Dynamical Modeling of the Nuclear Fission Process at Low Excitation Energies

Two recipes for modeling the dynamics of the nuclear fission process are known in literature. The underlying equations contain the driving, dissipative, and random forces. The two recipes are mostly different in the prescriptions for the driving force. In this work we carefully compare these driving forces and the resulting fission rates. It turns out that the rates may be very close or strongly different depending on the value the shell correction to the nuclear deformation energy. We give arguments in favor of one of the recipes.

Sensitivity impacts owing to the variations in the type of zero-range pairing forces on the fission properties using the density functional theory

Using the Skyrme density functional theory,potential energy surfaces of^(240)Pu with constraints on the axial quadrupole and octupole deformations(q_(20)and q_(30))were calculated.The volume-like and surface-like pairing forces,as well as a combination of these two forces,were used for the Hartree–Fock–Bogoliubov approximation.Variations in the least-energy fission path,fission barrier,pairing energy,total kinetic energy,scission line,and mass distribution of the fission fragments based on the different forms of the pairing forces were analyzed and discussed.The fission dynamics were studied based on the timedependent generator coordinate method plus the Gaussian overlap approximation.The results demonstrated a sensitivity of the mass and charge distributions of the fission fragments on the form of the pairing force.Based on the investigation of the neutron-induced fission of^(239)Pu,among the volume,mixed,and surface pairing forces,the mixed pairing force presented a good reproduction of the experimental data.

Project New Orion: Pulsed Nuclear Space Propulsion Using Photofission Activated by Ultra-Intense Laser

Project New Orion entails a pulsed nuclear space propulsion system that utilizes photofission through the implementation of an ultra-intense laser. The historical origins derive from the endeavors of Project Orion, which utilized thermonuclear devices to impart a considerable velocity increment on the respective spacecraft. The shear magnitude of Project Orion significantly detracts from the likelihood of progressive research development testing and evaluation. Project New Orion incorporates a more feasible pathway for the progressive research development testing and evaluation of the pulsed nuclear space propulsion system. Photofission through the application of an ultra-intense laser enables a much more controllable and scalable nuclear yield. The energy source for the ultra-intense laser is derived from a first stage liquid hydrogen and liquid oxygen chemical propulsion system. A portion of the thermal/kinetic energy of the rocket propulsive fluid is converted to electrical energy through a magneto-hydrodynamic generator with cryogenic propellant densification for facilitating the integral superconducting magnets. Fundamental analysis of Project New Orion demonstrates the capacity to impart a meaningful velocity increment through ultra-intense laser derived photofission on a small spacecraft.

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.

Fission Fragment Decay Heat by Using the Most Recent Evaluated Nuclear Data Library ENDF/B-VIII

In this paper, a home-made code was designed to calculate the decay heat emitted by fission fragments as a result of successive radioactive emissions after a fission burst. The nuclear data necessary for the calculations was extracted from the latest version of the Evaluated Nuclear Data Library ENDF/B-VIII.0. The code can calculate the decay heat of thermal and fast neutron-induced fission reactions on the isotopes of Thorium, Protactinium, Uranium, Neptunium, Plutonium, Americium, Curium, California, Einsteinium, and Fermium. A numerical method was used in this work to calculate the decay heat of all fission fragments due to the individual thermal or fast fissions of the isotopes of the previous ten actinides. The most influential nuclei in the decay heat were also identified at different times after the fission event. Moreover, the code showed high capability in calculating the fission fragments inventories and decay heats due to the decay of fission fragments of 31 fissionable nuclei.

