuel density from low to high will also change core neutronics and thermal-hydraulics of the reactor, and as a result, it affects the transient response of the reactor. This paper studies the effects of fuel density on reactivity coefficients and kinetic parameters of pebble bed reactor through several calculations with MCNP6 code combine with ENDF/B-VII.1 continuous energy cross-section nuclear data library. The overall calculation results show that the Doppler temperature coefficient (DTC) increases with increasing fuel density, but the moderator temperature coefficient (MTC) decreases due to hardening of neutron spectrum. Kinetic parameters such as effective delayed neutron fraction (βeff), prompt neutron lifetime(ℓ) and neutron generation time (Ʌ) which significantly reduced with increasing fuel density will strongly affect the reactor control and safety. The results of this work conclude that the selection of 9–15 g/cm3 fuel density should be considered carefully given that its effect on reactor controllability.Keywords: Fuel density, reactivity coefficients, kinetic parameters, MCNP6, ENDF/B-VII.1.

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Section: Pebbles In Core Modelingmentioning

confidence: 76%

Effects of Fuel Density on Reactivity Coefficients and Kinetic Parameters of Pebble Bed Reactor

Suwoto¹,

Dwijayanto²,

Luthfi³

et al. 2022

urania

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“…To obtain these values, a neutronic simulation was performed using the MCNP6.2 radiation transport code with the ENDF/B-VII.0 neutron cross-section library. MCNP is a well-established code for simulating the neutronic aspects of nuclear reactors and has been extensively used for various types of reactors [25][26][27][28][29][30]. Although MCNP may not be the most suitable simulation tool for MSR due to its decoupling from thermal-hydraulic calculations, it has nonetheless been used for simulating various MSR designs, such as MSBR [6,31,32], MSR-FUJI [9], TMSR-500 [33][34][35], and Integral Molten Salt Reactor (IMSR) [36], with good agreement to the reference.…”

Section: Methodsmentioning

confidence: 99%

Neutronic Design Modification of Passive Compact-Molten Salt Reactor

Dwijayanto,

Harto

2024

Atom Indo.

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Passive compact molten salt reactor (PCMSR) is a design concept of a molten salt reactor (MSR) currently under development in Universitas Gadjah Mada, Indonesia. It is designed as a thermal breeder reactor using thorium fuel cycle. However, our previous study shows that the original PCMSR design was incorrectly modelled, primarily overestimating its thorium breeding capability. To improve PCMSR neutronic design, we modified the core configuration by the addition of radial fuel channel layers previously nonexistent in original PCMSR core design in various configurations. Neutronic parameters of modified PCMSR geometries in the beginning of life (BOL) were simulated using MCNP6.2 radiation transport code with ENDF/B-VII.0 library. All variations of fuel layer addition show improvement in both temperature coefficient of reactivity (TCR) and breeding ratio (BR), with TCR values became more negative and BR values are larger than unity, ensuring proper breeding capability. Configuration Inner Core-Outer Blanket (IC-OB) achieves the largest BR and lowest doubling time (DT), whilst its TCR is an improvement from the original design. Therefore, IC-OB fuel layer configuration can be applied to redesign the original PCMSR and used in various design optimization scenarios.

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“…One of the advantages of the Monte Carlo method is to focus on the nuclear uncertainties by reducing the errors related to modeling and design. The critical coefficients (Keff and RTC) for KRITZ-2:13 were calculated by the card KCODE from the code MCNP6.1, which offers complex geometry modeling capabilities with high accuracy 3-D calculations of the physical system [18].…”

Section: Critical Calculationsmentioning

confidence: 99%

Cross sections Data Adjustment For KRITZ-2:13

Ahmed

Boukhal

Chakir

et al. 2021

KJS publishes peer-review articles in Mathematics, Computer Sci

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Over the past years, the cross-sections reaction data has been re-evaluated several times, in order to approximate the nuclear model measurements with the predictions with great reliability. In our work, uncertainty analysis caused by the data on the neutron factor (Keff) and the reactivity temperature coefficient (RTC), in addition to nuclear data adjustment related to the nuclear reactor physics have been done for KRITZ-2:13 reactor, with ENDF/B - VII.1, ENDF/B - VIII.0 and JENDL - 4.0 evaluations by the nuclear code MCNP6.1. Our analysis detects that the greatest uncertainty on Keff and RTC in the studied libraries comes from the capture and fission reaction contributions respectively, for U-238 and U-235. The previous reactions and their covariances were adjusted using the generalized least squares method (GLLSM), in order to contribute to improve the data needed for neutron simulation of experiments and to ensure the installations safety, where Keff and RTC represent neutron parameters reflecting the modification effects in the data.

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The implication of Thorium fraction on neutronic parameters of pebble bed reactor

Cited by 13 publications

References 13 publications

Effects of Fuel Density on Reactivity Coefficients and Kinetic Parameters of Pebble Bed Reactor

Effects of Fuel Density on Reactivity Coefficients and Kinetic Parameters of Pebble Bed Reactor

Neutronic Design Modification of Passive Compact-Molten Salt Reactor

Cross sections Data Adjustment For KRITZ-2:13

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