HTR-PM fuel pebble irradiation qualification in the high flux reactor in Petten

Knol, S.; Groot, Sander de; Salama, R.V.; Best, Jonathan; Bakker, K.; Bobeldijk, I.; Westlake, J.R.; Fütterer, Michael A.; Laurie, M.; Tang, Chunhe; Liu, Rongzheng; Liu, Bing; Zhao, Hongsheng

doi:10.1016/j.nucengdes.2017.09.020

Cited by 22 publications

(8 citation statements)

References 5 publications

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“…Increasing the kernel radius value, the Keff value increases. These results indicate that the HTR fueled pebble bed reactor [12,13,14] to achieve criticality requires fuel enrichment between 7% and 15%…”

Section: Resultsmentioning

confidence: 95%

“…A total of 5000 neutrons per cycle were simulated with a criticality value estimate (Keff) of 1.0 which was chosen so that the final accumulation results were expected to approach the critical condition of a reactor. The use of Skipping 10 cycles was done before the accumulation of criticality data (Keff) of a total of 210 cycles to prevent the convergence of the source and so that the fission source can stabilize besfore Keff values are used to average the final criticality value (Keff) [3,11,12].…”

Section: Simulation Methodsmentioning

confidence: 99%

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Simulation Of Fuel Ball Dimensional Size And Uranium Enhancement For High Temperature Reactor

et al. 2020

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The purpose of this study was to examine the combined effect of enriching U-235 fuel and fuel fingers (Kernell) to determine its criticality (Keff). In this study, simulation of HTR (High Temperature Reactor) type reactors using MCNPX (Monte Carlo N eXtended Particles). The fuel used is UO2 which has a density of 10.4 gr / cm3, with impurity using 4 ppm Boron atom with Atomic B-10 fraction of 80.1% and B-11 of 19.9%. The variation of enrichment used is 7% to 15% and the fuel radius (Kernell) ranges from 160 µm to 340 µm. From the results, it was obtained that the optimum Keff occurs at 7% enrichment and the radius of the fuel of 310 µm was 1.01236.

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Section: Resultsmentioning

confidence: 95%

Section: Simulation Methodsmentioning

confidence: 99%

Simulation Of Fuel Ball Dimensional Size And Uranium Enhancement For High Temperature Reactor

et al. 2020

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“…Research reactors are used mainly as a neutron source. Worldwide, high‐performance research reactors support many scientific missions 1 (eg, neutron scattering, materials irradiation, 2 and isotopes production) to serve basic and applied research in a wide range of scientific areas (eg, biological sciences, medicine, fusion, 3 materials testing, 4 and education). In many cases, 5 a research reactor supports several of these missions , 6 which leads them differ from power reactors.…”

Section: Introductionmentioning

confidence: 99%

An algorithm for accurate modeling and simulating reactor cores with involute‐shaped fuel plates by Monte Carlo

et al. 2021

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Summary A real three‐dimensional representation of reactor core with involute fuel plates via Monte Carlo method is still lacking at the present, and usually equivalent homogeneous models of water coolants and simplified fuel plate shapes have been used. This work proposed an algorithm to simulate the reactor core composed of involute fuel plates with an explicit accurate description of its involute surfaces. The description of involute surfaces is through its governing equations. The mathematical function methods to depict the involute curves and the schemes to compute the distance between any neutron particle and an involute surface along a ray are presented and demonstrated step‐by‐step. The algorithm is realized in the Monte Carlo code and validated by the published data of a high flux isotope reactor. This study definitively provides a method to model the involute fuel plates in the Monte Carlo simulation.

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“…However, relevant informations and research results correspond to human factors required in the RDE design process were very limited. Most operational evaluation and analysis conducted were related to the neutronics and thermalhydraulics aspects [14,15]. Other analyses on the operational experience data were emphasized on the challenge due to components reliability and ageing phenomena [16,17].…”

Section: Introduction *mentioning

confidence: 99%

Reactor Operational Experience Review and Analysis Based on Un-Intended Reactor Trip Data

et al. 2019

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To enhance the safety and reliability of a new reactor, human factors should be integrated into its design process. The experimental power reactor (RDE) currently being developed in Indonesia needs to include human factors in the design process. One approach to incorporate human factors into design is by considering reactor operational experience data. This paper reviews and analyses the operational experience data of RSG-GAS reactor. The operational experience data of RSG-GAS reactor with 40,435 hours of total operation time spanning from 2003 to 2013 was used as a base in the study. In depth analysis on human factors was applied to the primary cooling system using Human Factors Analysis and Classification System-HFACS method. An amount of 289 un-intended trips were found in the observation data period. Most of un-intended trip were caused by external factors (38%). A review on the primary and secondary cooling system operational data showed that 3.11% of un-intended reactor trip occurrence causes were associated with human failure. Most suspected human failure/human error corresponds to the pump maintenance task which is classified as A action category. Analysis on the cooling system based on HFACS showed that the challenges to the human factors are related to unsafe acts, preconditions of unsafe acts, and unsafe supervision. The result reaffirm that human factors should be treated appropriately in the design of reactor equipment and operation procedure as well.Keywords: reactor operation experience, research reactor, human factors, reactor trip

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HTR-PM fuel pebble irradiation qualification in the high flux reactor in Petten

Cited by 22 publications

References 5 publications

Simulation Of Fuel Ball Dimensional Size And Uranium Enhancement For High Temperature Reactor

Simulation Of Fuel Ball Dimensional Size And Uranium Enhancement For High Temperature Reactor

An algorithm for accurate modeling and simulating reactor cores with involute‐shaped fuel plates by Monte Carlo

Reactor Operational Experience Review and Analysis Based on Un-Intended Reactor Trip Data

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