• 제목/요약/키워드: Post-irradiation experiments

검색결과 14건 처리시간 0.018초

FAST irradiations and initial post irradiation examinations - Part I

  • G. Beausoleil;L. Capriotti;B. Curnutt;R. Fielding;S. Hayes;D. Wachs
    • Nuclear Engineering and Technology
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    • 제54권11호
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    • pp.4084-4094
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    • 2022
  • The Advanced Fuels Campaign Fission Accelerated Steady-state Test (FAST) at Idaho National Laboratory (INL) completed its first irradiation cycle within the Advanced Test Reactor (ATR). The test focused on the irradiation of alloy fuel forms for use in sodium fast reactors. The first cycle of FAST testing was completed and four rodlets were removed for the initial post irradiation examination (PIE). The rodlet design and irradiation conditions were evaluated using Monte Carlo N-Particle (MCNP) for as-run power history and COMSOL for temperature analysis. These rodlets include a set of low burnups (~2.5 % fissions per initial metal atoms [%FIMA]), control rodlets, and a helium-bonded annular rodlet (4.7 %FIMA). Nondestructive PIE has been completed and includes visual inspection, neutron radiography and gamma scanning of the FAST capsules and rodlets. Radiography confirmed the integrity of the experiments, revealed that the annulus in the annular fuel was filled at a modest burnup (4.7 %FIMA), and indicated potential slumping of the cooler rodlets at lower burnup. Precision gamma scanning indicated mostly usual fission product behavior, except for cesium in the He-bonded annular fuel. Future destructive PIE will be necessary to fully interpret the effects of accelerated irradiation on U-Zr metallic fuel behavior.

放射線이 照射된 MIS capacitor의 電荷 蓄積 및 flat band 전압 이동에 대한 實驗 및 數値的 硏究 (Experiments & numerical analysis of charge accumulation and flat band voltage shifts in irradiated MIS capacitor)

  • 황금주;김홍배;손상희
    • 대한전기학회논문지
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    • 제44권4호
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    • pp.483-489
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    • 1995
  • To investigate the mechanism generated by irradiation in the insulator layer irradiated MIS (Metal - Insulator - Semiconductor) device, the various types of MIS capacitors depending on insulator thickness, insulator types and implanted impurities are fabricated on the P-type wafer. MIS capacitors exposed by 1Mrad Co$^{60}$ .gamma.-ray are measured for flat band voltage and charge density shifts pre- and post-irradiation. The measuring results of post-irradiation show the flat band voltage shifting toward negative direction and charge density increasing regardless of parameters. This results have a good agreement with calculated data by computer simulation. Si$_{3}$N$_{4}$ layers have a good radiation-hardness than SiO$_{2}$ layers compared to the results of post-irradiation. Also, radiation-induced negative trap is discovered in the implanted insulator layer. Using numerical analysis, four continuty equations (conduction-band electrons continuity equation, valence-band holes continuity equation, trapped electrons continuity equation, trapped holes continuity equation) are solved and charge distributions according to the distance and Si-Insulator interface states are investigated.

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감마선 조사와 조사 후 보존제 처리가 절화 장미 및 국화의 수명에 미치는 영향 (Effect of Gamma Irradiation and Post-Irradaition Treatment of Preservatives on the Cut Flower Longevity of Rose and Mum.)

  • 박인환;정연승;이월순;권중호;변명우
    • 한국식품저장유통학회지
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    • 제6권3호
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    • pp.286-291
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    • 1999
  • 본 연구는 감마선 조사 시기, 강도 및 조사 후 보존제 처리가 절화장미와 국화의 수명에 미치는 영향을 알기 위하여 시행하였던 바 얻은 결과는 다음과 같았다. 절화장미의 경우 감마선 조사 강도가 0.5 KGy 까지는 절화품질에 미치는 영향이 적다고 할 수 있었으나, 이 보다 강한 조사구에서는 절화장미의 품질이 매우 악화되었으며, 조사 후 설탕용액에 침지한 것은 0.75 KGy 처리구까지 절화의 품질 유지효과가 인정되었다. 조사 후 절화보존제 침지 처리의 효과 실험에서는 2% sucrose, 0.2% silver nitrate, 1.0% Crysal 처리구에서 각각 선도 유지 효과가 어느 정도 인정되었으나, silver nitrate 처리구에서는 절화기부의 갈변부패가 매우 심한 것에서 절화수명의 연장에는 별 효과가 없었음을 알 수 있었다. 절화국화의 경우에는 감마선 조사 강도가 강해질수록 관산가치가 급격히 저하되었으며, 2.0KGy의 강도로 조사한 감마선 처리구에서는 증류수 및 HQS에 침지한 절화를 제외하고 다른 절화 보존제 처리구에서는 절화 수명이 급격히 저하되었다. 절화 보존제의 처리효과 중에 설탕용액의 침지 효과가 제일 우수하였는데, 감마선 무조사구에서 절화가 완전히 시들 때까지도 어느 정도 꽃을 관상 할 수 있을 정도로 절화수명은 유지되었다.

