Calculation of Prompt Fission Neutron from ^(233)U(n, f) Reaction byMulti-Modal Los Alamos Model

An attempt is made to improve the evaluation of the prompt fission neutron emis- sion from 233U（n, f） reaction for incident neutron energies below 6 MeV. The multi-modal fission approach is applied to the improved version of Los Alamos model and the point by point model. The prompt fission neutron spectra and the prompt fission neutron as a function of fragment mass （usually named ＂sawtooth＂ data） v（A） are calculated independently for the three most dominant fission modes （standard I, standard II and superlong）, and the total spectra and v（A） are syn- thesized. The multi-modal parameters are determined on the basis of experimental data of fission fragment mass distributions. The present calculation results can describe the experimental data very well, and the proposed treatment is thus a useful tool for prompt fission neutron emission prediction.

Calculation of prompt fission neutron spectra for ^(235)U(n,f )

The prompt fission neutron spectra for the neutron-induced fission of 235U at En 5 MeV are calculated using nuclear evaporation theory with a semi-empirical model, in which the nonconstant and con- stant temperatures related to the Fermi gas model are taken into account. The calculated prompt fission neutron spectra reproduce the experimental data well. For the n（thermal）＋235 U reaction, the average nuclear temperature of the fission fragment, and the probability distribution of the nuclear temperature, are discussed and compared with the Los Alamos model. The energy carried away by γ rays emitted from each fragment is also obtained and the results are in good agreement with the existing experimental data.

Calculation of prompt fission neutron spectrum for ^(233)U(n,f) reaction by the semi-empirical method

The prompt fission neutron spectra for the neutron-induced fission of 233U for low energy neutrons （below 6 MeV） are calculated using nuclear evaporation theory with a semi-empirical method, in which the partition of the total excitation energy between the fission fragments for the nth＋233U fission reactions is determined by the available experimental and evaluation data. The calculated prompt fission neutron spectra agree well with the experimental data. The proportions of high-energy neutrons of prompt fission neutron spectrum versus incident neutron energies are investigated with the theoretical spectra, and the results are consistent with the systematics. The semi-empirical method could be a useful tool for the prompt evaluation of fission neutron spectra.

Prompt fission neutron spectra of n+^(235)U above the(n,nf) fission threshold

Calculations of prompt fission neutron spectra （PFNS） from the ^235U（n, f） reaction were performed with a semi-empirical method for En = 7.0 and 14.7 MeV neutron energies. The total PFNS were obtained as a superposition of （n,xnf） pre-fission neutron spectra and post-fission spectra of neutrons which were evaporated from fission fragments, and these two kinds of spectra were taken as an expression of the evaporation spectrum. The contributions of （n,xnf） fission neutron spectra on the calculated PFNS were discussed. The results show that emission of one or two neutrons in the （n,nf） or （n,2nf） reactions influences the PFNS shape, and the neutron spectra of the （n,xnf） fission-channel are soft compared with the neutron spectra of the （n,f） fission channel. In addition, analysis of the multiple-chance fission component showed that second-chance fission dominates the PFNS with an incident neutron energy of 14.7 MeV whereas first-chance fission dominates the 7 MeV case.

MEASUREMENT OF PROMPT NEUTRON SPECTRA OF ^（238）U FISSION INDUCED BY 10．17 AND 12．12 MeV NEUTRONS

Erperimental method to measure the prompt neutron spectra of 238U fissioninduced by fast neutrons has been developed at HI-13 Tandem Van de Grab Accelerator Laboratory of CIAE. These techniques employ a multi-segment fission chamberand tab liquid scintillator neutron detectors. TOF (time of flight) techniques are usedfor prilnny neutrons to select the fission evellts induced by monoenergetic neutronfrom 'H(d, n) reactions instead of breakup neutrons from 'H(d, up) reactions. Thefission neutron TOF spectra are measured in coincidence with the fission fragmellts todistinguish fission neutrons from other secondals neutrons. The method perests measurements to a forly good accuracy under large neutron and gamma ray baCkgroulld.The tecboques are described and experimelltal spectra are presented.

Measurement of the prompt neutron spectrum from thermalneutron-induced fission in U-235 using the recoil proton method

A measurement of the ^235U prompt fission neutron spectrum (PFNS) by the recoil proton method was performed at the Institute of Nuclear Physics and Chemistry, China. Details of the method, which include the calculation and validation of the response matrix, are presented. The PFNS for ^235U in the energy range 1–12 MeV, induced by thermal neutrons, was obtained. The measured spectrum in the low-energy region was in good agreement with previous work and the ENDF/B-VII library, except for minor differences. In the high-energy region, however, the relative height of the measured spectrum was greater, and an analysis of the experiment indicated uncertainties of 13% at 10 MeV and 24% at 12 MeV. Experimental results showed that the recoil proton method could be used to measure prompt fission neutron spectra. Some directions for future work are included.

