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翻訳と辞書　辞書検索 [ 開発暫定版 ] スポンサード リンク nuclear reactor physics ： ウィキペディア英語版 nuclear reactor physics Nuclear reactor physics is the branch of science that deals with the study and application of chain reaction to induce a controlled rate of fission in a nuclear reactor for the production of energy.〔van Dam, H., van der Hagen, T. H. J. J., & Hoogenboom, J. E. (2005). ''Nuclear reactor physics''. Retrieved from http://www.janleenkloosterman.nl/reports/ap3341.pdf〕 Most nuclear reactors use a chain reaction to induce a controlled rate of nuclear fission in fissile material, releasing both energy and free neutrons. A reactor consists of an assembly of nuclear fuel (a reactor core), usually surrounded by a neutron moderator such as regular water, heavy water, graphite, or zirconium hydride, and fitted with mechanisms such as control rods that control the rate of the reaction. The physics of nuclear fission has several quirks that affect the design and behavior of nuclear reactors. This article presents a general overview of the physics of nuclear reactors and their behavior. ==Criticality== In a nuclear reactor, the neutron population at any instant is a function of the rate of neutron production (due to fission processes) and the rate of neutron losses (due to non-fission absorption mechanisms and leakage from the system). When a reactor’s neutron population remains steady from one generation to the next (creating as many new neutrons as are lost), the fission chain reaction is self-sustaining and the reactor's condition is referred to as "critical". When the reactor’s neutron production exceeds losses, characterized by increasing power level, it is considered "supercritical", and when losses dominate, it is considered "subcritical" and exhibits decreasing power. The "Six-factor formula" is the neutron life-cycle balance equation, which includes six separate factors, the product of which is equal to the ratio of the number of neutrons in any generation to that of the previous one; this parameter is called the effective multiplication factor k, also denoted by Keff, where k = Є ''L''f ρ ''L''th ''f'' η, where Є = "fast-fission factor", ''L''f = "fast non-leakage factor", ρ = "resonance escape probability", ''L''th = "thermal non-leakage factor", ''f'' = "thermal fuel utilization factor", and η = "reproduction factor". This equation's factors are roughly in order of potential occurrence for a fission born neutron during critical operation. As already mentioned before, k = (Neutrons produced in one generation)/(Neutrons produced in the previous generation). In other words, when the reactor is critical, k = 1; when the reactor is subcritical, k < 1; and when the reactor is supercritical, k > 1. "Reactivity" is an expression of the departure from criticality. δk = (k - 1)/k When the reactor is critical, δk = 0. When the reactor is subcritical, δk < 0. When the reactor is supercritical, δk > 0. Reactivity is also represented by the lowercase Greek letter rho (ρ). Reactivity is commonly expressed in decimals or percentages or pcm (per cent mille) of Δk/k. When reactivity ρ is expressed in units of delayed neutron fraction β, the unit is called the ''dollar''. If we write 'N' for the number of free neutrons in a reactor core and '$\backslash tau$' for the average lifetime of each neutron (before it either escapes from the core or is absorbed by a nucleus), then the reactor will follow differential equation (the ''evolution equation'') :$dN/dt\; =\; \backslash alpha\; N/\backslash tau$ where $\backslash alpha$ is a constant of proportionality, and $dN/dt$ is the rate of change of the neutron count in the core. This type of differential equation describes exponential growth or exponential decay, depending on the sign of the constant $\backslash alpha$, which is just the expected number of neutrons after one average neutron lifetime has elapsed: :$\backslash alpha\; =\; P\_P\_\; n\_\; -\; P\_\; -\; P\_$ Here, $P\_$ is the probability that a particular neutron will strike a fuel nucleus, $P\_$ is the probability that the neutron, having struck the fuel, will cause that nucleus to undergo fission, $P\_$ is the probability that it will be absorbed by something other than fuel, and $P\_$ is the probability that it will "escape" by leaving the core altogether. $n\_$ is the number of neutrons produced, on average, by a fission event—it is between 2 and 3 for both 235U and 239Pu. If $\backslash alpha$ is positive, then the core is ''supercritical'' and the rate of neutron production will grow exponentially until some other effect stops the growth. If $\backslash alpha$ is negative, then the core is "subcritical" and the number of free neutrons in the core will shrink exponentially until it reaches an equilibrium at zero (or the background level from spontaneous fission). If $\backslash alpha$ is exactly zero, then the reactor is ''critical'' and its output does not vary in time ($dN/dt\; =\; 0$, from above). Nuclear reactors are engineered to reduce $P\_$ and $P\_$. Small, compact structures reduce the probability of direct escape by minimizing the surface area of the core, and some materials (such as graphite) can reflect some neutrons back into the core, further reducing $P\_$. The probability of fission, $P\_$, depends on the nuclear physics of the fuel, and is often expressed as a cross section. Reactors are usually controlled by adjusting $P\_$. Control rods made of a strongly neutron-absorbent material such as cadmium or boron can be inserted into the core: any neutron that happens to impact the control rod is lost from the chain reaction, reducing $\backslash alpha$. $P\_$ is also controlled by the recent history of the reactor core itself (see below). 抄文引用元・出典: フリー百科事典『 ウィキペディア（Wikipedia）』 ■ウィキペディアで「nuclear reactor physics」の詳細全文を読む スポンサード リンク 翻訳と辞書 : 翻訳のためのインターネットリソース Copyright(C) kotoba.ne.jp 1997-2016. All Rights Reserved.