• Journal of Radiation Protection and Research
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• 제41권2호
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• pp.155-159
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• 2016

Background: Nuclear reactors produce a great number of antielectron neutrinos mainly from beta-decay chains of fission products. Such neutrinos have energies mostly in MeV range. We are interested in neutrinos in a region of keV, since they may take part in special weak interactions. We calculate reactor antineutrino spectra especially in the low energy region. In this work we present neutrino spectrum from a typical pressurized water reactor (PWR) reactor core. Materials and Methods: To calculate neutrino spectra, we need information about all generated nuclides that emit neutrinos. They are mainly fission fragments, reaction products and trans-uranium nuclides that undergo negative beta decay. Information in relation to trans-uranium nuclide compositions and its evolution in time (burn-up process) were provided by a reactor code MVP-BURN. We used typical PWR parameter input for MVP-BURN code and assumed the reactor to be operated continuously for 1 year (12 months) in a steady thermal power (3.4 GWth). The PWR has three fuel compositions of 2.0, 3.5 and 4.1 wt% $^{235}U$ contents. For preliminary calculation we adopted a standard burn-up chain model provided by MVP-BURN. The chain model treated 21 heavy nuclides and 50 fission products. The MVB-BURN code utilized JENDL 3.3 as nuclear data library. Results and Discussion: We confirm that the antielectron neutrino flux in the low energy region increases with burn-up of nuclear fuel. The antielectron-neutrino spectrum in low energy region is influenced by beta emitter nuclides with low Q value in beta decay (e.g. $^{241}Pu$) which is influenced by burp-up level: Low energy antielectron-neutrino spectra or emission rates increase when beta emitters with low Q value in beta decay accumulate Conclusion: Our result shows the flux of low energy reactor neutrinos increases with burn-up of nuclear fuel.

• Nuclear Engineering and Technology
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• 제41권2호
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• pp.199-214
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• 2009

High burn-up transformation process in low temperature nuclear fuel oxides material was observed in the early sixties in LWR $UO_2$ fuels, but not studied in depth. Increasing progressively the fuel discharge burn-up in PWR power plants, this material transformation was again observed in 1985 and identified as an important process to be accounted for in the fuel simulations due to its expected consequence on fuel heat transfer and therefore on the fission gas release. Fission gas release was one of the major concerns in PWR fuels, mainly during transient or accidents events. The behaviour of such a material in case of rod failure was also an important aspect to analyse. Therefore several national and international programs were launched during the last 25 years to understand the mechanisms leading to the high burn-up structure formation and to evaluate the physical properties of the final material. A large observations database has been acquired, using the more sophisticated techniques available in hot cells. This large database is discussed in this paper, providing basis to build an engineering-model, which is based on phenomenological description data and information accumulated. In addition this paper has the ambition to construct the best logical model to understand restructuring.

• Nuclear Engineering and Technology
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• 제33권4호
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• pp.365-374
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• 2001

In order to examine the in-reactor performance of very-high-density dispersion fuels for high flux performance research reactors, U-l0wt.%Mo microplates containing centrifugally atomized powder were irradiated at low temperature. The U-l0wt.%Mo dispersion fuels show stable in- reactor irradiation behaviors even at high burn-up, similar to U$_3$Si$_2$ dispersion fuels. The atomized U-l0wt.%Mo fuel particles have a fine and a relatively uniform fission gas bubble size distribution. Moreover, only one of third of the area of the atomized fuel cross-sections at 70a1.% burn-up shows fission gas bubble-free zones, This appears to be the result of segregation into high Mo and low Mo.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2019년도 춘계학술논문요약집
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• pp.137-138
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• 2019

• 방사성폐기물학회지
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• 제13권3호
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• pp.201-209
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• 2015

우리나라에서는 현재 23기의 원자력발전소를 운영 중에 있으며, 이들 원자력발전소로부터 발생하는 사용후핵연료를 처분대상으로 기준 심지층 처분시스템을 개발한 바 있다. 현재 이 기준 심지층 처분시스템은 초기농축도 4.5wt%, 방출연소도 55 GWd/MtU의 40 년 냉각된 사용후핵연료를 기준으로 하고 있다. 본 논문에서는 처분효율 및 경제성 향상 방안의 일환으로서 사용후핵연료의 종류 및 연소도 특성 등 발생특성을 검토하였다. 그리고 기준 사용후핵연료에 비하여 길이가 짧고 연소도가 비교적 낮은 사용후핵연료에 대한 처분용기 개념을 도출하고 열해석을 수행하여 처분시스템 개념을 제시하였다. 또한, 이 처분시스템 개념과 기준 사용후핵연료 처분시스템 개념을 처분밀도, 처분면적 등의 처분효율 및 구리와 벤토나이트 소요량 등 경제성 관점에서 비교 분석한 결과 약 20% 이상 향상을 보이는 것을 확인하였다. 본 분석결과는 사용후핵연료 관리정책 수립 및 실제 처분시스템 설계에 활용될 수 있을 것으로 사료된다.

