연구동향 분석

Evaluation of the reutilization of used nuclear fuel in a PWR core without reprocessing

Zafar Iqbal Zafar 박윤서 김명현 2019년

논문상세정보
인용/피인용
' Evaluation of the reutilization of used nuclear fuel in a PWR core without reprocessing' 의 주제별 논문영향력
논문영향력 선정 방법
논문영향력 요약
주제
  • Fuel management
  • Inventory assay
  • Reconstruction
  • Used nuclear fuel
동일주제 총논문수 논문피인용 총횟수 주제별 논문영향력의 평균
188 0

0.0%

' Evaluation of the reutilization of used nuclear fuel in a PWR core without reprocessing' 의 참고문헌

  • The use of passive, secure cells for processing of highly active nuclear wastes
    C. Phillips [2007]
  • Technical and economic limits to fuel burnup extension
  • Remote Technology Applications in Spent Fuel Management
  • Nuclear Reactor Engineering
  • Nuclear Design and Core Physics Characteristics of the Ulchin Nuclear Power Plant Unit 5 Cycle 1
  • Nuclear Design Report for Ulchin Nuclear Power Plant Unit 5 Cycle 6
  • Nuclear Design Report for Ulchin Nuclear Power Plant Unit 5 Cycle 5
  • Nuclear Design Report for Ulchin Nuclear Power Plant Unit 5 Cycle 4
  • Nuclear Design Report for Ulchin Nuclear Power Plant Unit 5 Cycle 3
  • Nondestructive assay measurements using the RPI lead slowing-down spectrometer
    B. Becker [2013]
  • MASTER-3.0: Multi-purpose Analyzer for Static and Transient Effects of Reactors
    J. B. Oh [2002]
  • MASTER 3.0 User's Manual
  • Leaking Fuel Impacts and Practices
    Z. Hozer [2012]
  • Investigation into fuel pin reshuffling options in PWR incore fuel management for enhancement of efficient use of nuclear fuel
    A. T. Daing [2014]
  • Improved Retrieval Technique of Pin-wise Composition for Spent Fuel Recycling
  • IAEA-TECDOC-1050, Poolside inspection, repair and reconstitution ofLWR fuel elements
    [1997]
  • Handbook of Small Modular Nuclear Reactors
  • HELIOS Program
  • HELIOS Methods
  • Developing and analyzing long-term fuel management strategies for an advanced Small Modular PWR
    A. Hedayat [2017]
  • Construction of linear empirical core models for pressurized water reactor in-core fuel management