~(58)Ni全套中子核数据的评价

评价了~(58)Ni在10~(-5)eV到20MeV能区的全套中子数据。数据包括全截面、弹性、去弹、总非弹,九条分立能级和连续态的非弹及(n,2n),(n,3n),(n,n'α) (n,αn'),(n,n'p) (n,pn'),(n,p),(n,d),(n,t),(n,α)和(n,γ)反应截面,还包括次级中子角分布、双微分截面(DDCS),γ产生数据和共振参数。评价依据直到1995年测量的     

~(58)Ni全套中子核数据的评价(英文)

评价了~(58)Ni在10~(-5)eV到20MeV能区的全套中子数据。数据包括全截面、弹性、去弹、总非弹,九条分立能级和连续态的非弹及(n,2n),(n,3n),(n,n′α) (n,αn′),(n,n′p) (n,pn′),(n,p),(n,d),(n,t),(n,α)和(n,γ)反应截面,还包括次级中子角分布、双微分截面(DDCS),γ产生数据和共振参数。评价依据直到1995年测量的实验数据和用UNF程序的理论计算。评价数据以ENDF/B-6格式入中国评价核数据库第三版(CENDL-3)。     

29—1100keV能区75As中子俘获截面测量

用活化法相对于Au的中子俘获截面，测量了29－1100keV能区^75As(n, γ）^76As的反应截面，测量精度为6．7－7．8％，并将测量结果与现有的实验数据作了比较。     

^204Pb（n,2n）^203Pb和^206Pb（n,α）^203Hg反应截面的测量

用活化法进行了13.50—14.81MeV中子能区~(204)Pb(n,2n)~(203)Pb和~(206)Pb(n,α)~(203)Hg反应截面的测量。用~(27)Al(n,α)~(24)Na反应作为中子注量标准。中子能量用锆、铌截面比测定。所得结果和有关文献的结果作了比较。     

14.8 MeV中子诱发78Kr(n,2n)77Kr反应截面的测量

快中子诱发(n,2n)反应截面的测量在核反应机制研究和核技术应用等方面有着广泛的应用价值。本文在中国原子能科学研究院的高压倍加器上,基于活化法实验测量了78Kr(n,2n)77Kr在148 MeV能点的反应截面。样品靶为高纯78Kr气体样品,用十万分之一天平称重得到78Kr的质量,将两片高纯93Nb薄片分别固定在样品靶两侧以监测中子注量率。利用T(d,n)4He反应产生148 MeV中子,轰击距中子源约10 cm的样品靶大于4 h后,用准确刻度过效率的HPGe探测器测量活化产物 77Kr和92Nbm的活度。利用蒙特卡罗程序计算中子注量率修正、样品自吸收修正、样品几何修正等因子,得到了78Kr(n,2n)77Kr的反应截面,并将结果与文献值和评价数据库进行了比较。研究结果有助于提高78Kr(n, 2n)77Kr反应截面测量和评价的水平。     

EMPIRE程序对n＋^58,60,61,62,64 Ni反应（0-20MeV）的理论计算

Ni是重要的结构材料核，本工作运用EMPIRE程序对n＋^58,60,61,62,64 Ni反应的全套数据进行理论计算，并给出了反应截面、角分布及次级中子双微分截面和能谱等全套中子数据的理论模型计算结果与实验数据及其他评价数据的比对。通过对不同反应阶段EMPIRE提供的不同模型描述对n＋^58,60,61,62,64 Ni反应进行了计算、并将结果和实验数据以及其它评价数据进行了比较分析，     

快中子64Zn(n,α)61Ni反应微分截面实验测量

由于64Zn(n,α)61Ni反应的剩余核是稳定的,不能用通常的活化法来测量,致使该反应截面实验数据缺乏.利用双屏栅电离室作为带电粒子探测器,在En=2.54,4.00,5.03,5.50与5.95MeV 5个能点,对64Zn(n,α)61Ni反应的微分截面进行了实验测量,并通过微分截面对角度的积分得到了反应截面.实验在北京大学4.5MV静电加速器上进行.2.54MeV的单能中子采用固体氚-钛靶T(p,n)3He反应产生,其余四种能量的准单能中子通过氘气体靶D(d,n)3He反应获得.绝对中子通量采用238U(n,f)反应来确定,实验过程中用BF3长中子计数器进行相对中子通量监测.测量结果与已有的实验与评价数据进行了比较.     

