Passive neutron multiplicity device for 240Pu measurement based on FPGA

IF 3.6 1区 物理与天体物理 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Science and Techniques Pub Date : 2024-09-04 DOI:10.1007/s41365-024-01514-1
Yan Zhang, Hao-Ran Zhang, Ren-Bo Wang, Ming-Yu Li, Rui Chen, Hai-Tao Wang, Xiang-Ting Meng, Shu-Min Zhou, Bin Tang
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Abstract

A passive neutron multiplicity measurement device, FH-NCM/S1, based on field-programmable gate arrays (FPGAs), is developed specifically for measuring the mass of plutonium-240 (240Pu) in mixed oxide fuel. FH-NCM/S1 adopts an integrated approach, combining the shift register analysis mode with the pulse-position timestamp mode using an FPGA. The optimal effective length of the 3He neutron detector was determined to be 30 cm, and the thickness of the graphite reflector was ascertained to be 15 cm through MCNP simulations. After fabricating the device, calibration measurements were performed using a 252Cf neutron source; a detection efficiency of 43.07% and detector die-away time of 55.79 \({\upmu }\)s were observed. Nine samples of plutonium oxide were measured under identical conditions using the FH-NCM/S1 in shift register analysis mode and a plutonium waste multiplicity counter. The obtained double rates underwent corrections for detection efficiency (\(\varepsilon\)) and double gate fraction (\(f_{\rm d}\)), resulting in corrected double rates (\(D_{\rm c}\)), which were used to validate the accuracy of the shift register analysis mode. Furthermore, the device exhibited fluctuations in the measurement results, and within a single 20 s measurement, these fluctuations remained below 10%. After 30 cycles, the relative error in the mass of 240Pu was less than 5%. Finally, correlation calculations confirmed the robust consistency of both measurement modes. This study holds specific significance for the subsequent design and development of neutron multiplicity devices.

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基于 FPGA 的 240Pu 测量无源中子倍率装置
我们开发了一种基于现场可编程门阵列(FPGA)的被动中子倍率测量装置 FH-NCM/S1,专门用于测量混合氧化物燃料中钚 240(240Pu)的质量。FH-NCM/S1 采用集成方法,利用 FPGA 将移位寄存器分析模式与脉冲位置时间戳模式相结合。通过 MCNP 模拟,确定 3He 中子探测器的最佳有效长度为 30 厘米,石墨反射器的厚度为 15 厘米。装置制作完成后,使用 252Cf 中子源进行了校准测量;观察到探测效率为 43.07%,探测器消亡时间为 55.79 \({\upmu }\)s 。在相同的条件下,使用移位寄存器分析模式下的 FH-NCM/S1 和钚废物倍率计数器测量了九个氧化钚样品。所获得的双倍率经过了探测效率(\(\varepsilon\))和双闸门分数(\(f_{\rm d}\))的修正,从而得到了修正后的双倍率(\(D_{\rm c}\)),用来验证移位寄存器分析模式的准确性。此外,该装置在测量结果中表现出波动,在一次 20 秒的测量中,这些波动保持在 10% 以下。经过 30 个周期后,240Pu 质量的相对误差小于 5%。最后,相关计算证实了两种测量模式的稳健一致性。这项研究对中子倍率装置的后续设计和开发具有重要意义。
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来源期刊
Nuclear Science and Techniques
Nuclear Science and Techniques 物理-核科学技术
CiteScore
5.10
自引率
39.30%
发文量
141
审稿时长
5 months
期刊介绍: Nuclear Science and Techniques (NST) reports scientific findings, technical advances and important results in the fields of nuclear science and techniques. The aim of this periodical is to stimulate cross-fertilization of knowledge among scientists and engineers working in the fields of nuclear research. Scope covers the following subjects: • Synchrotron radiation applications, beamline technology; • Accelerator, ray technology and applications; • Nuclear chemistry, radiochemistry, radiopharmaceuticals, nuclear medicine; • Nuclear electronics and instrumentation; • Nuclear physics and interdisciplinary research; • Nuclear energy science and engineering.
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