• Nuclear Engineering and Technology
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• 제54권1호
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• pp.11-18
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• 2022

In this research, curium oxide (CmO₂) is studied as fuel for VVER-1200 reactor to get an attention to its energy value and possibilities. For this purpose, CmO₂ is used in fuel rods or integrated burnable absorber (IBA) rods with and without UO₂ and then compared with the conventional fuel assembly of VVER-1200 reactor. It is burned to 60 GWd/t by using SRAC-2006 code and JENDL-4.0 data library. From these studies, it is found that CmO₂ is competent like UO₂ as a fuel due to higher fission cross-section of ²⁴³Cm and ²⁴⁵Cm isotopes and neutron capture cross-section of ²⁴⁴Cm and ²⁴⁶Cm isotopes. As a result, when some or all of the UO₂ of fuel rods or IBA rods are replaced by CmO₂, we get a similar k-inf like the reference even with lower enrichment UO₂ fuels. These studies show that the use of CmO₂ as IBA rods is more effective than the fuel rods considering the initially loaded amount, power peaking factor (PPF), fuel temperature and void coefficient, and the quality of spent fuel. From a detailed study, 3% CmO₂ with inert material ZrO₂ in IBA rods are recommended for the VVER-1200 reactor assembly from the once through concept.

• 천문학회보
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• 제45권1호
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• pp.70.4-71
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• 2020

One of the distinctive characteristics of the evolution of binary systems would be mass transfer. Close binary systems experience so-called Case A mass transfer during the main-sequence. We have performed calculations of the evolution of massive Case A (with the initial period 1.5 ~ 4.5 days) binary systems with the initial mass of 10 ~ 20 solar masses and mass ratio 0.5 ~ 0.95 using the MESA code. We find that in some systems, after the first mass transfer, the secondary stars evolve faster than the primary stars and undergo so-called 'reverse' mass transfer. Such phenomena tend to occur in relatively low-mass (initial mass < 16 solar masses) and close (initial period < 3 day) systems. Unless a system enters the common-envelope phase, the primary star would become a single helium star after the secondary star ends its life if the system were unbound by the neutron star kick. We find the various evolutionary implications of the remaining primary stars. In addition to the evolution into the compact single helium star progenitor, there is a possibility that the remaining primary star could evolve into a helium giant star, which could be a promising candidate for Type Ibn supernova progenitor, depending on the core mass. Further, we find that some primary stars satisfy the conditions for the formation of electron-capture supernova progenitor.

• Nuclear Engineering and Technology
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• 제20권2호
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• pp.105-111
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• 1988

과망간산염들, 즉 과망간산 칼륨, 과망간산 암모늄, 과망간산 바륨에서 망간의 중성자 포획으로 야기되는 화학적 효과를 고찰하였다. $^{55}$Mn(n, ｒ) $^{56}$ Mn 반응에서 생성된 방사성 망간 화학종, 즉 양이온 56/Mn, $^{56}$ MnO$_2$ 그리고 $^{56}$ MnO$_4$$^{-}$의 분포에 미치는 용제의 pH효과를 여러 가지 흡착제들과 이온교환체, 즉 제올이프 A-3, 카올리나이트, 알루미나, 이산화망간 그리고 도엑스 -50을 이용하여 고찰하였다. 카올리나이트와 알루미나에서 방사성 MnO$_4$$^{-}$의 분포가 대표적인 pH값인 4, 7 그리고 9 각각에서 다른흡착제와 이온교환체보다 높게 나타나며 동일한 흡착제일경우에는 pH 4 는 및 pH 9에서가 pH 7에서보다 높게 나타난다. $^{55}$Mn(n, ｒ) $^{56}$ Mn 반응에 의하여 과망간산염에서 생성된 반조망간원자들의 열-어니어링 거동 또한 고찰하였다. 열-어니어링에서 $^{56}$ MnO$_4$$^{-}$의 잔류율은 10$0^{\circ}C$ 및 13$0^{\circ}C$ 처리에서 온도가 높아질수록 증가함을 보였다. 망간염의 반조효과는 hot zone model로 설명하였다.

• Nuclear Engineering and Technology
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• 제46권3호
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• pp.313-342
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• 2014

A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark for Uncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of available uncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safety calculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phases each of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known as the "Neutronics Phase", which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutron-nuclide reactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters of neutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuity factors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done to reduce uncertainties in key nuclide reaction uncertainties (i.e.: $^{238}U$ radiative capture and inelastic scattering (n, n') as well as the average number of neutrons released per fission event of $^{239}Pu$).

• 한국의학물리학회지:의학물리
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• 제27권4호
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• pp.232-235
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• 2016

The purpose of this study is to develop the treatment planning system (TPS) based on Monte-Carlo simulation for BNCT. In this paper, we will propose a method for dose estimation by Monte-Carlo simulation using the CT image, and will evaluate the accuracy of dose estimation of this TPS. The complicated geometry like a human body allows defining using the lattice function in MCNPX. The results of simulation such as flux or energy deposition averaged over a cell, can be obtained using the features of the tally provided by MCNPX. To assess the dose distribution and therapeutic effect, dose distribution was displayed on the CT image, and dose volume histogram (DVH) was employed in our developed system. The therapeutic effect can be efficiently evaluated by these evaluation tool. Our developed TPS could be effectively performed creating the voxel model from CT image, the estimation of each dose component, and evaluation of the BNCT plan.

