• 방사성폐기물학회지
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• 제4권2호
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• pp.95-102
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• 2006

알파분광법에 의한 $^{237}Np$ 의 정량방법을 검토하였다. 황산염 매질에서 전류세기, 전착시간 및 유기물 첨가제 둥의 변화에 따른 $^{237}Np$ 의 전착조건을 찾은 결과 $1.2{\sim}1.5$ A에서 유기첨가제 없이 $1{\sim}1.5$ 시간 동안 전착하는 것이 효율적이었다. $^{237}Np$ 을 4.16 Bq에서 0.0264 Bq(1ng) 까지 전착한 결과 농도가 낮을수록 전착율 및 재현성이 낮아졌으며 1 ng 까지 측정이 가능하였다. 사용후 핵연료 합성용액에서 $^{237}Np$을 분리한 후 알파분광법으로 측정하여 정량한 결과 $98.8{\pm}5.1%$(n=4)의 회수율을 나타내었다. 사용후 핵연료 시료용액 중 $^{237}Np$ 을 정량하였으며 계산 값과 비교한 결과 10% 이내에서 서로 일치하였다.

• Nuclear Engineering and Technology
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• 제45권3호
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• pp.415-420
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• 2013

A determination method for $^{237}Np$ in spent nuclear fuel samples was developed using an isotope dilution method with $^{239}Np$ as a spike. In this method, inductively coupled plasma mass spectrometry (ICP-MS) was taken for the $^{237}Np$ instead of the previously used alpha spectrometry. $^{237}Np$ and $^{239}Np$ were measured by ICP-MS and gamma spectrometry, respectively. The recovery yield of $^{237}Np$ in synthetic samples was $95.9{\pm}9.7$% (1S, n=4). The $^{237}Np$ contents in the spent fuel samples were 0.15, 0.25, and $1.06{\mu}g/mgU$ and these values were compared with those from ORIGEN-2 code. A fairly good agreement between the measurements (m) and calculations (c) was obtained, giving ratios (m/c) of 0.93, 1.12 and 1.25 for the three PWR spent fuel samples with burnups of 16.7, 19.0, and 55.9 GWd/MtU, respectively.

• 공업화학
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• 제7권1호
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• pp.153-161
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• 1996

방사성폐액 중 주요 핵종인 $^{241}Am$, $^{152}Eu$ 및 $^{237}Np$를 선정하여 추출제 di-(2-ethylhexyl) phosphoric acid를 사용한 용매추출법으로 이들 세 가지 핵종의 상호분리에 대해 연구하였다. $^{237}Np$의 추출율을 향상시키기 위해 환원제로 $H_2O_2$를 첨가하여 추출한 결과 $^{241}Am$, $^{152}Eu$ 및 $^{237}Np$ 핵종 모두 99.9% 이상 추출할 수 있었다. 추출된 $^{241}Am$, $^{152}Eu$ 및 $^{237}Np$는 세 단계의 역추출과정을 통해 상호분리한 결과 $^{152}Eu$와 $^{237}Np$의 경우 상호분리도가 좋았으나, $^{241}Am$의 경우 약 7~9.6%의 $^{152}Eu$와 $^{237}Np$가 동반 역추출되어 $^{241}Am$ 용액에 대한 정제과정이 추가로 요구되었다. 용매재생과정에서 생성되는 제3상의 생성원인과 해결방법에 대해서도 논하였다.

• 한국방사선학회논문지
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• 제5권4호
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• pp.217-221
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• 2011

$^{237}Np$ is very important material in the fission products of nuclear reactors. Resonance integral(RI) tests of this material is necessary to check between the experiments and the evaluated data. Such feedback to the evaluated data is very important to correct data and improve of codes. The RI for the $^{237}Np(n,{\gamma})^{238}Np$ reaction were measured by using the 46-MeV electron linear accelerator (linac) at the Research Reactor Institute, Kyoto University (KURRI). The measurement was performed in the energy region from 0.005 eV and 10 keV. RI obtained as 804.7 barns, compared with those of the evaluated data in JENDL-4.0 and Mughabghab.

