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用于保障监督应用的基于诱发裂变的钚计量仪器原型的开发。

Development of prototype induced-fission-based Pu accountancy instrument for safeguards applications.

作者信息

Seo Hee, Lee Seung Kyu, An Su Jung, Park Se-Hwan, Ku Jeong-Hoe, Menlove Howard O, Rael Carlos D, LaFleur Adrienne M, Browne Michael C

机构信息

Korea Atomic Energy Research Institute, Daejeon 34057, Republic of Korea.

Korea Atomic Energy Research Institute, Daejeon 34057, Republic of Korea.

出版信息

Appl Radiat Isot. 2016 Sep;115:67-73. doi: 10.1016/j.apradiso.2016.06.011. Epub 2016 Jun 14.

Abstract

Prototype safeguards instrument for nuclear material accountancy (NMA) of uranium/transuranic (U/TRU) products that could be produced in a future advanced PWR fuel processing facility has been developed and characterized. This is a new, hybrid neutron measurement system based on fast neutron energy multiplication (FNEM) and passive neutron albedo reactivity (PNAR) methods. The FNEM method is sensitive to the induced fission rate by fast neutrons, while the PNAR method is sensitive to the induced fission rate by thermal neutrons in the sample to be measured. The induced fission rate is proportional to the total amount of fissile material, especially plutonium (Pu), in the U/TRU product; hence, the Pu amount can be calibrated as a function of the induced fission rate, which can be measured using either the FNEM or PNAR method. In the present study, the prototype system was built using six (3)He tubes, and its performance was evaluated for various detector parameters including high-voltage (HV) plateau, efficiency profiles, dead time, and stability. The system's capability to measure the difference in the average neutron energy for the FNEM signature also was evaluated, using AmLi, PuBe, (252)Cf, as well as four Pu-oxide sources each with a different impurity (Al, F, Mg, and B) and producing (α,n) neutrons with different average energies. Future work will measure the hybrid signature (i.e., FNEM×PNAR) for a Pu source with an external interrogating neutron source after enlarging the cavity size of the prototype system to accommodate a large-size Pu source (~600g Pu).

摘要

已开发并表征了一种用于未来先进压水堆燃料处理设施中可能生产的铀/超铀(U/TRU)产品核材料衡算(NMA)的原型保障仪器。这是一种基于快中子能量倍增(FNEM)和被动中子反照率反应性(PNAR)方法的新型混合中子测量系统。FNEM方法对快中子引起的裂变率敏感,而PNAR方法对被测样品中热中子引起的裂变率敏感。引起的裂变率与U/TRU产品中裂变材料的总量,特别是钚(Pu)成正比;因此,可以将Pu含量校准为引起的裂变率的函数,该裂变率可以使用FNEM或PNAR方法进行测量。在本研究中,原型系统使用六个(3)He管构建,并针对包括高压(HV)坪、效率曲线、死时间和稳定性在内的各种探测器参数评估了其性能。还使用AmLi、PuBe、(252)Cf以及四个具有不同杂质(Al、F、Mg和B)且产生具有不同平均能量的(α,n)中子的Pu氧化物源,评估了该系统测量FNEM特征平均中子能量差异的能力。未来的工作将在扩大原型系统的腔体尺寸以容纳大尺寸Pu源(约600g Pu)后,测量带有外部询问中子源的Pu源的混合特征(即FNEM×PNAR)。

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