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压水堆核电厂启动过程中,次级中子源为堆外源量程探测器提供本底计数率,避免测量盲区,确保反应堆安全启动。但次级中子源的引入会为核电厂带来较大的经济和环境负担,同时也需承受次级中子源破损等带来的风险。为此,可使用受辐照燃料组件的自发裂变中子源进行替代,即无源启动方式。通过研究堆外源量程探测器计数率的理论计算方法,并基于运行电厂测量数据进行分析验证,为源量程探测器计数率的理论预估提供了较为完善的理论方法流程。本文结果可为无源启动源量程探测器计数率分析提供支持,同时也可用于次级中子源装载量或布置位置的优化分析等。 相似文献
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以人工计算结果与参考模式下的程序计算结果相比较的方法,研究堆芯中子探测器校刻系数影响因素。得出探测器灵敏度是校刻系数主要影响因素的结论。提出了一种用于安装调试阶段选择中子探测器的优化方案。 相似文献
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为研究国产中子气泡探测器在核测井中子个人剂量监测中的适用性,采用国内研制的中子气泡探测器对核测井运源车外表面、车内兼用储源仓周围等关注点的中子辐射水平进行监测,同时采用进口LB6411型中子周围剂量当量仪进行比对监测。实验结果表明,当运源车兼用储源仓内仅装载中子源时,中子气泡探测器与LB6411的测量结果无显著统计学差异,两者测量结果符合较好,中子气泡探测器的测量结果准确可信;当兼用储源仓分别装载中子源、中子-γ源时,两组中子气泡探测器的测量结果也无显著统计学差异,中子气泡探测器适用于中子-γ混合辐射场中子辐射剂量的测量。中子气泡探测器在运源车现场与在241Am-Be源标准中子场中的剂量响应灵敏度因子间的相对偏差为7.4%,验证了其较好的能量响应特性,并显示了在核测井现场条件下用于中子个人剂量监测的适用性。 相似文献
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用于中子诊断的塑料闪烁探测器性能标定 总被引:1,自引:1,他引:0
介绍了用于脉冲中子诊断的塑料闪烁探测器特性,并通过K-400加速器和脉宽10ns的窄脉冲中子管分别刻度了探测器的DT中子探测效率和灵敏度。探测效率的计算值与实测数据在误差范围内是一致的。 相似文献
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为测量DPF脉冲中子产额,设计了电流型银激活探测器。该探测器由中子慢化体、天然银片、塑料闪烁体和光电倍增管组成。定义了该探测器测量DPF快脉冲中子产额时的探测灵敏度。采用高压倍加器稳态中子源对电流型银激活探测器的探测灵敏度进行了标定。稳态中子源的绝对中子产额由伴随粒子法给出。通过计算机自动记录探测器在饱和照射后其输出电流随时间的变化曲线,通过分析变化曲线求解特征参数,进而得到电流型银激活探测器在距离14 MeV脉冲中子源1 m 处时的探测灵敏度为1.843´109 nA-1。在包含因子k为2时,探测灵敏度的扩展不确定度小于17.5 %。 相似文献
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介绍了利用K600中子发生器进行Si-PIN探测器灵敏度标定的实验方法,并在实验中测出了Si-PIN探测器对14MeV中子的直照灵敏度。同时,利用MCNP模拟程序对Si-PIN探测器不同能量的中子直照灵敏度进行了理论计算,实验灵敏度处理结果和理论计算值较为一致。 相似文献
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反应堆启动初始阶段,中子注量非常低,是一般核测量系统的测量盲区。针对测量盲区的问题,设计了一种高灵敏度宽量程的中子注量率探测器。通过计算及实验表明,该探测器具有稳定的性能,能提供一种反应堆物理启动过程中盲区中子注量率测量的方法。 相似文献
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本文将10 B粉与1,2-二氯乙烷溶剂、芳华树脂粘结剂混合研制了中子灵敏层10 B膜,以此制作一新型涂硼正比计数器。为增加探测效率,除管内壁涂硼外,在管内增置了14片双面涂硼环氧薄片,并用241 Am-Be源测试了其性能。活度为3.7×109 Bq的241 Am-Be源实验表明:此新型涂硼正比计数器坪长约150V,坪斜为8.2%/100V(750~900V);工作电压为800V时测得新型涂硼正比计数器的计数率为50s-1,灵敏度为0.71cm2。与管内壁仅涂硼的正比计数器相比,新型涂硼正比计数器中子灵敏面积增加到3.15倍后,探测器坪长从80 V增至150 V,坪斜从12.4%/100 V改进到7.58%/100V,灵敏度提高到2.63倍。同时,以基于蒙特卡罗方法的Geant4平台,模拟计算单能中子及241 Am-Be源中子照射包裹高密度聚乙烯慢化材料的新型涂硼正比计数器的响应和探测效率。241 AmBe源模拟结果和实验结果吻合较好。实验测试及模拟结果表明,涂硼技术与增加灵敏面积相结合的正比计数器的设计较成功。 相似文献
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《Fusion Engineering and Design》2014,89(9-10):2194-2198
Self powered neutron detectors (SPND) have a number of interesting properties (e.g. small dimensions, capability to operate in harsh environments, absence of external bias), so they are attractive neutron monitors for TBM in ITER. However, commercially available SPNDs are optimized for operation in a thermal nuclear reactor where the neutron spectrum is much softer than that expected in a TBM. This fact can limit the use of SPND in a TBM since the effective cross sections for the production of beta emitters are much lower in a fast neutron spectrum.This work represents the first attempt to study SPNDs as neutron flux monitors for TBM. Three state-of-the-art SPND available on the market were bought and tested using fast neutrons at TAPIRO fast neutron source of ENEA Casaccia and with 14 MeV neutrons at the Frascati neutron generator (FNG).The results clearly indicate that in fast neutron spectra, the response of SPNDs is much lower than in thermal neutron flux. Activation calculations were performed using the FISPACT code to find out possible material candidates for SPND suitable for operation in TBM neutron spectra. 相似文献
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利用测热技术测量核反应堆中子通量密度 总被引:2,自引:2,他引:0