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동박과 PSR간의 접합력 향상에 관한 연구 (Study on the Improvement of Adhesion between Cu Laminate and PSR)

  • 김경섭;정승부;신영의
    • Journal of Welding and Joining
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    • 제17권2호
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    • pp.61-65
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    • 1999
  • Because of the need for packages which accommodate high pin count, high density and high speed device, PBGA(plastic ball grid array) package gets more spotlight. But the substrate material which is used for PBGA package is in nature susceptible to moisture penetration. The objective of the study is to find out the path of delamination in the stacked structure of substrate. To increase the adhesion between the cooper laminate and PSR(photo solder resist) which is the weakest part, experiments were performed by changing parameters of printing pre-treatment and post-treatment process. As a result of experiments, the factor effects on the adhesion between the cooper laminate and PSR is caused by all of the pre-treatment and post-treatment condition. A considerable change was observed depending on the amount of UV irradiation after thermal cure which is typical of printing post-treatment condition rather than pre-treatment condition.

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In-pile tritium release behavior and the post-irradiation experiments of Li4SiO4 fabricated by melting process

  • Linjie Zhao;Mao Yang;Chengjian Xiao;Yu Gong;Guangming Ran;Xiaojun Chen;Jiamao Li;Lei Yue;Chao Chen;Jingwei Hou;Heyi Wang;Xinggui Long;Shuming Peng
    • Nuclear Engineering and Technology
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    • 제56권1호
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    • pp.106-113
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    • 2024
  • Understanding the tritium release and retention behavior of candidate tritium breeder materials is crucial for breeder blanket design. Recently, a melt spraying process was developed to prepare Li4SiO4 pebbles, which were subsequently subjected to the in-pile tritium production and extraction platform in China Mianyang Research Reactor (CMRR) to investigate their in-situ tritium release behavior and irradiation performance. The results demonstrate that HT is the main tritium release form, and adding hydrogen to the purge gas reduces tritium retention while increasing the HT percent in the purge gas. Post-irradiation experiments reveal that the irradiated pebbles darken in color and their grains swell, but the mechanical properties remain largely unchanged. It is concluded that the tritium residence time of Li4SiO4 made by melt spraying method at 467 ℃ is approximately 23.34 h. High-density Li4SiO4 pebbles exhibit tritium release at relatively low temperatures (<600 ℃) that is mainly controlled by bulk diffusion. The diffusion coefficient at 525 ℃ and 550 ℃ is 1.19 × 10-11 cm2/s and 5.34 × 10-11 cm2/s, respectively, with corresponding tritium residence times of 21.3 hours and 4.7 hours.

REVIEW OF 15 YEARS OF HIGH-DENSITY LOW-ENRICHED UMo DISPERSION FUEL DEVELOPMENT FOR RESEARCH REACTORS IN EUROPE

  • Van Den Berghe, S.;Lemoine, P.
    • Nuclear Engineering and Technology
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    • 제46권2호
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    • pp.125-146
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    • 2014
  • This review aims to provide a synthesis of the knowledge generated and the lessons learned in roughly 15 years of UMo dispersion fuel R&D in Europe through a series of irradiation experiments. A lot of irradiations were also performed outside of Europe, particularly in the USA, Russia, Canada, Korea and Argentina. In addition, a large number of out-of-pile investigations were done throughout the world, providing support to the understanding of the phenomena governing the UMo behaviour in pile. However, the focus of this article will be on the irradiations and Post-Irradiation Examination (PIE) results obtained in European experiments. The introduction of the article provides a historic overview of the evolution and progress in the high density UMo dispersion fuel development. The ensuing sections then provide further details on the various phases of the development, from the UMo dispersion in a pure Al matrix through the addition of Si to the matrix to address the interaction layer formation and finally to the more advanced solutions to the excessive swelling encountered in various experiments. This review was based only on published results or results that are currently in the process of being published.

