• Journal of Radiation Protection and Research
• /
• 제40권3호
• /
• pp.181-186
• /
• 2015

방사성 제논 탐지는 공기 중 $^{131m}Xe$, $^{133}Xe$, $^{133m}Xe$ 및 $^{135}Xe$를 저준위 백그라운드 계측 시스템으로 검출하여 지하 핵실험 여부를 규명하는 핵심기술 중 하나이다. 방사성 제논 감시는 공기 포집, 제논 추출, 측정 및 분석을 통해 수행되며, $^{135}Xe$의 최소검출가능농도는 비교적 짧은 반감기로 인해 포집, 추출 및 측정시간에 따라 큰 차이를 보이게 된다. 본 연구에서는 방사성 제논 계측 시스템의 정해진 시료 포집 및 전처리 조건에서 최적의 방사성 제논 측정시간을 도출하기 위해 이론적 접근 및 SAUNA 시스템을 이용한 실험을 통해 최소의 MDC를 보이는 측정시간을 결정하고 이론적 계산과 실험결과에 대하여 비교 평가하였다.

• 대한전자공학회논문지
• /
• 제13권5호
• /
• pp.17-23
• /
• 1976

고속열중성자로에서 정상 운전중인 원자로를 운전정지하였다가 재가동할 때 가장 문제가 되는 것은 핵분열 생성물인 Xe135의 독소작용이다. 이것은 Xe135가 원자로 출력에 영향을 주는 열중성자에 대한 흡수단면적이 크고 그의 반감기가 길기 때문이다. 그러므로 원자로의 일시적 운전정지가 요구될 때 이의 재가시에는 반듯이 이 독소를 능과할 수 있는 충분한 초과반응도를 가해 주던지, Xe135가 붕괴되어 그의 농도가 줄어든 이후에야 원자로의 재가동이 가능하게 된다. 위와 같은 문제는 사실상 원자로 운전시 안전성 뿐만 아니라 경제성에도 큰 영향을 주고 있다. 본 논문에서는 이 점을 고려하여 Pontoyagin의 최대원리를 이용하여 운전정지를 최적화시키므로서 언제든지 원자로를 전출력으로 재가동할 수 있도록 운전정지 방법을 개선하였다. 그러나 제어과정에서나 그 이후에도 X, 농도는 제어된 허용치를 넘지 않고 최소시간 이내에 모든 제어를 끝내도록 하였다. The buildup of fission product, i.e. Xe-135 poisoning, is a prime factor in restarting a nuclear reactor from the shutdown, which was under normal operation in the high flux thermal reactor, It is caused by the high absorption crosssection of Xe-135 to thermal neutrons and its long half life, from which the thermal power is affected. It is then possible to restart a nuclear reactor after the sufficient excess reactivity to override this poisoning must be inserted, or its concentration is decreased sufficiently when its temporary shutdown is required. As ratter of fact, these have an important influence not only on reactor safety but also on economic aspect in operation. Considering these points in this study, the shutdown process was cptimized using the Pontryagin's maximum principle so that the shutdown mirth[d was improved as to restart the reactor to its fulpower at any time, but the xenon concentration did not excess the constrained allowable value during and after shutdown, at the same time all the control actions were completed within minimum time from beginning of the shutdown.

• Nuclear Engineering and Technology
• /
• 제56권2호
• /
• pp.601-610
• /
• 2024

This paper gives an extensive analysis on the characterization of xenon isotopic ratios for various nuclear reactors and nuclear explosions through neutronic depletion codes. The results of the characterization can be used for discriminating the sources of the xenon isotopes' release among the nuclear explosions and nuclear reactors. The considered sources of the xenon radionuclides do not only include PWR, CANDU, and nuclear explosions using uranium and plutonium bombs, but also IRT-200 and 5MWe Yongbyon (MAGNOX reactor) research reactors operated in North Korea. A new data base (DB) on xenon isotopic activity ratios was produced using the results of the characterization, which can be used in discrimination of the sources of xenon isotopes. The results of the study show that 5MWe Yongbyon reactor has quite different characteristics in ¹³⁵Xe/¹³³Xe ratio from the PWRs and the nuclear reactors have different characteristics in ¹³⁵Xe/¹³³Xe ratios from the nuclear explosions.

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 2005년도 춘계학술발표회
• /
• pp.135-136
• /
• 2005

• Nuclear Engineering and Technology
• /
• 제52권6호
• /
• pp.1131-1136
• /
• 2020

Xenon behaves differently in molten salt reactors (MSRs) compared to solid fuel reactors. This behavior needs exploring due to the large reactivity effect of the ¹³⁵Xe isotope, given the current interest in MSR power plant development for commercial deployment. This paper focuses on select topics in xenon transport, reviews relevant past works, and proposes specific research questions to advance the state of the art in each of the focus areas. Specifically, the paper discusses the issue of xenon solubility in MSRs, the behavior of particulates circulating in MSR fuel salt and its influence on the xenon transport, the possibility of ionization of xenon atoms which changes its effective size and thus affects its mass transport, and finally the issue of circulating void fraction and how it is measured. This work presents specific recommendations for MSR designers to research the limits of Henry's law validity, circulating particulate scrubbers, validity of mass transport coefficients in high radiation fields, and the effects of pump speed on circulating void fraction.

