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Zuhair Zuhair
Pusat Teknologi Reaktor dan Keselamatan Nuklir – BATAN Kawasan Puspiptek, Gedung No. 80, Serpong, Tangerang 15310
Environmental Science

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Safety Analysis of Stacy's Critical Territory Criticality with Monte Carlo Transport Calculations Zuhair Zuhair
Natural B, Journal of Health and Environmental Sciences Vol 2, No 1 (2013)
Publisher : Natural B, Journal of Health and Environmental Sciences

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (138.054 KB) | DOI: 10.21776/ub.natural-b.2013.002.01.3

Abstract

A set of experiment has been done at STACY facility and many fundamental parameters of uranyl nitrate solution have been found out. Criticality is one of main parameters in predicting neutronic characteristic of STACY experiment beside solution level reactivity, void reactivity, kinetic parameter and temperature reactivity which dominates transient phenomenon in abnormal condition. Criticality experiment performed at STACY core uses 9.97% 235U -enriched uranyl nitrate solution with 80-cm-diameter cylindrical and 150-cm-height tank. Eight critical configurations in unrelected and water-reflected conditions were selected in this paper for criticality safety calculation with Monte Carlo transport code MCNPX. For all configurations, MCNPX calculations show good consistency with the trend of producing underestimated keff. Calculation biases with experimental data (keff = 1) for water-reflected configurations, i.e. 0.01-0.18%, were slightly better than those of unreflected configurations (0.14-0.41%). MCNPX calculation results which are better than the prediction of MCNP-4C concludes that MCNPX is more eligible to be applied to criticality safety analysis of uranyl nitrate solution in commercial nuclear fuel cycle facility.
Study of Package Fraction Fraction Sensitivity TRISO in Design of HTR Pebble Bed Criticality Zuhair Zuhair; Suwoto Suwoto
Natural B, Journal of Health and Environmental Sciences Vol 1, No 4 (2012)
Publisher : Natural B, Journal of Health and Environmental Sciences

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (145.502 KB) | DOI: 10.21776/ub.natural-b.2012.001.04.13

Abstract

HTR is a high temperature reactor used for electricity production and process heat applications such as hydrogen production, desalination of sea water, enhanced oil recovery and so on. HTR is designed based on the utilization of TRISO fuel particles that can prevent strongly the escape of fission products even at temperatures above 1600 oC. TRISO particles packing fraction is one of four key parameters that are essential in HTR design besides radius of the kernel, kernel density and fuel enrichment. This paper discusses the sensitivity of TRISO particles packing fraction that impacts to the loading of uranium in the fuel pebble, the long cycle of reactor operation and achievable maximum fuel burn-up. With the capability of Monte Carlo transport code MCNP5, all components of the reactor, starting from TRISO particles, were modeled in detail and explicit and calculated using the continuous energy nuclear data library ENDF/B-VI. The results show that the value of effective multiplication factor (keff) has a tendency to increase with decreasing particle TRISO packing fraction and to decrease with increasing fuel burn-up. Keff values decrease with increasing TRISO particle packing fraction both at the beginning of cycle (BOC) and at the end of cycle (EOC). Reactivity swing is also very sensitive on the TRISO particles packing fraction. From the analysis, it can be concluded that TRISO particles packing fraction greatly affects the neutronics performance of HTR pebble bed design. Packing fraction can change the effective multiplication factor (keff) and the swing reactivity with similar behavior.
Co-Authors Suwoto Suwoto