^179Hf（n,2n）^178Hf^m2和^209Bi（n,2n）^208Bi反应截面的测量

用活化法测量相对于~(93)Nb(n,2n)~(92)Nb~m反应的~(179)Hf(n,2n)~(178)Hf~(m2)的反应截面和相对于~(27)Al(n,2n)~(24)Na反应的~(209)Bi(n,2n)~(208)Bi的反应截面。在中子能量为14.4 MeV处~(179)Hf(n,2n)~(178)Hf~(m2)反应的测量截面为(6.04±0.32)×10~(-31)m~2。在中子能量为14.6 MeV处~(209)Bi(n,2n)~(208)Bi反应的测量截面为(2279±173)×10~(31)m~2。在这些测量中,中子能量是用~(90)Zr(n,2n)~(89)Zr~(m+8)反应和~(93)Nb(n,2n)~(92)Nb~m反应的截面比法测定的。     

35MeV以下56Fe(n,p)56Mn反应截面及协方差评价

56Fe(n,p)56Mn通常作为标准反应来监测中子场通量,该反应截面数据的准确性直接影响到活化法测量结果的精确度,进而影响到实验待测物理量的精度。本文开展了56Fe(n,p)56Mn反应截面实验测量数据评价工作与协方差计算工作,首先系统分析EXFOR中现有的56Fe(n,p)56Mn反应截面实验测量数据,对实验数据进行了归纳总结分析,并从中子源、测量方法、探测器类型等方面对56Fe(n,p)56Mn直接测量实验数据进行评价。然后,拟合给出适用入射中子能量区间为295～35 MeV的激发曲线。随后,针对评价中重点推荐的实验数据开展了关联协方差矩阵的计算工作。最后,使用核反应计算程序TALYS对56Fe(n,p)56Mn激发曲线进行了调参计算并和评价数据进行了比较分析。该工作拓展了现有的中子活化反应截面实验数据的评价方法,结果提高了35 MeV以下中子诱发56Fe(n,p)56Mn反应的评价数据精度。     

6Li(n,t)4He反应微分截面的实验测量

用屏栅电离室对1．85和2．67MeV中子^6Li(n,t)^4He反应的微分截面及截面进行了测量。使用氚固体靶通过T(p,n)^3He反应产生中子,利用BF3长中子管进行相对中子通量监测,绝对中子通量则用^238U(n,f)反应来刻度。测量结果与已有数据进行了比较。     

Activation cross sections for (n, p) reactions on nickel isotopes induced by neutrons around 14 MeV

The cross sections of ⁵⁸Ni(n, p)^58(m+g)Co,⁶⁰Ni(n, p)^60mCo,⁶¹Ni(n, p)⁶¹Co and ⁶²Ni(n, p)^62mCo reactions induced by neutrons around 14 MeV were measured using activation technique and a coaxial HPGe γ-ray detector. The natural nickel foils of 99.9% purity were used as target materials. Fast neutrons were produced by the T(d, n)⁴He reaction. The neutron flux was determined using the monitor reaction ²⁷Al(n, α)²⁴Na and the neutron energies were measured with the method of cross-section ratios for ⁹⁰Zr(n, 2n)⁸⁹Zr to ⁹³Nb(n, 2n)^92mNb reactions. The results of this work are compared with the collected partial recent data published previously and the estimations obtained from the published empirical formula based on the statistical model with dependence on the Q-value and odd-even effect taken into consideration.     

Development of the high-energy neutron fluence rate standard field in Japan with a peak energy of 45 MeV using the 7Li(p,n)7Be reaction at TIARA

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.     