Effect of gamma irradiation on post-harvest quality of king oyster mushrooms (Pleurotus eryngii )

  • Seo-Joon Yeom;Geon-Ah Lee;Sang-Su Kim;Ki-Nam Yoon;Beom-Seok Song;Jong-Heum Park;Woo-Jin Jung;Young-Min Kim;Jae-Kyung Kim
    • 한국식품저장유통학회지
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    • 제30권5호
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    • pp.729-742
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    • 2023
  • The consumption of king oyster mushrooms has steadily increased owing to their unique flavor and delicate texture. This study extended the storage period of king oyster mushrooms (Pleurotus eryngii ) via gamma irradiation. Irradiated samples (0, 0.5, 1, 2, and 3 kGy) were stored at 4℃ with 80% relative humidity for up to 28 days, and the experiments were conducted every 7 day. Microbiological analysis revealed a dose-dependent reduction in total aerobic bacteria, Pseudomonas spp., and yeasts and molds, and gamma irradiation above 2 kGy effectively controlled microbial contamination for up to 28 days. At the 28th day of storage, the irradiated king oyster mushrooms exhibited delayed browning through the reduction of tyrosinase activity. Moreover, firmness reduction (%) was 80.59±1.89% for the non-irradiated group and 42.80±1.28, 34.57±1.13, 31.05±3.24, and 39.73±0.94% for the irradiated group (0.5, 1, 2, and 3 kGy), respectively. These results were supported by the scanning electron microscopy photos, which showed smaller pores in the irradiated group than in the non-irradiated group. This study demonstrated that 2 kGy of gamma irradiation effectively reduces microbial contamination and delays the browning and softening of king oyster mushrooms for up to 28 days.

Front-end investigations of the coated particles of nuclear fuel samples - ion polishing method

  • Krajewska, Zuzanna M.;Buchwald, Tomasz;Tokarski, Tomasz;Gudowski, Wacław
    • Nuclear Engineering and Technology
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    • 제54권6호
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    • pp.1935-1946
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    • 2022
  • The investigations of the coated-particles of nuclear fuel samples are carried out in three stages: front-end, irradiation in the reactor core, and post-irradiation examination. The front-end stage is the initial analysis of the failures rates of produced samples before they are placed in the reactor core. The purpose of the verification is to prepare the particles for an experiment that will determine the degree of damage to the coated particles at each stage. Before starting experiments with the samples, they must be properly prepared. Polishing the samples in order to uncover the inner layers is an important, initial experimental step. The authors of this paper used a novel way to prepare samples for testing - by applying an ion polisher. Mechanical polishing used frequently for sample preparations generates additional mechanical damages in the studied fuel particle, thus directly affecting the experimental results. The polishing methods were compared for three different coated particles using diagnostic methods such as Raman spectroscopy, scanning electron microscopy, and confocal laser scanning microscopy. Based on the obtained results, it was concluded that the ion polishing method is better because the level of interference with the structures of the individual layers of the tested samples is much lower than with the mechanical method. The same technique is used for the fuel particles undergone ion implantation simulating radiation damage that can occur in the reactor core.

전자빔 조사에 의한 오염토양중의 PAHs및 PCBs의 분해 (Removal of PAHs and PCBs in artificially contaminated soils using electron beam irradiation)

  • 김석구;정장식;김이태;배우근
    • 한국지하수토양환경학회지:지하수토양환경
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    • 제7권3호
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    • pp.61-70
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    • 2002
  • 난분해성 유기오염물로 오염된 토양 복원을 위한 전자빔 직접조사 공정의 적용가능성을 평가하기 위하여 PAHs 와 PCBs로 오염시킨 토양에 대한 전자빔 조사실험을 수행하였다 전자빔 흡수선량 600kGy에서 PAHs의 제거율은 약 97% 이었고 PCBs는 800kGy에서 약 70%가 제거되었다. PAHs는 PCBs에 비해 낮은 흡수선량에서도 높은 제거율을 나타내었다. 오염물의 분해는 가속된 전자와 물의 반응으로 생성된 반응성 높은 중간생성물에 의한 산화/환원 반응보다는 고에너지 전자와 대상오염물의 직접적인 반응에 기인한다. 전자빔 조사에 의해 난분해성 오염물질로 오염된 토양을 효과적으로 제거할 수 있으나 이를 위해 높은 에너지를 요구하므로 비경제적인 공법이 될 수 있다. 따라서, 전자빔 직접조사 공정보다는 기존 토양복원 공법의 후처리 공정으로 개발하는 것이 경제적이고 실용화 가능할 것으로 판단된다.

