Axial burnup profile database for pressurized water reactors

机译：压水堆轴向燃耗曲线数据库

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The axial burnup profile in a discharged fuel assembly typically has high burnup in the center and lower burnup at the ends of the assembly.The assembly average burnup is maintained as part of reactor records.However,the axial burnup profile is calculated from the depletion analysis of the cycle operation.Thus,these calculated axial profiles are used in analyses involving burnup credit.An axial burnup profile database was compiled for a large number of PWR fuel assemblies over a range of burnup,initial enrichment and operating conditions.The objective was to provide a detailed characterization of spent PWR fuel,specifically with respect to the axial burnup distribution.

机译：排出的燃料组件中的轴向燃尽曲线通常在中心具有较高的燃尽率，而在组件的末端则具有较低的燃尽率。组件的平均燃尽率是反应堆记录的一部分，但轴向燃尽率概算是通过消耗分析来计算的因此，这些计算的轴向轮廓用于涉及燃耗信用的分析。针对燃耗，初始浓缩和运行条件范围内的大量压水堆燃料组件，编制了轴向燃耗轮廓数据库。提供乏压水堆燃料的详细特性，特别是关于轴向燃耗分布的特性。

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《》|1998年|p.567-568|共2页
会议地点 Las Vegas NV(US)
作者
R.J.Cacciapouti; S.Van Volkinburg;
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正文语种 eng
中图分类环境污染及其防治;
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机译：铀，P，钕和铯同位素相关性与Burnup的高Burnup加压水反应器燃料分析
2. Analysis of high burnup pressurized water reactor fuel using uranium, plutonium, neodymium, and cesium isotope correlations with burnup [J] . Jung Suk Kim, Young Shin Jeon, Soon Dal Park, Nuclear engineering and technology . 2015,第7期

机译：使用铀，p，钕和铯同位素与燃耗的高燃耗压水堆燃料分析
3. Thermal-hydraulic analysis of UO_2 and MOX fuel considering different cladding materials at various burnup levels in pressurized water reactor [J] . Farhana Islam Farha, Hossain Sahadath, Sadek Hossain Nishat Heat transfer . 2021,第7期

机译：在加压水反应器中考虑不同包覆材料的UO_2和MOX燃料的热液压分析
4. Axial burnup profile database for pressurized water reactors [C] . R.J.Cacciapouti, S.Van Volkinburg International conference on high-level radioactive waste management . 1998

机译：加压水反应堆的轴向燃烧型材数据库
5. In-situ Surface Enhanced Raman Spectroscopy Investigation of the Surface Films on Alloy 600 and Alloy 690 in Pressurized Water Reactor-Primary Water. [D] . Wang, Feng. 2012

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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

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7. CIRFT testing of high-burnup used nuclear fuel rods from pressurized water reactor and boiling water reactor environments [O] . Jy-An John Wang, Hong Wang, Hao Jiang, 2015

机译：高燃烧的核燃料杆带有加压水反应器和沸水反应器环境的圆形测试
8. Standard- and extended-burnup PWR (pressurized-water reactor) and BWR (boiling-water reactor) reactor models for the ORIGEN2 computer code. [R] . Ludwig, S. B., Renier, J. P. 1989

机译：用于ORIGEN2计算机代码的标准和扩展燃耗pWR（压水反应堆）和BWR（沸水反应堆）反应堆模型。

Axial burnup profile database for pressurized water reactors

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