A Parametric Study of the DUPIC Fuel Cycle to Reflect Pressurized Water Reactor Fuel Management Strategy

Daniel Rozon; Wei Shen

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A Parametric Study of the DUPIC Fuel Cycle to Reflect Pressurized Water Reactor Fuel Management Strategy

机译：DUPIC燃料循环的参数研究以反映压水堆燃料管理策略

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For both pressurized water reactor (PWR) and Canada deuterium uranium (CANDU) tandem analysis, the Direct Use of spent PWR fuel In CANDU reactor (DUPIC) fuel cycle in a CANDU6 reactor is studied using the DRAGON/DONJON chain of codes with the ENDF/B-V and ENDF/B-VI libraries. The reference feed material is a 17×17 French standard 900-MW(electric) PWR fuel.

机译：对于压水堆（PWR）和加拿大氘铀（CANDU）串联分析，使用DRAGON / DONJON代码链和ENDF研究了CANDU6反应堆中CANDU反应堆（DUPIC）燃料循环中直接使用乏PWR燃料的情况。 / BV和ENDF / B-VI库。参考进料为17×17法国标准900兆瓦（电）压水堆燃料。

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《Nuclear science and engineering》 |2001年第1期|p.1-25|共25页
作者
Daniel Rozon; Wei Shen;
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收录信息美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
原文格式 PDF
正文语种 eng
中图分类原子能技术;
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1. ECONOMIC ANALYSIS ON DIRECT USE OF SPENT PRESSURIZED WATER REACTOR FUEL IN CANDU REACTORS - IV: DUPIC FUEL CYCLE COST [J] . WON IL KO, HANGBOK CHOI, MYUNG SEUNG YANG Nuclear Technology . 2001,第2期

机译：在坎杜反应堆中直接使用高压加压水燃料的经济分析-IV：双燃料周期成本
2. ECONOMIC ANALYSIS ON DIRECT USE OF SPENT PRESSURIZED WATER REACTOR FUEL IN CANDU REACTORS-FUEL IN CANDU REACTORS-I: DUPIC FUEL FABRICATION COST [J] . HANGBOK CHOI, WON IL KO, MYUNG SEUNG YANG Nuclear Technology . 2001,第2期

机译：直接在坎杜反应堆中使用高压加压水燃料的经济分析-坎杜反应堆中的燃料-I：双燃料制造成本
3. ECONOMIC ANALYSIS ON DIRECT USE OF SPENT PRESSURIZED WATER REACTOR FUEL IN CANDU REACTORS-II: DUPIC FUEL-HANDLING COST [J] . HANGBOK CHOI, WON IL KO, MYUNG SEUNG YANG Nuclear Technology . 2001,第2期

机译：直接在坎杜反应堆中使用加压加压水燃料的经济分析-II：双重燃料处理成本
4. Studies of Advanced Fuel Cycles in Indian Pressurized Heavy Water Reactors andAdvanced Heavy Water Reactor [C] . P.D. Krishnani, Baltej Singh, Umasankari Kannan, PHYSOR 2004 - the physics of fuel cycles and advanced nuclear systems: global developments . 2004

机译：印度加压重水反应堆和先进重水反应堆中先进燃料循环的研究
5. Design and Construction of a Lab Scale Pressurized Entrained Flow Reactor for Studying the Thermochemical Conversion of Solid Fuels at High Temperature. [D] . Tchapda, Aime Hilaire. 2017

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6. Pb(Mg1/3Nb2/3)-PbTiO3-Based Ultrasonic Transducer for Detecting Infiltrated Water in Pressurized Water Reactor Fuel Rods [O] . Geonwoo Kim, Namkyoung Choi, Yong-Il Kim, 2019

机译：基于Pb（Mg1 / 3Nb2 / 3）-PbTiO3的超声波换能器用于检测压水堆燃料棒中的渗透水
7. Comparison between Equilibrium Cycle and Successive Multicycle Optimization Methods for In-Core Fuel Management of Pressurized Water Reactors [O] . Akio YAMAMOTO, Keiji KANDA 1997

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8. Contribution of Fuel Vibrations to Ex-Core Neutron Noise During the First and Second Fuel Cycles of the Sequoyah-1 Pressurized Water Reactor [R] . Sweeney, F. J., March-Leuba, J., Smith, C. M. 1984

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A Parametric Study of the DUPIC Fuel Cycle to Reflect Pressurized Water Reactor Fuel Management Strategy

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