Geant4 simulation of 238U(n,f) reaction induced by D-T neutron source

Knowledge of actinides(n,f) fission process induced by neutron is of importance in the field of nuclear power and nuclear engineering,especially for reactor applications.In this work,fission characteristics of^(238)U(n,f) reaction induced by D-T neutron source were simulated with Geant4 code from multiple perspectives,including the fission production yields,total nubar,kinetic energy distribution,fission neutron spectrum and cumulative γ-ray spectrum of the fission products.The simulation results agree well with the experimental nuclear reaction data(EXFOR) and evaluated nuclear data(ENDF).Mainly,this work was to examine the rationality of the parametric nuclear fission model in Geant4 and to direct our future experimental measurements for the cumulative fission yields of ^(238)U(n,f) reaction.

^(238)U(n,f)短寿命产物核累积产额的评价(英文)

为满足堆内或核爆中链式反应过程的燃耗值的计算需要,对裂变谱中子和14 MeV中子诱发238U裂变的短寿命产物核的累积产额进行了评价。评价利用了所有可利用的实验数据,经物理分析后,使用AVERAGE程序加权平均,用ZOTT程序进行同时评价,给出了所要求能点的唯一最佳推荐数据,并将评价结果与ENDF/B-VII ,JEF-2 .2 ,JENDL-3 .2和CENDL-2的推荐数据进行了比较。评价结果将用于CENDL-2的更新与升级。

BEAVRS堆芯k_(eff)的敏感性与不确定性分析

核数据不确定性分析影响着反应堆安全,在反应堆堆芯物理计算过程中具有重要意义。利用SCALE6.1程序包中KENO模块建立反应堆模拟评估和验证基准BEAVRS(Benchmark for Evaluation and Validation of Reactor Simulations)第一循环热态零功率堆芯物理模型,采用TSUNAMI-3D模块开展k_(eff)的敏感性与不确定性分析,分析了不同燃料富集度、不同温度对k_(eff)敏感性与不确定性的影响。结果表明:核数据不确定性导致BEAVRS模型的k_(eff)总的不确定性为0.5016%;^(235)U的平均裂变中子数敏感性导致k_(eff)的敏感性系数最大(0.92658);对k_(eff)不确定性贡献最大的是238U(n,γ)反应截面,为0.29814%;在燃料富集度降低、温度上升时,238U(n,γ)反应截面不确定性会导致k_(eff)的不确定性增大。因此,在开展反应堆堆芯物理计算过程中,应重点关注238U(n,γ)反应截面信息。

Double differential cross sections of light charged particle production for the n+^238U reaction

Production of light complex particles from the n＋^238u reaction is analyzed with the exciton model including the improved Iwamoto-Harada pickup mechanism for the preequilibrium process. It is allowed that some of the nucleons forming the complex ejectile come from levels below the Fermi energy, and the intrinsic structure of the emitted particle is taken into account. The equilibrium-state emissions are also considered by using Hauser- Feshbach theory with the width fluctuation correction and the evaporation model angular distributions, energy spectra and double differential cross sections of neutron, alpha emissions for the n＋^238U reaction are consistently calculated and analyzed with the energy range En ≤150 MeV. ENDF-formatted nuclear data including information charged particles are obtained. Moreover, all cross sections, proton, deuteron, triton and nuclear theoretical models in about the production of light

Cross-sections of the ^(238)U(n,γ) ^(239)U reaction in the 3.0-7.0 MeV energy region measured by relative activation method

The reaction cross-sections of^(238)U(n,γ)^(239)U have been experimentally determined at neutron energies of6.117±0.119 MeV,4.626±0.086 MeV,and 3.622±0.348 MeV employing the relative activation approach along with the off-line γ-ray spectroscopy method.The D(d,n)3He reaction was utilized to obtain monoenergetic neutrons of the required energy,and the^(197)Au(n,γ)^(198)Au reaction cross-sections were adopted as the referential standard to ascertain the neutron capture cross-sections of^(238)U.Furthermore,the effects of low-energy scattered neutrons,neutron fluence fluctuations,counting of geometric corrections when measuring γ-rays,and neutron and γ-ray self-absorption caused by the sample thickness have been considered and revised in the present work.For a comparison with experimental results,the cross-sections of the^(238)U(n,γ)^(239)U reaction were calculated theoretically with the original parametric TALYS-1.9 program.The experimental measurements were in contrast to previous experimental re sults and the evaluation data available for ROSFOND-2010,CENDL-3.2 and ENDF/B-VIII.0.

Measurement and analysis of the ^(238)U(n, 2n) reaction rate in depleted uranium/polyethylene shells

In order to check the conceptual design of the subcritical blanket in a fusion-fission hybrid reactor, a depleted uranium/polyethylene simulation device with alternate shells has been established. The measurement of the 23SU（n, 2n） reaction rate was carried out using an activation technique, by measuring the 208 keV T rays emitted from 237U. The self-absorption of depleted uranium foils with different thicknesses was experimentally corrected. The distribution of the 23SU（n, 2n） reaction rate at 90° to the incident D＋ beam was obtained, with uncertainty between 5.3% and 6.0%. The experiment was analyzed using MCNP5 code with the ENDF/BVI library, and the calculated results are all about 5% higher than the measured results.

Calculation of the Neutron Direct Inelastic Scattering cross Section of ~ (238) U

In this work, Rotation model and rotation vibration coupled channel optical model (CCOM) were first used to carry out systematic calculation of neutron direct inelastic scattering cross section (DISCS) for the reaction 238 U (n,n′) with an incident energy from 0 01 MeV to 20 0 MeV . The number of coupled energy levels involved in this calculation increased to eight at the first time, namely 0 +, 2 +, 4 +, 6 +, 8 + in the ground rotation band of 238 U and 1 -, 3 -, 5 - in the octupole vibration band with K=0 -. Some physical problems, such as how to get the optical model parameters of deformed nuclei and phonon amplitudes, are discussed.

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.

Pre-neutron-emission mass distributions for reaction ^(238)U(n,f) up to 60 MeV

Abstract： The pre-neutron-emission mass distributions for reaction ^238U（n, f） up to 60 MeV are systematically studied with an empirical fission potential model. The energy dependence of the peaks and valleys of the pre-neutronemission mass distributions is described by an exponential form based on the newly measured data. The energy dependence of evaporation neutrons before scission is also considered, which plays a crucial role in the reasonable description of the mass distributions. The measured ^238U（n, f） are reasonably well reproduced up to 60 predicted using this approach. data of the pre-neutron-emission mass distributions for reaction MeV. The mass distributions at unmeasured energies are also