• Bulletin of the Korean Chemical Society
• /
• 제33권2호
• /
• pp.511-514
• /
• 2012

A continuous flow hyperpolarized (HP) $^{129}Xe$ NMR spectroscopy was employed for the first time to investigate $TiO_2$ nanotubes (Ti-NTs) synthesized from commercial nanoparticles with different reaction times. A single peak attributing to channels for Ti-NTs was observed for variable temperature HP $^{129}Xe$ NMR spectra. It was also noted that there is alteration in value for heat of adsorption, ${\Delta}H$ from $12.6{\pm}1.3$ to $16.4{\pm}0.4kJ/mol$ and variation in chemical shift of the xenon adsorbed in channels, ${\delta}_s$ from $120{\pm}2\sim135{\pm}9ppm$ which were closely correlated to channel length and it was shown that P25-24 Ti-NTs with longest channel is most favorite Ti-NTs for Xe adsorption.

• 한국세라믹학회지
• /
• 제30권3호
• /
• pp.181-188
• /
• 1993

The sintering and renitridation behaviors of ultrafine Si3N4 powder compacts, which were heavily oxidized and/or free-Si rich, were investigated with particular attentiion to microstructures. The specimens were heated without restoring to additives and pressure by controlling heating process attained a Xe image apparatus. The effect of particle size, free-Si contents, decomposition and renitridation, were investigated. When fired to 1$650^{\circ}C$ within 15 sec and then immediately held at 135$0^{\circ}C$ for 10min N2 atmosphere, significant densification took place in the limited region, in addition to decreasing oxygen contents to less than 0.3wt%. On the other hand, specimens decomposed due to overheating at the initial stage were rapidly renitridated at the relatively lower temperature of the holding stage. And, then, the activation energy for the renitridation was calculated to be 49kcal/mole.

• 한국세라믹학회지
• /
• 제32권7호
• /
• pp.832-838
• /
• 1995

The densifying behavior of ultrafine amorphous Si3N4 (about 20 nm)-$\beta$-SiC (about 40~80 nm) powders (O2 : 1.3~15wt%, 0$700^{\circ}C$ within 15 sec and then immediately cooled and held at 135$0^{\circ}C$ for 10 min in N2 atmosphere without resorting to additives using a Xe image heating apparatus. Using an ultrafine pure Si3N4 powder with particle size less than 30nm, further more, mixed with an appropriate amount of $\beta$-SiC, was found to be advantageous to obtain uniform and homogeneous microstructure. In addition, ultrafine Si3N4 powders were also proved to be effective as sintering additive on densifying large sized Si3N4 powder compacts.

• Nuclear Engineering and Technology
• /
• 제13권4호
• /
• pp.264-276
• /
• 1981

TRIGA Mark-III 원자로의 핵특성을 실제운전상태와 유사하게 모사할 수 있는 해석절차를 개발하였다. 계산에 사용한 전산코드는 다군중성자확산 연소계산코드인 CITATION이고 채택한 중성자에너지군의 수는 TRIGA형 원자로에서 일반적으로 사용하는 7군(고속영역 3, 열영역 4)이다. 직접적인 3차원 계산이 현실적으로 불가능하므로 평면 2차원계산과 원통형 2차원 계산으로 3차원 효과를 기하였다. 연구로와 같이 노심이 작은 원자로에 대하여는 중성자평형에서 buckling에 의한 효과가 매우 크기 때문에 이를 정확하게 나타내는 방법의 개발에 중점을 두었다. 본 연구에서는 에너지군 또는 영역에 무관한 buckling을 중성자 수송이론으로 산출하는 전형적인 방법을 사용하지 않고 중성자 확산이론으로서 에너지군별, 영역별 buckling을 산출하였으며, 이를 이용하여 수행한 노심계산의 결과는 만족스러웠다. 계산시 노심은 원자로수조의 중앙부에 있는 것으로 하고 제어봉은 완전히 인출되었으며 동위원생산용 조사시료는 없는 것으로 가정하였다. 계산결과로서 연소에 따른 초과반응도가의 변화, 운전이력에 따른 Xe-135 독작용의 변화, 회전조사시료대의 반응도가를 산출하고 이를 실제 운전자료와 비교하였다. 또한 중성자속 및 출력분포, 노심 각 조사시설에서의 중성자 스펙트럼등에 대한 계산결과도 제시하였다.

• Nuclear Engineering and Technology
• /
• 제52권6호
• /
• pp.1099-1109
• /
• 2020

The performance of gadolinium burnable absorber (GdBA) for reactivity control in UO₂ and (U, Th)O₂ fuels and its impact on spent fuel characteristics was performed. Five fuel assemblies: one without GdBA fuel rod and four each containing 16, 24, 34 and 44 GdBA fuel rods in both fuels were investigated. Reactivity swing in all the FAs with GdBA rods in UO₂ fuel was higher than their counterparts with similar GdBA fuel rods in (U, Th)O₂ fuel. The excess reactivity in all FAs with (U, Th)O₂ fuel was higher than UO₂ fuel. At the end of single discharge burn-up (~ 49.64 GWd/tHM), the excess reactivity of (U, Th) O₂ fuel remained positive (16,000 pcm) while UO₂ fuel shows a negative value (-6,000 pcm), which suggest a longer discharge burn-up in (U, Th)O₂ fuel. The concentration of plutonium isotopes and minor actinides were significantly higher in UO₂ fuel than in (U, Th)O₂ fuel except for ²³⁶Np. However, the concentration of non-actinides (gadolinium and iodine isotopes) except for ¹³⁵Xe were respectively smaller in (U, Th)O₂ fuel than in UO₂ fuel but may be two times higher in (U, Th)O₂ fuel due to its potential longer discharge burn-up.