开池式反应堆芯内60Co生产装置的研究

IF 0.4 4区工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY

Kerntechnik Pub Date : 2022-12-23 DOI:10.1515/kern-2022-0094

Amr Abdelhady

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引用次数: 0

摘要

摘要核研究堆中高比60Co活性的生产需要长时间的辐照才能达到适当的消费需求。钴装置是第二研究堆(ETRR-2)堆芯内的固定实验装置，设计用于生产60Co，活度为50000 Ci。钴装置是由16个铝罐组成的，这些铝罐中填充了钴箔。利用依赖于蒙特卡罗方法的程序来估计60Co活性是本研究的目的。MCNP6, KENO-VI和MAVRIC代码将用于评估钴装置在反应堆堆芯内达到适当60Co活度所花费的时间，考虑到连续照射和离散照射。计算表明，近一年的连续中子辐照足以达到所要求的活度。在离散辐照的情况下，达到所需活性所需的时间将超过一年，这取决于反应堆的运行周期。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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Investigating the in-core 60Co production assembly for open pool type reactor

Abstract Production of high specific 60Co activity in nuclear research reactor needs long time of irradiation to reach the proper consumer demands. Cobalt device is a fixed experiment inside the core of the second research reactor (ETRR-2) that designed for production of 60Co with activity of 50,000 Ci. Cobalt device is assembly of 16 pins of aluminum cans that filling with the cobalt foils. Utilizing the programs that depend on the Monte Carlo method to estimate 60Co activity is the objective of this study. MCNP6, KENO-VI, and MAVRIC codes would be used to evaluate the time that the cobalt device has been spent inside the reactor core for reaching the proper 60Co activity considering the continuous irradiation as well as the discrete irradiation. The calculations show that nearly one year of continuous neutron irradiation is sufficient for reaching the required activity. In case of discrete irradiation, the time required for reaching the required activity would be more than a year depending on the reactor operation period.

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来源期刊

Kerntechnik 工程技术-核科学技术

CiteScore

0.90

自引率

20.00%

发文量

审稿时长

6-12 weeks

期刊介绍： Kerntechnik is an independent journal for nuclear engineering (including design, operation, safety and economics of nuclear power stations, research reactors and simulators), energy systems, radiation (ionizing radiation in industry, medicine and research) and radiological protection (biological effects of ionizing radiation, the system of protection for occupational, medical and public exposures, the assessment of doses, operational protection and safety programs, management of radioactive wastes, decommissioning and regulatory requirements).