• Nuclear Engineering and Technology
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• 제13권4호
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• pp.207-220
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• 1981

예평형붕괴를 고려한 통계모형 전산코드 STAPES를 써서 NP-237핵분열 단면적을 입사중성자 에너지 20MeV까지 계산하였다. 중성자 방출에 수반되는 분열과정은 3차 복합핵까지 고려하였으며, 이중분열장벽에 관련된 주요 입력변수는 실험값의 최근 동향을 감안, 전 에너지 영역을 통하여 약 l0%의 편차범위 내에서 부합될 수 있도록 조정하였다. 계산결과는 각 에너지에 대응하는 단면적 값의 표와, 실험값과의 비교를 제시하는 그림으로 나타냈다.

• Nuclear Engineering and Technology
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• 제3권2호
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• pp.77-97
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• 1971

1970년 말까지 보고된 U-238, Np-237 및 Th-232의 고속중성자에 대한 핵분열단 면적 및 그 실험오차를 조사 분석하여 최소자숭직교다항식적합법에 의하여 단면적의 최적치와 95%신뢰도에 대응하는 오차범위를 계산하고 이 결과를 사용하여 분열스펙트럼에 대한 평균단면적치를 추정하였다.

• Nuclear Engineering and Technology
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• 제39권5호
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• pp.673-682
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• 2007

The contents of transuranic elements in high-burnup spent fuel samples were determined. The activity amounts of $^{238}Pu,\;^{239}Pu,\;^{240}Pu,\;^{241}Am,\;^{244}Cm\;and\;^{242}Cm$ were measured by alpha spectrometry using $^{242}Pu\;and\;^{243}Am$ as tracers, respectively. A spike addition method for $^{237}Np$ was established by an alpha and gamma spectrometry using $^{239}Np$ as a spike after the optimum conditions for the measurements of $^{237}Np\;and\;^{239}Np$, respectively, were obtained. A separation system using anion exchange chromatography and diethylhexylphosphoric acid extraction chromatography was applied for the separation of these elements. This method was applied to high-burnup spent nuclear fuel samples $(40{\sim}60GWD/MTU)$. The contents of the transuranic elements were compared with those by ORIGEN-2 code. Measurements and the calculations of the contents of the plutonium isotopes $^{238}Pu,\;^{239}Pu\;and\;^{240}Pu$ agreed to within 10% on average. The contents of $^{237}Np$ agreed to within approximately 5% except for one instance of a calculation, while those of $^{241}Am,\;^{244}Cm\;and\;^{242}Cm$ showed higher values by approximately 19%, 35% and 14% on average, respectively, compared to the calculations according to the burnup.

• Nuclear Engineering and Technology
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• 제33권2호
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• pp.231-240
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• 2001

When it is assumed that PWR, CANDU and DUPIC spent fuels are disposed of in deep geological repository, consequent annual individual doses are calculated, and it is shown that doses meet the regulatory limit. From these results, the hazardous radionuclides applicable to partitioning and transmutation are selected. These selected radionuclides such as Tc-99, Ⅰ-129, Cs-135 and Np-237 are then reviewed in terms of partitioning and transmutation. Separation of I-129, Np-237 and Tc-99 from spent fuels is considered desirable, and transmutation of these radionuclides results in remarkable hazard reduction. However, it is concluded that separation and transmutation of Cs-135 may be ineffective although it is classified into a hazardous radionuclide.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2004년도 Proceedings of the 4th Korea-China Joint Workshop on Nuclear Waste Management
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• pp.182-190
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• 2004

An unique extraction chromatographic column (TOA: Tri-n-octylamine on Teflon powder) with a two-stage sample loading was prepared to separate Np and Pu from the environmental matrix. Np and Pu were efficiently retained in 4 M $HNO_3$ medium on the column and easily eluted with 0.02 M oxalic acid in 0.16 M HNO$_3$at $95^{\circ}C$. The separated solutions were free from most of the matrix elements and were aspirated into the ICP-MS directly. The decontamination factor for 238U is more than 104. The instrumental detection limit for 237Np was 0.46 pg mL-l ($1.2{\times}10_{-5}$Bq mL-l), and for 239Pu was 0.48 pg mL-l ($1.1{\times}10_{-3}$ Bq mL-l). The feasibility for the determination of both elements was proved by analysing IAEA-135 reference samples, the measured values agreed with the recommended reference value.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2005년도 추계 학술대회 논문집
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• pp.252-253
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• 2005