임신 ddy Mice에서 착상전기 방사선 조사에 따른 산전 사망 및 외부 기형 발현 (Prenatal Deaths and External Malformations Caused by X-Irradiation during the Preimplantation Period of ddy Mice)

  • 노희정;최일봉;구연화
    • Radiation Oncology Journal
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    • 제16권3호
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    • pp.233-243
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    • 1998
  • 목적 : 착상전기의 진단 및 치료 영역의 방사선 조사가 임신 ddy mouse에서 산전 사망과 외부 기형을 유발하는지, Compaction전 시기의 반응에 시기별 차이가 있는지 그리고 계통에 따르는 차이가 있는지 여부를 알아 보고자 하였다. 대상 및 방법 : 임신 ddy mouse 대조군 32 마리와 실험군 53 마리를 대상으로 연구를 시행하였으며, 실험군에 대한 방사선 조사는 착상전의 중요한 두 시기인 24 h p.c.와 48 h p.c.에 진단 영역에서도 이용되는 방사선 선량인 0.1, 0.5 Gy를 포함하여 0.75, 1.5, 3 Gy를 조사한 후, 임신 18일에 희생시켜 산전 사망 즉 착상전 사망, 배 사망 및 태아 사망과 외부 기형을 관찰하였다. 결과 : 1) 착상전 사망은 24 h p.c. 및 48 h p.c.에서 대조군에 비해 현저하게 많이 발생하였으며 선량 의존성을 나타냈고, 시기별 한계 선량은 각각 0.05 Gy 및 0.075 Gy이상으로 24 h p.c.가 48 h p.c.보다 방사선에 대한 감수성이 높은 시기임을 알 수 있었다. 2) 배 사망은 48 h p.c.의 0.1 Gy 조사군을 제외한 24 h p.c. 및 48 h p.c.의 모든 조사군에서 대조군에 비해 많이 발생하였고 선량 의존성을 보였으며, 한계 선량은 각각 0.1 Gy 및 0.25 Gy이상으로 24 h p.c.가 48 h p.c.보다 방사선 조사에 의한 배 사망의 감수성이 높았다. 3) 태아 사망은 24 h p.c. 및 48 h p.c.의 실험군 모두에서 발생하지 않았다. 4) 외부 기형은 24 h p.c. 실험군에서 뇌노출 기형 2예, 안검결손 기형 3예, 무안구증 3예, 구개열 2예, 복벽 파열 2예, 꼬리 기형 2예 및 다리 기형 1예, 국소 복벽 결손 1예 등이 발생하였는데, 그 중 진단 영역의 방사선 선량인 0.1 Gy군에서 안검결손 기형 1예, 복벽 파열 1예, 0.5 Gy군에서 뇌노출 기형 1예, 꼬리 기형 2예 및 다리 기형 1예가 발생하여 대조군에 비해 통계적으로 유의한 증가를 나타냈으며 이 시기의 한계선량은 0.2 Gy이상이었다. 48 h p.c.군에서도 안검결손 기형 1예, 꼬리 기형 2예가 발생하였으나 대조군과 통계적인 유의차가 없었다. 결론 : 이상의 결과를 통해 치료 영역뿐만 아니라 진단 영역의 방사선 조사로도 착상전기 임신 ddy mouse에서 착상전 사망 및 배 사망이 발생하고 24 h p.c.에서는 기형도 유발되어 이 시기의 방사선 영향이 "all-or-none" 반응만 일어나는 것이 아님을 알 수 있었으며, 24 h p.c.가 48 h p.c.보다 방사선 감수성이 높은 시기라는 사실과 함께 다른 연구 결과들과 비교하여 계통에 따르는 차이가 있음을 알 수 있었다. 그러므로 가임기 여성의 방사선 진단 및 치료시 Rugh의 10일 법칙을 적용하여 착상전기 방사선 조사로 인한 부작용들을 적극적으로 예방하는 것이 매우 중요하다고 생각한다.

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