• 한국방사선학회논문지
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• 제16권2호
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• pp.185-194
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• 2022

국제적으로 과거 원자력 및 방사선 관련 활동으로 인해 부지 및 토양 등이 오염된 레거시 부지에 대한 해결과 관리가 관심의 대상이 되고 있다. 국내에서도 연구로 해체 등의 사례가 있었으며 북한은 최신화된 안전규제가 적용되고 있지 않을 가능성이 있으며 관련하여 운영 기록 등의 관리되지 않고 있을 가능성이 있어 레거시 부지가 될 가능성이 크다. 따라서 본 연구에서는 레거시 부지의 해결에 대한 국제 사례를 검토하고 이로부터 레거시 부지의 특성과 문제점을 파악하였다. 이에 국제 관리 기준에 따른 레거시 부지 대응 절차와 규제 체계를 분석하고 규제 체계 개발 시 고려되어야 할 사항을 도출 하였다. 레거시 부지 대응 방안의 개발은 향후 레거시 부지 발생시 대응과 레거시 부지의 발생을 예방하는데 사용될 수 있다.

• 방사성폐기물학회지
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• 제19권3호
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• pp.387-419
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• 2021

The challenges facing companies and institutions surrounding civil nuclear decommissioning are diverse and many, none more so than those faced in the United Kingdom. The UK's Generation I nuclear power plants and early research facilities have left a 'Nuclear Legacy' which is in urgent need of management and clean-up. Sellafield is quite possibly the most ill-famed nuclear site in the UK. This complex and challenging site houses much of what is left from the early days of nuclear research in the UK, including early nuclear reactors (Windscale Piles, Calder Hall, and the Windscale Advanced Gas Cooled Reactor) and the UK's early nuclear weapons programme. Such a legacy now requires careful management and planning to safely deal with it. This task falls on the shoulders of the Nuclear Decommissioning Authority (NDA). Through a mix of prompt and delayed decommissioning strategies, key developments in R&D, and the implementation of site licenced companies to enact decommissioning activities, the NDA aims to safety, and in a timely manner, deal with the UK's nuclear legacy. Such approaches have the potential to influence and shape other such approaches to nuclear decommissioning activities globally, including in Korea.

• 방사성폐기물학회지
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• 제20권1호
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• pp.65-98
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• 2022

The nuclear legacy that remains in the United Kingdom (UK) is complex and diverse. Consisting of legacy ponds and silos, redundant reprocessing plants, research facilities, and non-standard or one-off reactor designs, the clean-up of this legacy is under the stewardship of the Nuclear Decommissioning Authority (NDA). Through a mix of prompt and delayed decommissioning strategies, the NDA has made great strides in dealing with the UK's nuclear legacy. Fuel debris and sludge removal from the legacy ponds and silos situated at Sellafield, as part of a prompt decommissioning strategy for the site, has enabled intolerable risks to be brought under control. Reactor defueling and waste retrievals across the Magnox fleet is enabling their transition to a period of care and maintenance; accelerated through the adopted 'Lead and Learn' approach. Bespoke decommissioning methods implemented by the NDA have also enabled the relevant site licence companies to tackle non-standard reactor designs and one-off wastes. Such approaches have potential to influence and shape nuclear decommissioning decision making activities globally, including in Korea.

• 정보처리학회논문지D
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• 제12D권5호
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• pp.797-806
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• 2005

미국 국방성에서 주관한 시뮬레이션 표준인 HLA(High Level Architecture)의 목적은 시뮬레이션 소프트웨어들 사이의 상호 호환을 용이하게 하고 그들 구성 요소들의 재사용을 촉진하는데 있다. 산업 현장에는 HLA가 시뮬레이션 표준이 되기 이전에 개발된 많은 시뮬레이션 소프트웨어들이 있다. 레거시 시뮬레이션들을 HLA를 사용한 패더레이션으로의 통합은 M&S(Modeling 고 Simulation) 영역에서 중요한 연구 주제이다. 원자력과 우주항공 같은 임무 완수가 중요한 산업의 레거시 시뮬레이션 소프트웨어들은 일반적으로 Fortran 언어를 사용한다. 하지만 HLA가 Fortran 언어를 지원하고 있지 않기 때문에 그들의 재사용은 쉽지 않다. 본 논문은 레거시 시뮬레이션 소프트웨어의 변경을 최소화하면서 HLA 패더레이션으로 이전을 용이하게 하는 통합 방법을 제시한다. 패더레이션에 참여하는 각 패더레이트는 실행 시간에 생성되는 공유메모리를 통하여 통신하는 분리된 실행을 갖는다. 발행과 접수를·위한 두 가지 유형의 공유메모리 블록이 사용된다 레거시 시뮬레이션 소프트웨어에서 사용되는 전역변수 선언 블록은 발행과 접수를 위하여 분할되고 HLA FOM 설계를 위하여 객체 및 상호작용 클래스로 사상된다. 제안된 방법을 검증하기 위하여 플랜트 설계에 사용되고 있는 레거시 원자력 시뮬레이션 코드의 HLA 통합을 시도하였고 통합 결과를 관측하기 위하여 FMT(Federation Management Tool)를 사용하였다. FMT가 표시하는 진단정보는 본 연구가 제안하는 방법이 성공적이고 효과적으로 HLA 통합에 사용될 수 있음을 보였다.

