• Title/Summary/Keyword: Nuclear Acceptance

Search Result 209, Processing Time 0.06 seconds

Examination of Proliferation Resistance Assessment for Nuclear Fuel Cycles

  • Lee, Yoon-Hee;Lee, Kun-Jai
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2009.06a
    • /
    • pp.73-73
    • /
    • 2009
  • There are many factors to evaluate nuclear fuel cycle such as safety, public acceptance, economics, etc.. Transparency, proliferation, environment issues, public acceptance and safety are essential to expansion of nuclear industry and proliferation resistance is one of key constraints in the deployment of advanced nuclear energy systems. Proliferation resistance is being considered as one of the most important factors in assessing advanced and innovative nuclear systems. IAEA defmes proliferation resistance as characteristics of nuclear energy system that impedes the diversion or undeclared production of nuclear material [1]. Barriers to proliferation is consist of intrinsic and extrinsic barriers(institutional measures). Intrinsic barriers are characterized in material barriers and technical barriers in general. Material barriers is intrinsic, or inherent, qualities of materials that reduce the inherent desirability or attractiveness of the material as an explosive. Isotopic, chemical, radiological, mass and bulk, detectability barriers are considered as material barriers attributes [2]. Proliferation resistance is examined for several nuclear fuel cycles based on previous study which is focused on the intrinsic barriers [3-4]. Pyroprocessing and DUPIC are considered as reprocessing technologies in Korea and the PWR direct disposal is considered. Comparative assessments of the proliferation attributes and merits of different fuel cycle systems will be performed and the optimal back-end fuel cycle and strategy will be proposed.

  • PDF

Magnesium potassium phosphate cements to immobilize radioactive concrete wastes generated by decommissioning of nuclear power plants

  • Pyo, Jae-Young;Um, Wooyong;Heo, Jong
    • Nuclear Engineering and Technology
    • /
    • v.53 no.7
    • /
    • pp.2261-2267
    • /
    • 2021
  • This paper evaluates the efficacy of magnesium potassium phosphate cements (MKPCs) as waste forms for the solidification of radioactive concrete powder wastes produced by the decommissioning of nuclear power plants. MKPC specimens that contained up to 50 wt% of simulated concrete powder wastes (SCPWs) were evaluated. We measured the porosity and compressive strength of the MKPC specimens, observing them using scanning electron microscopy and X-ray diffraction. The addition of SCPWs reduced the porosity and increased the compressive strength of the MKPC specimens. Struvite-K crystals were well-synthesized, and no additional crystal phase was formed. After thermal cycling and after immersion, MKPC specimens with 50 wt% SCPWs satisfied the waste-acceptance criteria (WAC) for compressive strength. Semi-dynamic leaching tests were performed using the ANS 16.1 method; the leachability indices of Cs, Co, and Sr were 11.45, 17.63, and 15.66, respectively, which also satisfy the WAC. Thus, MKPCs can provide stable matrices to immobilize radioactive concrete wastes generated by the decommissioning of nuclear power plants.

Development of Performance Analysis Methodology for Nuclear Power Plant Turbine Cycle Using Validation Model of Performance Measurements (원전 터빈사이클 성능 데이터의 검증 모델에 의한 성능분석 기법의 개발)

  • Kim, Seong-Geun;Choe, Gwang-Hui
    • Transactions of the Korean Society of Mechanical Engineers B
    • /
    • v.24 no.12
    • /
    • pp.1625-1634
    • /
    • 2000
  • Verification of measurements is required for precise evaluation of turbine cycle performance in nuclear power plant. We assumed that initial acceptance data and design data of the plant could provide correlation information between performance data. The data can be used as sample sets for the correct estimation model of measurement value. The modeling was done practically by using regression model based on plant design data, plant acceptance data and verified plant performance data of domestic nuclear power plant. We can construct more robust performance analysis system for an operation nuclear power plant with this validation scheme.