• Nuclear Engineering and Technology
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• 제41권2호
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• pp.187-198
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• 2009

In this paper, three power ramp tests performed on high burn-up Re-crystallized Zircaloy2 - UO2 BWR fuel rods (56 to 63 MWd/kgU) within the SCIP project are simulated with METEOR and ALCYONE 3D. Two of the ramp tests are of staircase type up to Linear Heat Rates of 420 and 520 W/cm and with long holding periods. Failure of the 420 W/cm fuel rod was observed after 40 minutes. The third ramp test consisted of a more standard ramp test with a constant power rate of 80 W/cm/min up to 410 W/cm with a short holding time. The tests were first simulated with the METEOR 1D fuel rod code, which gave accurate results in terms of profilometry and fission gas releases. The behaviour of a fuel pellet fragment and of the cladding piece on top of it was then investigated with ALCYONE 3D. The size and the main characteristics of the ridges after base irradiation and power ramp testing were recovered. Finally, the failure criteria validated for PWR conditions and fuel rods with low-to-medium burn-ups were used to analyze the failure probability of the KKL rodlets during ramp testing.

• Journal of Hospice and Palliative Care
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• 제13권3호
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• pp.161-168
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• 2010

목적: 본 연구는 한국 호스피스 완화의료에 개입하고 있는 사회복지사의 소진에 관한 요인과 보호요인에 관한 연구이며 요인분석에 있어서는 전문적 역량, 사회적 지지 그리고 수퍼비전으로 구분하여 상관관계를 살펴보았다. 방법: 표집대상은 사회복지 활동을 시행하고 있는 의료기관을 주요 대상 기관으로 선정하고, 46부의 설문지가 분석 자료로 활용되었다. SPSS 12.0 통계 프로그램을 이용하여 기술통계분석, T-test, ANOVA 그리고 다중회귀분석(Multiple Regression)을 활용하였다. 결과: 전문적 역량에 따른 사회복지사의 소진 분석에서는 대체적으로 유의미한 부적 상관관계가 있음으로 조사되었으며 회귀분석 결과 서비스 신념, 자기규제 신념 그리고 직업 소명의식이 소진보호요인으로 분석되었고, 사회적 지지에서는 상사의 지지가 신체적 소진과 정서적 소진을 보호요인으로 분석되었다. 슈퍼비전의 지식, 평가, 귄위 항목이 사회복지사의 비인간화를 보호하는 중요 변수임을 또한 확인할 수 있었다. 결론: 사회복지사의 소진 극복을 위하여 전문적 교육, 사회적 지지 그리고 수퍼비전의 체계적 구축을 위한 구조적 지원과 개인이 극복하고자 노력하는 적극적인 요인들이 복합적으로 이루어질 때, 소진에 대한 극복과 전문가로서의 자리매김이 가능할 것으로 사료된다.

• 대한불안의학회지
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• 제8권2호
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• pp.93-98
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• 2012

Objective : Cortisol, a product of hypothalamus-pituitary-adrenal axis (HPA axis), is one of our defensive mechanisms in response to stress. The level of cortisol in the saliva is a major biomarker of the stress response by HPA axis and shows diurnal variation. We measured salivary cortisol level and its diurnal variation to compare the pattern of changes by degree of burn and Clinician-Administered PTSD Scale (CAPS) score. Methods : We measured the salivary cortisol levels of 37 subjects hospitalized in the burn center at our facility from March to June 2012. Salivary cortisol levels were measured at 6 : 00 AM and at 7 : 00 PM. All subjects were tested for CAPS to evaluate the severity of posttraumatic stress disorder and the Hamilton Depression Rating Scale to evaluate and to control the coexisting depression. Results : Factorial ANOVA test revealed that there was a statistically significant difference in terms of the effect of the interaction between the degree of burn and the patient's CAPS score. Unlike the mild burn group, in the severe burn group, the patients who had a low CAPS score didn't show a normal diurnal variation and the patients who had a high CAPS score showed the normal diurnal variation. After a few months follow up, we found a greater degree of psychiatric complications in severe burn patients that had a lower cortisol stress response. Conclusion : We suppose that the disappearance of the stress response changes in salivary cortisol seen in the severe burn group may be caused by an impaired stress response. Through followed observation of the subjects, this disruption of cortisol response may cause psychiatric problems afterwards.

• Nuclear Engineering and Technology
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• 제41권2호
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• pp.143-148
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• 2009

The increasing power and other demands on PWR fuel is leading to a demand for cladding that has low corrosion but that should also be robust with regard to mechanical behavior, impact of the irradiation environment and the coolant chemistry. The Optimized $ZIRLO^{TM}$ cladding is an evolutionary development of $ZIRLO^{TM}$ taking advantage of the long experience of the ZIRLO cladding but has significantly improved corrosion behavior. Recently, operation of Optimized ZIRLO to above 73 kWd/kgU has shown a reduction of the corrosion of almost 50%.

• 한국진공학회:학술대회논문집
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• 한국진공학회 2014년도 제46회 동계 정기학술대회 초록집
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• pp.456.1-456.1
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• 2014

Transmutation characteristics of transuranics (TRU) in a transmutation reactor based on LAR (Low Aspect Ratio) tokamak as a neutron source are investigated. Optimum radial build of a transmutation reactor is found by coupled analysis of the tokamak systems and the neutron transport. The dependence of the transmutation characteristics on an aspect ratio, A in the range of 1.5 to 2.5, and on a fusion power in the range of 150 MW to 500 MW are investigated. Equilibrium fuel cycle is developed for effective transmutation and it is shown that with one unit of the transmutation reactor based on the LAR tokamak producing fusion power in the range of a few hundred MW, up to 3 PWRs (1.0 GWe capacity) can be supported with the burn-up fraction bigger than 50%.