Prediction of the Average Decay Heat per Fission for MOX Nuclear Fuel

MIXED Oxide Nuclear fuel (MOX) contains both uranium and plutonium in oxidized form. It is important to calculate the nuclear decay heat due to the single thermal fission (fission due to 0.0235 eV neutron) for all fissile nuclei in the MOX fuels (U235, Pu239, and Pu241). These fissile nuclei are the main source of the decay heat in MOX fuel. Decay heat calculation of the weighted fissile material content in MOX fuel is also important. A numerical method was used in this work to calculate the concentrations of all fission products due to the individual thermal fission of the three fissile materials as a function of time N(t). The decay heat calculations for the three fissile materials are directly calculated using the summation method by knowing the different concentrations of fission products over time. The average decay heat of the MOX fuel in induced thermal fission is also concluded. The most influential nuclei in the decay heat were also identified. The method used has been validated by several comparisons before, but the new in this work is using the most recent Evaluated Nuclear Data Library ENDF/B-VIII.0. Calculations of decay heat show very common trends for a period of 107 sec after the fission burst of thermal fissions of individual fissile nuclei. Moreover, the code showed high capability in calculating the fission fragments inventories and decay heats due to the decay of fission fragments of 31 fissionable nuclei.

Waste Transmutation and Nuclear Energy Generation Using a Tokamak Fusion-Fission Hybrid Reactor

A tokamak fusion-fission hybrid reatcor is proposed as one of candidates for disposal ofthe long-lived actinides and fission product wastes and supply of future energy.To assess thefeasibility of transmutation of long-lived radiowastes using fusion-fission hybrid reactors,afusion core design is presented and several possible conceptual blankets are studied,for,re-spectively,actinides transmutation and fission product transmutation.The results show thatactinides and fission products may be effectively transmuted using the presented hybrid reac-tors.

^(252)Cf自发裂变K X射线发射与动能-电荷关系

原子核裂变后多物理量间的关联测量是认识裂变过程直接有效的实验手段,然而由于初级裂变产物准确的电荷鉴别仍面临技术困难,电荷相关的多参数研究相对匮乏.为此,通过高分辨的低能高纯锗探测器和金硅面垒探测器开展了^(252)Cf自发裂变的裂变碎片K X射线和动能的符合测量.利用K X射线可以很好地鉴别电荷数Z=39—62的裂变碎片,电荷分辨ΔZ≈0.7,K X射线产额呈现强烈的电荷相关性.借助K X射线给出了碎片平均动能和平均总动能及其分布宽度随核电荷数的分布,轻碎片动能分布具有鲜明的奇偶效应,偶Z碎片的动能比奇Z碎片的高约0.48 MeV;平均总动能在Z=52—53处达到峰值,总动能分布宽度在Z=56附近呈现凹坑,这反映了形变壳结构对断点形状的显著影响.裂变碎片K X射线发射的信息及动能-电荷关系研究可为裂变独立产额测量和裂变理论模型的检验提供必要的参考数据.

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。

核燃料裂变气体行为研究进展

核燃料裂变气体行为是影响核燃料性能最为关键的因素之一。裂变气体是核燃料在裂变过程中产生的惰性气体,性质较为稳定,但其不溶于燃料基体,多以气体形式存留在燃料内。存留在燃料基体内的裂变气体会造成燃料肿胀,而从基体中释放到气腔的裂变气体会影响燃料和包壳间气隙的热导率和气压。无论是造成肿胀还是影响热导率和气压都会对核燃料的安全造成威胁,因此对裂变气体行为的研究具有重要意义。迄今为止,对裂变气体行为的相关研究开展了60余年,研究人员对裂变气体行为有了相当深刻的认识,并开发了包括裂变产生、气泡形核、气泡聚合、气泡迁移、气体原子重溶和最终裂变气体释放的一套完整的裂变气体行为理论体系,这套理论体系被广泛应用于核燃料性能分析中,为核燃料设计与性能模拟做出了极大的贡献。本文总结了裂变气体行为理论中多种具体的裂变气体行为,详细地阐述了裂变气体各种具体行为的产生原因及过程,同时针对不同类型核燃料独有的裂变气体行为进行了汇总,归纳了用于不同核燃料裂变气体行为的经验性和机理性模型,最后总结了现今裂变气体行为方向的研究重点。