Measurement of fast-neutron capture cross sections for 75As

1 INTRODUCTIONThe cross sections of the "As(n,7)"As reaction are boortant in evaluating theradiation damage of the material. EXPerimeats[1-6] and evaluations have been performedto deterAnne the "As(n, 7)"As reaction cross section, but there are large discrepanciesamong them especially in the MeV neutron energy region. Therefore, new eXPerAnent isneeded.2 EXPERIMENT DETAILSThe measuremenis were perfOrmed at the 4.5 MV Van de Grand accelerator of theInstitute Of Heavy Ion Phy…     

Nuclear Data Sheets for A ;eq 58

The 1990 evaluation of A;eq58 (90Pe09) by L. K. Peker has been revised using experimental reaction and decay data received as of February 10, 1997. Neutron reaction data: see the Bibliography CINDA-A, CINDA-B and supplements.     

贫化铀球装置内的~(238)U(n,2n)反应率实验研究

采用两套不同尺寸的贫化铀球装置开展了装置内部的238 U(n,2n)反应率实验研究,利用PD-300加速器D-T中子源辐照实验装置,源强变化采用伴随粒子法监测,238 U圆片放置在实验装置的45°孔道内,分布在距中子源不同距离处,辐照结束后,采用HPGe探测器测量238 U圆片活化γ射线。实验结果与蒙特卡罗程序模拟计算结果进行了比较和分析。结果表明,238 U(n,2n)反应率实验结果与模拟计算值较吻合,238 U(n,2n)反应率随球体半径r的增加,近似服从e-ar/r2分布规律。     

二次中子源在中国实验快堆上应用的初步可行性分析

为满足中国实验快堆(CEFR)物理启动的经济性需要,研究二次中子源替代堆内的~(252)Cf一次中子源的可行性。参照CEFR的相关参数及二次中子源产生中子的原理,设计了二次中子源。用MCNP程序模拟计算了二次中子源组件中~(123)Sb的(n,γ)核反应率和9Be的(γ,n)单核反应率,得出二次中子源组件在不同工况辐照下的源强,分析其在CEFR中应用的可行性。计算结果表明,在大多数工况下,所设计的二次中子源组件能满足CEFR的启动要求。本文所设计的二次中子源及计算结果可为CEFR二次中子源的应用提供参考。     

高气压屏栅电离室的调试和58Ni(n,p)反应双微分截面的试测

介绍了高气压屏栅电离室的结构和调试,并对＾５８Ｎｉ（ｎ,ｐ）试测结果进行了分析,结果证明此电离和测量方法对（ｎ,ｐ）反应的测量是适用的。目前正用此电离室进行测量（ｎ,ｐ）反应堆面的实验。     

Theoretical spectrum-threshold detector data correlation in EBR-II

An experimental and computer program to further examine the neutron environment in the Experimental Breeder Reactor-II (EBR-II) has been completed. Monte Carlo and S₄ Transport methods were used to determine the neutron spectrum at various positions in the EBR-II core and blanket regions. Response functions for the threshold detectors ⁵⁸Ni (n, p) ⁵⁸Co and ⁵⁴Fe (n, p) ⁵⁴Mn were determined for each position and the corresponding predicted induced activities are compared with experimental results. Based on combinations of calculated neutron spectra, experimental detector responses, and cross section end points an empirical differential cross section was determined for the ⁴⁶Ti (n, p) ⁴⁶Sc threshold reaction. Spectrum averaged cross sections for the three threshold reactions which have been determined at various positions in this facility suggest that significant errors in fast neutron fluences will result if the usual fission spectrum averaged cross sections are used.     

基于实验与模拟相结合的气体样品(n,α)反应截面测量方法研究

建立了一套利用屏栅电离室测量快中子诱发气体样品(n,α)反应截面的方法。针对气体样品测量中存在的样品核数确定、中子注量测量、待测事件挑选等问题,本方法首先利用模拟计算结果选择合适的气体样品有效区域,使得事件区尽量无本底覆盖且易于统计;再利用中子准直器和阴极、阳极信号时间信息,分离并统计样品有效区域产生的事件数;最后利用实验测量的238U(n,f)裂变计数和SuperMC模拟结果,得到有效区域内的中子注量。利用该方法在中子能量为471、487、500、512、529和545 MeV的能点系统地测量了14N(n,α0)反应的相对截面,结果与ENDF/B Ⅷ0符合良好。