Estimation of radionuclides leaching characteristics in different sized geopolymer waste forms with simulated spent ion-exchange resin

  • Younglim Shin;Byoungkwan Kim;Jaehyuk Kang;Hyun-min Ma;Wooyong Um
    • Nuclear Engineering and Technology
    • /
    • v.55 no.10
    • /
    • pp.3617-3627
    • /
    • 2023
  • This study presents a method to solidify spent ion-exchange resin (IER) in a metakaolin-based geopolymer and shows results of mechanical strength, immersion, leaching, irradiation, and thermal cycling tests for waste acceptance criteria (WAC) to repository. The geopolymer waste form with 20 wt% of simulated spent IER met the WAC in South Korea (ROK), and the leaching tests of various sized-waste forms up to 15.0 × 30.0 cm and waste loadings up to 20 wt% for 1-5 d and 1-90 d achieved a leachability index, Li > 6. In a leaching test for 5 d, the cumulative fraction leached (CFL) for Cs, which leached the most, was linearly correlated with the square root of leaching time for all waste forms, and Li increased as the size of the waste form increased. The CFL was also correlated with elapsed time in the 90 d leaching test. The correlations among CFL, time, and volume-to-surface area ratio of waste forms used to estimate the Li of Cs of a 200-L sized geopolymer with 15 wt% IER showed the Li values as 14.73 (5 d) and 17.71 (90 d), respectively, indicating that the large-sized geopolymer waste form met the WAC.

Local Residents' Perception Analysis of Nuclear Power after the Thyroid Cancer Damage Lawsuit Adjacent to the Nuclear Plant (원전주변 갑상선암 발병 피해 소송 사건 이후 원자력에 대한 지역주민 인식 분석)

  • Lee, Jae-Heon;Kim, Jung-Hoon
    • Journal of the Korean Society of Radiology
    • /
    • v.10 no.8
    • /
    • pp.583-590
    • /
    • 2016
  • The subjects in this study are the residents of Busan, analyzing the perception gap between the residents adjacent to the nuclear plant and living in town, about the lawsuit of thyroid cancer damage nearby the nuclear plant, to distinguish the citizen's acceptance level about the nuclear power. 551 people(269 people adjacent to nuclear plant, 282 people in town) were face-to-face surveyed and the result showed that people's perceptions of the nuclear power has changed after the thyroid cancer damage lawsuit. In the case of the residents adjacent to the nuclear plant, it became clear that the negative perception of nuclear power became stronger due to increasing distrust and anxiety about nuclear power after the lawsuit of thyroid cancer damage nearby the nuclear plant. On the other hand, people living in town showed their positive perceptions of nuclear power despite the thyroid cancer damage lawsuit. However, two-sided perception was shown compared to the acceptance of nuclear power, since the safety and reliability of the nuclear power was analyzed as negative perception. Therefore, for the constant increased use of nuclear power in the future, national understanding and credibility, including the communication with the nation or the residents in the neighboring area of nuclear power plant, will be necessary.

Development of ISI UT Auto Flaw Evaluation and Acceptance Module of Nuclear Power Plants (원전 ISI UT 자동 결함평가 및 판정 모듈 개발)

  • Park, Ik-Keun;Park, Un-Su;Kim, Hyun-Mook;Kim, Chung-Seok;Um, Byong-Guk;Lee, Jong-Po
    • Proceedings of the KSME Conference
    • /
    • 2000.11a
    • /
    • pp.212-218
    • /
    • 2000
  • The importance and role of pre-/in-service inspection(PSI/ISI) for nuclear power plant(NPP) components are intimately related to plant design, safety, reliability, operation, etc. In this paper, for an effective and efficient management of large amounts of PSI/ISI data in NPPs, an intelligent database program(WS-IDPIN) for PSI/ISI data management of NPP was developed. WS-IDPIN program enables the prompt extraction of previously conducted PSI/ISI conditions and results so that the time-consuming data management, painstaking data processing and analysis in the past are avoided. Furthermore, development of ISI UT auto flaw evaluation and acceptance module based on ASME Code Sec. XI were presented. This module can be used for any angle beam examination from flat plate to spherical shapes as selected by the proper azimuthal angle. This program can be further developed as a unique PSI/ISI data management expert system.

  • PDF