Nuclear Energy and Its History: Past Consequences, Present Inadequacies and a Perspective for Success

An attempt is made to locate nuclear technology within a logical context considering history, risks, societal catastrophes and perspectives: the need is identified for a new direction in the exploitation in order to restore the role in energy production. We depict the situation coming from a marvelous history of discoveries started at the beginning of the XX century;heroes are recalled who made possible something that is inconceivable today: design, construction and production of electricity in a few years;that history was tainted by intentional nuclear explosions, i.e. the original sin that we are now paying. Then, we attempt to show that the societal risk is an inherent part of the civilization. Restoring the public trust (towards nuclear fission technology) by matching nuclear safety with the current technological status and advancers in risk assessment is the key objective. The “independent assessment”, or a principle for the exploitation of nuclear energy already stated in the 50’s of the previous century, shall then re-appear. This is used to erect the signpost for a “dynamic barricade” to further reduce the risk of operation of nuclear reactors and to match the design with current technological capabilities and with the frontiers of the research.

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。

核测量用裂变电离室宽量程中子注量率测量性能验证

分析了堆外核测量系统中间量程裂变电离室工作原理及宽量程测量的多种工作模式,根据其多工作模式特点研究宽量程中子注量率测量技术,探讨了上堆试验方法。对裂变室脉冲模式和均方压模式情况在反应堆进行性能验证,验证结果表明,该探测器具有超宽的量程范围,探测器输出与中子注量率在脉冲计数模式线性度最大值为1.16%,均方压工作模式线性度最大值为2.06%,中子通量测量上限可达到1010 cm^(-2)·s^(-1)量级,符合AP系列堆外核测量系统中间量程通道的宽量程使用要求,可广泛应用于核电及船用堆外核测量监测系统。

Fundamental Architecture and Performance Analysis of Photofission Pulsed Space Propulsion System Using Ultra-Intense Laser

Photofission enables a unique capability for the domain of non-chemical space propulsion. An ultra-intense laser enables the capacity to induce nuclear fission through the development of bre- msstrahlung photons. A fundamental architecture and performance analysis of a photofission pulsed space propulsion system through the operation of an ultra-intense laser is presented. A historical perspective of previous conceptual nuclear fission propulsion systems is addressed. These applications use neutron derived nuclear fission;however, there is inherent complexity that has precluded further development. The background of photofission is detailed. The conceptual architecture of photofission pulsed space propulsion and fundamental performance parameters are established. The implications are the energy source and ultra-intense laser can be situated far remote from the propulsion system. Advances in supporting laser technologies are anticipated to increase the potential for photofission pulsed space propulsion. The fundamental performance analysis of the photofission pulsed space propulsion system indicates the architecture is feasible for further evaluation.

A desktop-computer simulation for exploring the fission barrier

A model of a fissioning nucleus that splits symmetrically both axially and equatorially is used to show how one can predict the presence of a fission barrier of several tens of MeV for nuclides of mass number A ~ 90 and of ~ 10 MeV for elements such as uranium. While the present model sacrifices some physical realism for the sake of analytic and programming simplicity, it does reproduce the general behavior of the run of fission barrier energy as a function of mass number as revealed by much more sophisticated models. Its intuitive appeal and tractability make it appropriate for presentation in a student-level “Modern Physics” class.

Viewing the Future of Nuclear Power Plants Following the 2011 Disaster in Fukushima Nuclear Power Plant

Concerning the increasing global energy demand, the current paper considers nuclear energy as a solution. Within this context, the 2011 disaster in Fukushima Nuclear Power Plant and, particularly, the technical disorders in boiling water reactors are explained. The deficiency of safety technique in boiling water reactors is explained. The deficiencies in safety procedure of this type of reactors manifested during 2011 earthquake and subsequent tsunami are explained. To complete the discussion, the newer technologies of reactors enabling them to act more safely during natural disasters are introduced. These investigations indicate that despite improvement in the fission reactor technologies, the danger embedded in them still remains. Therefore, the nuclear fusion using Deuterium-Tritium reaction is the best way forward for energy production in the future, and the best candidate of this type of reactors is Tokamak.