Positron annihilation study of defects in GaAs irradiated by fission neutron

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Multi-modal calculations of prompt fission neutrons from ^(238)U(n,f) at low induced energy

Properties of prompt fission neutrons from 238U（n, f） are calculated for incident neutron egies below 6 MeV using the multi-modal model, including the prompt fission neutron spectrum, thnere average prompt fission neutron multiplicity, and the prompt fission neutron multiplicity as a function of the fission fragment mass v（A） （usually named ＂sawtooth＂ data） The three most dominant fission modes are taken into account. The model parameters are determined on the basis of experimental fission fragment data. The predicted results are in good agreement with the experimental data.

A study of beryllium moderator thickness for a fission chamber with fast neutron measurements

The detection efficiency of the fission chamber(FC) is very important for studying the neutron flux measurement(NFM) system in ITER. In this article, we mainly focus our attention on the influence of the moderator. With the Monte Carlo particle transport simulation tool named Geant4, we make a simulation of FC detection efficiency with different levels of thickness of a beryllium moderator.Two manufactured FCs for ITER-NFM systems are then used to test the parameters and performance. The test results agree well with our simulation.

Experimental Study of the Prompt Neutron Spectra of ^(238)U Fission Induced by Fast Neutrons

The prompt neutron spectra of 238U fission induced by 10.17 and 12.12 MeVneutrons have been measured using a multi-segment fission chamber and two ST-451liquid scintillator neutron detectors in conjunction with a double-TOF technique.Use ofcoincidence between the fission fragments and neutrons enables the fission neutrons tobe distinguished from other secondary ones.The measured spectra can be roughly des-cribed by Maxwellian distributions.The Maxwellian temperatures obtained by fittingare 1.40±0.04 MeV and 1.47±0.04 MeV for 10.17 MeV and 12.12 MeV incidentneutron energies,respectively.They are compared with theoretical calculations by codeFINESSE and the evaluation by ENDF/B-Ⅵ.

MOX燃料与包壳化学相互作用研究进展

简要介绍了MOX燃料芯块微观组织特点和主要裂变产物行为及其对化学相互作用层的影响,归纳总结了国内外对化学相互作用层微观结构的研究进展,分析了现有研究的不足和仍待解决的问题,以期对我国未来MOX燃料的研究和应用提供部分参考。

^(238)PuO_(2)中子周围剂量当量率计算及蒙特卡罗模拟

为了在辐射防护时更加仔细地评估238 Pu产生的中子对工作人员的危害,首先,使用多球中子谱仪对3.4 g的^(238)PuO_(2)粉末样品的中子源强度进行了测量,得到平均中子能量为0.57 MeV。其次,根据平均中子能量,分别按照点源方法和体源方法计算了距该样品不同距离处的中子周围剂量当量率。经过计算发现在距离放射源较近时,体源的计算结果要远小于中子点源的计算结果,在距离放射源比较远时,中子点源和体源的计算结果相同。其次,使用经过计量检定的中子剂量当量率仪对距样品不同距离处的中子周围剂量当量率进行了测量,并与中子体源方法的计算结果进行了对比。最后,使用蒙特卡罗软件Fluka分别模拟了平均中子能量为0.57 MeV以及服从麦克斯韦分布的裂变中子的能量的中子周围剂量当量率结果。研究结果表明:使用中子体源方法的计算结果均在中子剂量当量率仪测量结果的范围内;使用Fluka模拟的中子剂量率结果与中子体源方法计算的结果也非常接近,且均在中子剂量当量率仪测量结果范围内。因此,在^(238)PuO_(2)的辐射防护时,可以使用理论计算的方法替代蒙特卡罗模拟。对于其他自发裂变的核素,按照上述方法,也可以计算其中子剂量率。

反应堆中子通量测量用裂变电离室探测装置研制

为建立一套用于反应堆中子通量测量的监测装置,以实现核电站堆外核测量系统测量要求,研制了一种长灵敏区、宽量程、高灵敏度和强γ抑制能力的裂变电离室探测装置。同时对该裂变电离室探测装置的热中子灵敏度、高压坪特性、甄别特性和γ感应度等典型核性能指标进行了试验验证。试验结果表明,该裂变电离室综合性能能够满足AP1000系列核电站堆外核测量系统中间量程测量通道的应用需求。

堆外核测量系统裂变电离室线性响应研究

为满足先进反应堆堆外核测量系统中间量程测量通道灵敏度高、探测器灵敏区长、反应堆线性响应好的需求,采用多支灵敏区长度具有一定比例关系、同时机械结构完全相同的裂变电离室,进行热中子灵敏度标定和反应堆线性响应研究,以为核电厂实际所需长灵敏区裂变电离室提供一种在现有试验堆条件下进行其核性能试验的方法。通过测量不同灵敏区长度的裂变电离室热中子灵敏度和反应堆高中字注量率下的线性响应,对其热中子灵敏度随灵敏区长度的线性变化和反应堆线性响应进行试验验证。测量结果表明,裂变电离室热中子灵敏度随灵敏区长度呈线性关系,且在反应堆热中子注量率1.23×10^(2)~3.10×10^(10)nv(1nv=1n·cm^(-2)·s^(-1))范围内进行计数率模式和MSV模式线性拟合,裂变电离室最大线性度为-1.23%。