• Nuclear Engineering and Technology
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• 제42권1호
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• pp.79-88
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• 2010

Spent $UO_2$ nuclear fuel discharged from a nuclear power plant (NPP) contains fission products, U, Pu, and other actinides. Due to neutron capture by $^{238}U$ in the rim region and a temperature gradient between the center and the rim of a fuel pellet, a considerable increase in the concentration of fission products, Pu, and other actinides are expected in the pellet periphery of high burnup fuel. The characterization of the radial profiles of the various isotopic concentrations is our main concern. For an analysis, spent nuclear fuels originating from the Yeonggwang-2 pressurized water reactor (PWR) were chosen as the test specimens. In this work, the distributions of some actinide isotopes were measured from center to rim of the spent fuel specimens by a radiation shielded laser ablation inductively coupled plasma mass spectrometer (LA-ICP-MS) system. Sampling was performed along the diameter of the specimen by reducing the sampling intervals from 500 ${\mu}m$ in the center to 100 ${\mu}m$ in the pellet periphery region. It was observed that the isotopic concentration ratios for minor actinides in the center of the specimen remain almost constant and increase near the pellet periphery due to the rim effect apart from the $^{236}U$ to $^{235}U$ ratio, which remains approximately constant. In addition, the distributions of local burnup were derived from the measured isotope ratios by applying the relationship between burnup and isotopic ratio for plutonium and minor actinides calculated by the ORIGEN2 code.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.104-104
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• 2018

Kori Unit 1 is the first permanent shutdown nuclear power plant in Korea and it is on June 18th, 2017. Spent fuel assemblies began to be discharged from the reactor core to the spent fuel pool(SFP) within one week after shutdown of Kori unit 1 and the campaign was completed on June 27th, 2017. The total number of spent nuclear fuel assemblies in SFP of Kori Unit-1 is 485 and their discharging date is different respectively. So, decay heat was evaluated considering the actual enrichment, operation history and cooling time of the spent fuel assemblies stored in SFP of the Kori Unit-1. The code used in the evaluation is the ORIGEN-based CAREPOOL system developed by KHNP. Decay heat calculation of PWR fuel is based on ANSI/ANS 5.1-2005, "Decay heat power in light water reactors" and ISO-10645, "Nuclear energy - Light water reactors - Calculation of the decay heat power in nuclear fuels. Also, we considered the contribution of fission products, actinide nuclides, neutron capture and radioactive material in decay heat calculation. CAREPOOL system calculates the individual and total decay heat of all of the spent fuel assemblies in SFP of Kori Unit-1. As a result, the total decay heat generated in SFP on June 28th, 2017 when the spent fuel assemblies were discharged from the reactor core, is estimated to be about 4,185.8 kw and to be about 609.5 kw on September 1st, 2018. It was also estimated that 119.6 kw is generated in 2050 when it is 32 years after the permanent shutdown. Figure 1 shows the trend of total decay heat in SFP of Kori Unit-1.

• 방사성폐기물학회지
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• 제18권1호
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• pp.83-90
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• 2020

흑연 동위원소 비율법(GIRM)은 비핵화 검증 도구로써 흑연감속로의 플루토늄 생산량을 예측하는데 사용된다. 원자로가 가동되면 ²³⁸U의 중성자 포획 반응에 의해 플루토늄이 생성되어 축적되고 동시에 흑연 내 불순물도 핵반응을 통해 다른 핵종으로 바뀌기 때문에 플루토늄의 생성량과 불순물의 농도는 일정한 상관 관계를 갖는다. 이러한 상관관계에도 불구하고 어느 특정 시점에서의 불순물의 농도는 불순물의 초기 농도에 의존하기 때문에 불순물의 초기 농도가 알려지지 않으면 불순물의 절대 농도만으로 플루토늄 생산량을 예측하는 것은 불가능하다. 그러나 불순물의 초기 동위원소 비율은 초기 불순물 농도에 상관없이 알려져 있기 때문에 불순물의 동위원소 비율과 플루토늄 생산량의 관계는 흑연감속로에서 플루토늄 생성량을 예측하는 유용한 도구가 될 수 있다. 흑연동위원소 비율법의 지표 원소로 Boron, Lithium, Chlorine, Titanium, Uranium 등이 이용되는 것으로 알려져 있다. 위 지표원소의 동위원소 비와 플루토늄 생성량 사이의 상관 관계가 초기 불순물 농도에 의존하지 않는지를 네 가지 다른 흑연 불순물 조성을 이용하여 평가하였다. ¹⁰B/¹¹B, ³⁶Cl/³⁵Cl, ⁴⁸Ti/⁴⁹Ti, ²³⁵U/²³⁸U은 흑연의 초기 불순물 농도에 상관없이 누적 플루토늄 생성량과 일관된 상관 관계를 갖는다. 이러한 원소들은 다른 원소의 핵반응에 의해 해당 원소의 동위원소가 생성되지 않기 때문이다. 반면 ⁶Li/⁷Li과 플루토늄 생성량의 상관관계는 흑연 내 불순물의 초기 농도에 의존한다. ⁷Li은 ⁶Li의 중성자 포획 반응에 의해서 생성되기도 하지만 ¹⁰B의 (n, α)반응으로도 생성되는 것이 더 지배적이기 때문에 ¹⁰B의 초기 농도가 ⁷Li의 생성량에 영향을 미치는 것이다. 따라서 Lithium은 흑연 동위원소 비율법을 위한 지표 원소로 적절하지 않음을 알 수 있다.