A Developed Material as a Nuclear Radiation Shield for Personal Wearing

A new composite of silicone rubber and boric acid was developed to be used as a personal wearing for protection from nuclear radiation. The capability of this material for absorbing thermal neutrons of different intensities followed by a detonation of nuclear weapon has been investigated. This investigation was performed by using californium-252 neutron source of like fission spectrum. The thermal neutron flux was measured behind different thicknesses of the developed material using a BF3 detector. Two positions of measurements were performed;at position near the detonation where the intensity of thermal neutron flux is low and at position far from the detonation where the intensity of thermal neutron is high. For both cases, the contribution of total thermal, initial incident and new produced thermal neutron fluxes are measured. The obtained results indicated that, addition of boron with concentration of about 17% to the silicon rubber tends to decrease the flux by more than 70%.

Pairing effects on the fragment mass distribution of Th,U,Pu,and Cm isotopes

In this article,a comprehensive study of the fission process of Th,U,Pu,and Cm isotopes using a Yukawa-folded meanfield plus standard pairing model is presented.The study focused on analyzing the effects of the pairing interaction on the fragment mass distribution and its dependence on nuclear elongation.The significant role of pairing interactions in the fragment mass distributions of^(230)Th,^(234)U,^(240)Pu,and^(246)Cm was demonstrated.Numerical analysis revealed that increasing the pairing interaction strength decreased the asymmetric fragment mass distribution and increased the symmetric distribution.Furthermore,the odd-even mass differences at symmetric and asymmetric fission points were examined,highlighting their sensitivity to changes in the pairing interaction strength.Systematic analysis of the Th,U,Pu,and Cm isotope fragment mass distributions demonstrated the effectiveness of the model in reproducing the experimental data.In addition,the effects of the zero-point energy and half-width parameter on the fragment mass distribution for^(240)Pu were explored.Thus,this study provides valuable insights into the fission process by emphasizing the importance of pairing interactions and their relationship with nuclear elongation.

Student-level numerical simulation of conditions inside an exploding fission-bomb core

This paper describes a freely-available spread-sheet that has been developed to simulate the conditions of reaction rate, core acceleration and velocity, energy generation, and pressure within a detonating fission-bomb core. When applied to a model of the Hiroshima Little Boy bomb, the spreadsheet predicts a yield of 12.7 kilotons, a figure in reasonable agreement with published values.

裂变燃耗计算中裂变产额数据的适用性评估

针对裂变燃耗计算中低中子注量率条件下实验测量和评价的裂变产额能否应用于高中子注量率条件下裂变燃耗的计算问题,通过裂变核消失量和裂变产物生成量,用解析方法分别计算了低中子注量率(1014cm-2·s-1)和高中子注量率(1030cm-2·s-1)下的裂变燃耗。结果表明,裂变燃耗低时无关中子注量率高低,两种方法的计算结果一致,燃耗增大时差异增大。分析燃耗差异的主要原因为:低中子注量率下是裂变产物生成量的饱和,高中子注量率下是裂变产物在中子作用下的“消失”。用燃耗计算程序CINDER90及其自带的核数据库模拟计算了热中子在高低两种注量率下235U和87Kr,88Kr,144Ce,147Nd等裂变产物的核子数密度随时间的变化关系,据此用两种燃耗计算方法的计算结果与解析分析的结果一致。因此,裂变燃耗深度是影响裂变产额数据适用性的重要因素。当裂变燃耗较低时,无论中子注量率高低,实验室条件下测定的裂变产额等核数据适用于裂变燃耗的计算,但当裂变燃耗较高时,在高中子注量率下需准确评估裂变产物的表观消失截面,在低中子注量率下则需注意短寿命裂变产物的饱和问题。