基于Geant4的裂变核素中子角关联分布数值模拟

为了打破目前通过实验手段对中子角关联进行测量时受到实验条件限制的问题,使用蒙特卡洛方法,依托Geant4软件搭建了一套中子角关联测量模型,对235U、238U、239Pu、240Pu以及252Cf进行数值模拟,得到了这5种裂变核素的中子角关联分布。结果表明:在相同条件下,不同裂变核素之间的中子角关联分布存在差异;使用测量模型得到的不同核素中子角关联分布与国外实验结果重合度较高。

Product yields for the photofission of ^(232)Th,^(234,238)U,^(237)Np,and ^(239,240,242)Pu actinides at various incident photon energies

Photofission fragments mass yield for^(232)Th,^(234;238) U,^(237) Np, and^(239;240;242) Pu isotopes are investigated.The calculations are done using a developed approach based on Gorodisskiy's phenomenological formalism. The Gorodisskiy's method is developed to be applied for the neutron-induced fission. Here we revised it for application to photofission. The effect of emitted neutron prior to fission on the fission fragment mass yields has also been studied. The peak-to-valley ratio is extracted for the240 Pu isotope as a function of energy. Obtained results of the present formalism are compared with the available experimental data. Satisfactory agreement is achieved between the results of present approach and the experimental data.

Numerical analysis on element creation by nuclear transmutation of fission products

A burnup calculation was performed to analyze the Apr`es ORIENT process, which aims to create highlyvaluable elements from fission products separated from spent nuclear fuels. The basic idea is to use nuclear transmutation induced by a neutron capture reaction followed by a β-decay, thus changing the atomic number Z of a target element in fission products by 1 unit. LWR(PWR) and FBR(MONJU) were considered as the transmutation devices. High rates of creation were obtained in some cases of platinum group metals(44Ru by FBR,46 Pd by LWR) and rare earth(64Gd by LWR,66 Dy by FBR). Therefore, systems based on LWR and FBR have their own advantages depending on target elements. Furthermore, it was found that creation rates of even Z(= Z + 1) elements from odd Z ones were higher than the opposite cases. This creation rate of an element was interpreted in terms of "average 1-group neutron capture cross section of the corresponding target element σc Z defined in this work. General trends of the creation rate of an even(odd) Z element from the corresponding odd(even) Z one were found to be proportional to the 0.78th(0.63th) power of σc Z, however with noticeable dispersion. The difference in the powers in the above analysis was explained by the difference in the number of stable isotopes caused by the even-odd effect of Z.

Fusion Neutron Flux Detector for the ITER

Two fission chambers with different amounts of fissile material （enriched 90% uranium-235） have been manufactured for neutron flux detection in a thermonuclear fusion device. The characteristics of neutron signal and its discrimination from other signals, and a plateau of high voltage between the anode and cathode have been validated in a thermal neutron source. The energy responses of the two fission chambers at seven energy levels have been calibrated in an accelerator fast neutron source and the results agree well with the simulations.

Measurement of the neutron total cross section of carbon at the Back-n white neutron beam of CSNS

To verify the performance of the neutron total cross-sectional spectrometer, the neutron total cross section of carbon is initially measured in the energy range of 1 eV to 20 MeV using the time-of-flight method. The measurement is performed at the Back-n white neutron source with a 76-m time-of-flight path using the China Spallation Neutron Source. A multilayer fast fission chamber with 235U and 238U is employed as the neutron detector. The diameter and thickness of the natural graphite sample are 70 mm and 40 mm, respectively. Signal waveforms are collected using a data acquisition system. Off-line data processing was used to obtain the neutron time-of-flight spectra and transmissions. The uncertainty of the counting statistics is generally approximately 3% for each bin in the energy range of 1–20 MeV. It is determined that the results for the neutron total cross section of carbon obtained using ^235U cells are in good agreement with the results obtained using 238U cells within limits of statistical uncertainty. Moreover, the measured total cross sections show good agreement with the broadening evaluated data.

A digital wide range neutron flux measuring system for HL-2A

To achieve wide-range, high-integration, and real-time performance on the neutron flux measurement on the HL-2A tokamak, a digital neutron flux measuring（DNFM） system based on the peripheral component interconnection（PCI） e Xtension for Instrumentation express（PXIe） bus was designed.This system comprises a charge-sensitive preamplifier and a field programmable gate array（FPGA）-based main electronics plug-in. The DNFM totally covers source-range and intermediate-range neutron flux measurements, and increases system integration by a large margin through joining the pulse-counting mode and Campbell mode. Meanwhile, the neutron flux estimation method based on pulse piling proportions is able to choose and switch measuring modes in accordance with current flux, and this ensures the accuracy of measurements when the neutron flux changes suddenly. It has been demonstrated by simulated signals that the DNFM enhances the full-scale measuring range up to 1.9×10^8cm^-2s^-1, with relative error below 6.1%. The DNFM has been verified to provide a high temporal sensitivity at 10 ms time intervals on a single fission chamber on HL-2A.