一种新型中子探测器被研究,其原理是利用带电离子在矿物中沉积的能量退火时会以热量的方式释放出来,通过测量释放的热量而确定中子通量密度。对新型中子探测器进行刻度,在反应堆内某位置测量的热中子通量密度为5.108×1011 cm-2•s-1,与标定的热中子通量密度(5.000×1011 cm-2•s-1)在2%内符合,说明该探测器可测量中子通量密度。本文方法制作的探测器体积小,可制作成不同形状,便于反应堆不同环境下的中子通量密度测量。选取相应中子能量反应截面较大的元素,该探测器还可测量不同中子能量的通量密度。 相似文献
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Tetsuro Matsumoto Akihiko Masuda Hideki Harano Yoshiaki Shikaze Yoshihiko Tanimura Hajime Seito 《Journal of Nuclear Science and Technology》2017,54(5):529-538
In this study, we developed a 45 MeV neutron fluence rate standard of Japan. Quasi-monoenergetic neutrons with a peak energy of 45 MeV in the neutron standard field were produced by the 7Li(p,n)7Be reaction using a 50-MeV proton beam from an azimuthally varying field (AVF) cyclotron of the Takasaki Ion Accelerators for Advanced Radiation Application (TIARA). The neutron energy spectrum was measured using an organic liquid scintillation detector and a 6Li-glass scintillation detector by the time-of-flight method, and using a Bonner sphere spectrometer by the unfolding method. The absolute neutron fluence was determined using a proton recoil telescope (PRT) composed of the liquid scintillation detector and a Si(Li) detector that was newly developed in the present study. The detection efficiency of the PRT was obtained using the MCNPX code. The peak neutron production cross section for the 7Li(p,n)7Be reaction was also derived from the neutron fluence in order to confirm the neutron fluence of the TIARA high-energy neutron field. The peak neutron production cross section obtained in the present study was in good agreement with those of previous studies. The characteristics of the 45-MeV neutron field in TIARA were successfully evaluated in order to calibrate high-energy neutron detectors and high-energy neutron dosimeters. 相似文献
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为实现反应堆不同空间和能量的相对中子通量密度在线监测,本文研究开发了一套新型的用于狭小空间且位置灵敏的闪烁体中子探测系统。该套系统由5种探头、5路光子计数器、1台计算机及相应的软件组成。5种探头的主要构成物质分别为~6 LiF+ZnS(Ag)、~(232) ThO_2+ZnS(Ag)、~(238) UO_2+ZnS(Ag)、~9Be+ZnS(Ag)以及BGO晶体,故可测量不同能量的相对中子通量密度。其中,掺有~6 LiF的探头用于热中子的测量,BGO探头用于γ测量,其余3种探头用于快中子的测量。利用该系统进行了启明星1#装置内热中子及快中子的相对通量密度分布测量,并将测量结果与利用蒙特卡罗方法得到的理论分布结果进行了比较。考虑到理论设置参数与实际实验参数的差别,可认为测量结果是可信的。 相似文献
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载钆液闪探测器是高能物理及核物理实验中重要的粒子探测工具。通过研制得到了一台大体积的直径为30 cm等高圆柱形载钆液闪探测器,载钆液闪溶液的载钆量为0.5%wt;利用252Cf中子源进行了中子与γ分辨性能实验测试,结果表明,直径30 cm等高圆柱形载钆液闪的中子与γ分辨性能较差;利用飞行时间技术通过符合测量的方法,分别测量了中子与伽马分辨谱中的中子与γ信号的时间分布,两者峰位之间的时间差为2 ns;利用252Cf裂变电离室的裂变碎片信号作为开门信号,通过符合测量的方法,获得了直径30 cm等高圆柱形载钆液闪的中子俘获时间分布实验数据,中子俘获平均时间为11μs。对于较大体积条件下,载钆液闪的中子与γ分辨性能较差的物理现象,通过实验给出了合理解释和分析。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(11):1414-1421
In the foregoing studies, it has been proved that the digital reactivity meter can be used for not only sub-criticality measurement but also continuous sub-criticality monitoring during criticality approach. Based on these studies, we investigated the applicability of a digital reactivity meter for continuous sub-criticality monitoring to intervene before a criticality accident occurs that is similar to the Tokai-mura accident in 1999. In our mock up numerical simulation, there are three calculation steps that are (1) reactivity transient calculation, (2) neutron transient calculation and (3) sub-criticality monitoring calculation. The reactivity transient was calculated using two-group diffusion nuclear constants and the neutron transient was calculated using the one-point reactor kinetics. In sub-criticality monitoring, three algorithms for reactivity evaluation were compared. We have investigated which algorithm is the most suitable to use in an actual system. In practice, we also advise use of some filtering algorithm to reduce the neutron transient fluctuation and a warning reactivity to know estimated sub-criticality as earlier as possible. 相似文献