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DOSE RATE ESTIMATES EXTERIOR TO THE CASTOR MTR-2 CASK USED FOR STORAGE OF THE WWR-S ROMANIAN REACTOR SPENT FUEL

机译：用于存储WWR-S罗马尼亚反应器燃料的CASTOR MTR-2桶的剂量率估计要比外部高

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The paper presents the investigation of the shielding safety problem of the German container CASTOR MTR 2 loaded with the spent fuel of the Romanian WWR-S reactor. The SCALE-4.3 code system, namely the SAS4 module with MORSE, as the shielding Monte Carlo code, based on the (27n-18g)-coupled group energy cross-sections generated from ENDF/B-V file was used for solving the problem. Gamma and neutron dose rates estimated on the surface of the container, and respectively: surface +lm, +2m, +3m in both radial and axial calculation directions for normal, loading and audit conditions are presented and discussed.

机译：本文介绍了对装有罗马尼亚WWR-S反应堆乏燃料的德国CASTOR MTR 2集装箱的屏蔽安全问题的研究。基于从ENDF / B-V文件生成的（27n-18g）耦合组能量截面的SCALE-4.3代码系统，即带有MORSE的SAS4模块，作为屏蔽蒙特卡罗代码，用于解决该问题。介绍并讨论了在容器表面上估算的伽玛和中子剂量率，分别是：在径向和轴向计算方向上的法线，载荷和审核条件下，表面+ lm，+ 2m，+ 3m。

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来源
《Safety of radioactive waste management》|2000年|p.1-5|共5页
会议地点 Cordoba(AR)
作者
D. ENE;
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作者单位

National Institute of Research and Development for Physics and Nuclear Engineering-"Horia Hulubei" Bucharest, Bucharest, Romania;

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会议组织
原文格式 PDF
正文语种 eng
中图分类放射性废物管理及综合利用;
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1. Radiation dose rate distributions of spent fuel dry casks estimated with MAVRIC based on detailed geometry and continuous-energy models [J] . Gao Yuan, Hughes Christopher R., Greulich Christopher R., Annals of nuclear energy . 2018,第JULa期

机译：基于详细几何和连续能量模型的MAVRIC估算的乏燃料干桶的辐射剂量率分布
2. Neutron dose rate analysis of the new CONSTOR? storage cask for the RBMK-1500 spent nuclear fuel [J] . Ernestas Narkūnas, Artūras ?mai?ys, Povilas Po?kas, Nuclear engineering and technology . 2021,第6期

机译：新祠的中子剂量率分析？用于RBMK-1500的储存桶废核燃料
3. Evaluation of Spent Fuel Cask Dose Rate Distribution During Long Term Storage [J] . Yuan Gao, Christopher R. Greulich, James Tulenko, Transactions of the American nuclear society . 2018,第Nova期

机译：长期储存期间乏燃料桶剂量率分布的评估
4. DOSE RATE ESTIMATES EXTERIOR TO THE CASTOR MTR-2 CASK USED FOR STORAGE OF THE WWR-S ROMANIAN REACTOR SPENT FUEL [C] . D. ENE International conference on safety of radioactive waste management . 2000

机译：剂量率估计用于存储WWR-S罗马尼亚反应堆废燃料的蓖麻MTR-2桶外部
5. Models and Characterizations of Neutron Scintillation Detectors for Feasibility of Spent Fuel Cask Monitoring [D] . Wang, Haitang 2017

机译：乏燃料桶监测可行性的中子闪烁探测器模型与特性
6. Pressurized water reactor spent nuclear fuel data library produced with the Serpent2 code [O] . Zsolt Elter, Li Pöder Balkeståhl, Erik Branger, 2020

机译：加压水反应器用Serpent2代码生产的核燃料数据库
7. Time and dose assessment of barge shipment and at-reactor handling of a CASTOR V/21 spent fuel storage cask [O] . C.J. Hostick, J.C. Lavender, B.H. Wakeman 1992

机译：驳船装运的时间和剂量评估和蓖麻型燃料储存桶的铸件V / 21的反应堆处理
8. Time and dose assessment of barge shipment and at-reactor handling of a CASTOR V/21 spent fuel storage cask. [R] . Hostick, C. J., Lavender, J. C., Wakeman, B. H. 1992

机译：驳船运输和反应堆处理CasTOR V / 21乏燃料储存罐的时间和剂量评估。

DOSE RATE ESTIMATES EXTERIOR TO THE CASTOR MTR-2 CASK USED FOR STORAGE OF THE WWR-S ROMANIAN REACTOR SPENT FUEL

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