A new strategy to simulate a random geometry in a pebble-bed core with the Monte Carlo code MCNP

Kim, Hong-Chul; Kim, Song Hyun; Kim, Jong Kyung

doi:10.1016/j.anucene.2011.05.012

Cited by 19 publications

(4 citation statements)

References 1 publication

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“…By comparing the calculation results presented in Figure 5, it is known that core height of initial critically of HTR-10 used MCNP6 by Hery A et al is 125 cm while the results of VSOP package created by Jing et al is 123.57 cm [24] and the core height of criticality from KAIST by MCNP is 130.15 cm [23]. The other hand the results of initial core height resulted from criticality experiment of HTR-10 is 123.06 [25]. The inaccuracy of the results generated by the initial core height criticality with MCNP6 against to expriment is 1.58%.…”

Section: Resultsmentioning

confidence: 96%

GAMMA DOSE RATE ANALYSIS IN BIOLOGICAL SHIELDING OF HTGR-10 MWth PEBBLE-BED REACTOR

Adrial

Hamzah²,

Hartini³

2019

urania

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GAMMA DOSE RATE ANALYSIS IN BIOLOGICAL SHIELDING OF HTGR-10 MWth PEBBLE BED REACTOR. HTGR-10 MWth is a high-temperature gas-cooled reactor. The fuel and moderator are pebble shaped with a radius of 3 cm. One fuel pebble consists of thousands of UO2 kernels with a density of 10.4 gram/cc and the enrichment rate of 17%. The core of HTGR-10 MWth is the center of origin of neutrons and gamma radiation resulting from the interaction of neutrons with pebble fuel, moderator and biological shield. The various types of radiations generated from such nuclear reactions should be monitored to ensure the safety of radiation workers. This research was conducted using MCNP-6 Program package with the aim to calculate and analyze gamma radiation dose in biological shield of HTGR-10 MWth. In this study, the biological shield is divided into 10 equal segments. The first step of the research is to benchmark the created program against the critical height of HTR-10. The results of the benchmarking show an error rate of ± 1.1327%, while the critical core height of HTGR 10 MWth for the ratio of pebble fuel and pebble moderator (F:M) of 52: 48 occurs at a height of 134 cm. The rate of gamma dose at the core is 3.0052E + 05 mSv/hr. On the biological shield made of regular concrete with a density of 2.3 grams/cc, the rate of gamma dose decreases according to an equation y = 0.0042 e-0.03x. Referring to Perka Bapeten no 4 of 2013, the safe limits for workers and radiation protection officers will be achieved if the minimum thickness of biological shield is 115 cm with gamma dose rate of 0 mSv/hour.Keywords: Gamma dose rate, HTGR 10 MWth, biological shield, pebble

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Section: Resultsmentioning

confidence: 96%

GAMMA DOSE RATE ANALYSIS IN BIOLOGICAL SHIELDING OF HTGR-10 MWth PEBBLE-BED REACTOR

Adrial

Hamzah²,

Hartini³

2019

urania

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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: 96%

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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“…The neutron transport and burnup analysis was performed using a continuousenergy Monte Carlo code called MVP-BURN [13]. Methods to model the double heterogeneity of PBRs have been developed recently for various Monte Carlo-based codes [14][15][16]. However, the intrinsic statistical geometry model in the MVP-BURN code is appropriate to model the double heterogeneity and the stochastic nature of PBR core and fuel design correctly in a simple way.…”

Section: Calculational Methodsmentioning

confidence: 99%

Preliminary Neutronic Design of High Burnup OTTO Cycle Pebble Bed Reactor

2015

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The pebble bed type High Temperature Gas-cooled Reactor (HTGR) is among the interesting nuclear reactor designs in terms of safety and flexibility for cogeneration applications. In addition, the strong inherent safety characteristics of the pebble bed reactor (PBR) which is based on natural mechanisms improve the simplicity of the PBR design, in particular for the Once-Through-Then-Out (OTTO) cycle PBR design. One of the important challenges of the OTTO cycle PBR design, and nuclear reactor design in general, is improving the nuclear fuel utilization which is shown by attaining a higher burnup value. This study performed a preliminary neutronic design study of a 200 MWt OTTO cycle PBR with high burnup while fulfilling the safety criteria of the PBR design.The safety criteria of the design was represented by the per-fuel-pebble maximum power generation of 4.5 kW/pebble. The maximum burnup value was also limited by the tested maximum burnup value which maintained the integrity of the pebble fuel. Parametric surveys were performed to obtain the optimized parameters used in this study, which are the fuel enrichment, per-pebble heavy metal (HM) loading, and the average axial speed of the fuel. An optimum design with burnup value of 131.1 MWd/Kg-HM was achieved in this study which is much higher compare to the burnup of the reference design HTR-MODUL and a previously proposed OTTO-cycle PBR design. This optimum design uses 17% U-235 enrichment with 4 g HM-loading per fuel pebble.

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A new strategy to simulate a random geometry in a pebble-bed core with the Monte Carlo code MCNP

Cited by 19 publications

References 1 publication

GAMMA DOSE RATE ANALYSIS IN BIOLOGICAL SHIELDING OF HTGR-10 MWth PEBBLE-BED REACTOR

GAMMA DOSE RATE ANALYSIS IN BIOLOGICAL SHIELDING OF HTGR-10 MWth PEBBLE-BED REACTOR

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

Preliminary Neutronic Design of High Burnup OTTO Cycle Pebble Bed Reactor

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