• 방사성폐기물학회지
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• 제19권3호
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• pp.339-352
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• 2021

Legacy waste from the decommissioned A-1 nuclear power plant in the Slovak Republic is scheduled for immobilisation within a tailored alkali borosilicate glass formulation, as part of ongoing site cleanup. The aqueous durability and characterisation of a simulant glass wasteform for Chrompik III legacy waste, was investigated, including dissolution experiments up to 112 days (90℃, ASTM Type 1 water). The wasteform was an amorphous, light green glassy product, with no observed phase separation or crystalline inclusions. Aqueous leach testing revealed a suitably durable product over the timescale investigated, comparing positively to other simulant nuclear waste glasses and vitreous products tested under similar conditions. Iron and titanium rich precipitates were observed to form at the surface of monolithic samples during leaching, with the formation of an alkali deficient alteration layer behind these at later ages. Overall this glass appears to perform well, and in line with expectations for this chemistry, although longer-term testing would be required to predict overall durability. This work will contribute to developing confidence in the disposability of vitrified Chrompik legacy wastes.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 춘계공동학술발표회요약집
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• pp.56.2-56
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• 2002

• Nuclear Engineering and Technology
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• 제48권2호
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• pp.404-418
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• 2016

This paper presents a documentation and development method to facilitate the certification of scientific computing software used in the safety analysis of nuclear facilities. To study the problems faced during quality assurance and certification activities, a case study was performed on legacy software used for thermal analysis of a fuelpin in a nuclear reactor. Although no errors were uncovered in the code, 27 issues of incompleteness and inconsistency were found with the documentation. This work proposes that software documentation follow a rational process, which includes a software requirements specification following a template that is reusable, maintainable, and understandable. To develop the design and implementation, this paper suggests literate programming as an alternative to traditional structured programming. Literate programming allows for documenting of numerical algorithms and code together in what is termed the literate programmer's manual. This manual is developed with explicit traceability to the software requirements specification. The traceability between the theory, numerical algorithms, and implementation facilitates achieving completeness and consistency, as well as simplifies the process of verification and the associated certification.

• Nuclear Engineering and Technology
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• 제49권5호
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• pp.1010-1018
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• 2017

The European Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste project sought to develop best practices in the retrieval, treatment, and disposal of irradiated graphite including other irradiated carbonaceous waste such as structural material made of graphite, nongraphitized carbon bricks, and fuel coatings. Emphasis was given on legacy irradiated graphite, as this represents a significant inventory in respective national waste management programs. This paper provides an overview of the characteristics of graphite irradiated during its use, primarily as a moderator material, within nuclear reactors. It describes the potential techniques applicable to the retrieval, treatment, recycling/reuse, and disposal of these graphite wastes. Considering the lifecycle of nuclear graphite, from manufacture to final disposal, a number of waste management options have been developed. These options consider the techniques and technologies required to address each stage of the lifecycle, such as segregation, treatment, recycle, and ultimate disposal in a radioactive waste repository, providing a toolbox to aid operators and regulators to determine the most appropriate management strategy. It is noted that national waste management programs currently have, or are in the process of developing, respective approaches to irradiated graphite management. The output of the Treatment and Disposal of Irradiated Graphite and other Carbonaceous Waste project is intended to aid these considerations, rather than dictate them.

• 한국세라믹학회지
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• 제52권2호
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• pp.92-102
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• 2015

Current plans for legacy nuclear wastes stored in underground tanks at the U.S. Department of Energy's Hanford Site in Washington are that they will be separated into high-level waste and low-activity waste fractions that will be vitrified separately. Formulating optimized glass compositions that maximize the waste loading in glass is critical for successful and economical treatment and immobilization of these nuclear wastes. Glass property-composition models have been developed and applied to formulate glass compositions for various objectives for the past several decades. Property models with associated uncertainties combined with composition and property constraints have been used to develop preliminary glass formulation algorithms designed for vitrification process control and waste-form qualification at the planned waste vitrification plant. This paper provides an overview of the current status of glass property-composition models, constraints applicable to Hanford waste vitrification, and glass formulation approaches that have been developed for vitrification of hazardous and highly radioactive wastes stored at the Hanford Site.

• Nuclear Engineering and Technology
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• 제54권3호
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• pp.817-825
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• 2022

A recent benchmarking effort, under the auspices of the Organization for Economic Cooperation and Development (OECD) Nuclear Energy Agency (NEA), has been made to evaluate the current state of modeling and simulation tools available to model fluoride salt-cooled high temperature reactors (FHRs). The FHR benchmarking effort considered in this work consists of several cases evaluating the neutronic parameters of a 2D prismatic FHR fuel assembly model using the participants' choice of simulation tools. Benchmark participants blindly submitted results for comparison with overall good agreement, except for some which significantly differed on cases utilizing a molybdenum-bearing control rod. Participants utilizing more recently updated explicit isotopic cross sections had consistent results, whereas those using elemental molybdenum cross sections observed reactivity differences on the order of thousands of pcm relative to their peers. Through a series of supporting tests, the authors attribute the differences as being nuclear data driven from using older legacy elemental molybdenum cross sections. Quantitative analysis is conducted on the control rod to identify spectral, reaction rate, and cross section phenomena responsible for the observed differences. Results confirm the observed differences are attributable to the use of elemental cross sections which overestimate the reaction rates in strong resonance channels.