Reactor physics

Several of the reactor physics parameters are both measurable and calculable from more fundamental properties such as the energy-dependent neutron cross sections and atom number densities. An extensive database. Evaluated Nuclear Data Files (ENDF), has been maintained over several decades. There is an interplay between theory and experiment to guide design of a reactor, as in other engineering systems. 

Electrical power Reactor physics Reactor systems Accident phenomenology... 

This chapter develops the techniques needed to analyze multiple and complex reactions in stirred tank reactors. Physical properties may be variable. Also treated is the common industrial practice of using reactor combinations, such as a stirred tank in series with a tubular reactor, to accomplish the overall reaction. 

The reactor volume is taken as the volume of the reactor physically occupied by the reacting fluids. It does not include the volume occupied by agitation devices, heat exchange equipment, or head-room above liquids. One may arbitrarily select the temperature, pressure, and even the state of aggregation (gas or liquid) at which the volumetric flow rate to the reactor will be measured. For design calculations it is usually convenient to choose the reference conditions as those that prevail at the the inlet to the reactor. However, it is easy to convert to any other basis if the pressure-volume-temperature behavior of the system is known. Since the reference volumetric flow rate is arbitrary, care must be taken to specify precisely the reference conditions in order to allow for proper interpretation of the resultant space time. Unless an explicit statement is made to the contrary, we will choose our reference state as that prevailing at the reactor inlet and emphasize this choice by the use of the subscript zero. Henceforth,... 

Walter, A.E. The visible but not imaginary numbers. In ANS International Conference on Mathematics and Computations, Reactor Physics and Environmental Analyses Portland, Oregon, 1995. 

Oka, Y. Physics of supercritical-pressure light water cooled reactors. Proc. 1998 Frederic Joliot Summer School in Reactor Physics, Caderache, France, and references cited herein, 1998 240-259 pp. 

H. Mandel, Heavy Water Organic Cooled Reactor, Physical Properties of Some Polyphenyl Coolants, AEC Report A l-CE-15, Apr. 15, 1966. 

After each growth cycle, the reactors must be opened, the wafers removed, and the lower portion of the reactor physically cleaned. The lower quartz reactor and the bottom plate (base plate) are scraped clean using a metal tool, and the particulate material (mixture of GaAs, GaAsP, arsenic oxides and phosphorus oxides) is collected in a metal container positioned below the vertical reactor. 

Dasgupta, R. and B. Maiti hid. Eng. Chem. Process Des. Dev. 25(2), 381 (1986). Mandel, H. Heavy Water Organic Cooled Reactor, Physical Properties of Some Polyphenyl Coolants, AEC Report A l-CE-15, Apr. 15, 1966. 

Stacey, W.M.. Nuclear Reactor Physics, John Wiley. Sons, Tnc., New York, NY, 2001. 

To adequately treat these many applications and to illustrate the specific ways in which decay data make useful, if not crucial, contributions to them is a task that lies beyond the space and time limitations of this paper. We have thus chosen to limit the scope of this presentation to the discussion of several selected examples, drawn mostly from the area of fission-reactor physics. These include the results of recent significant developments in actinide-nuclide decay data and, in the spirit of this symposium, decay data of fission-product nuclides off the line of p stability and some of the problems and challenges they present to both experimental capabilities and nuclear theory. 

Safely implementing a thermochemical nuclear hydrogen generation scheme requires a robust understanding of the interaction between the nuclear plant and the chemical plant. In turn, this requires robust models of the chemical plant, reactor thermal-hydraulics and reactor physics. Efforts have been conducted in both the transient modelling of the sulphur-iodine (S-I) and hybrid sulphur (HyS) thermochemical cycles, as well as coupling to models of the pebble bed modular reactor (PBMR-268) (Brown, 2009). 

Bezhunov, G.M., et al. (1989) Experimental and analytical study of prompt neutron lifetime in fast reactors with moderation zones in the reflector, in Neutronic problems of nuclear power system safety paper theses VI AU-Union Workshop on Reactor Physics, Tsniiatominform Publishers, Moscow, pp.48-50 (in Russian). 

S. E. Liverhout, Elementary Introduction to Reactor Physics, Wiley, New York, 1960... 

R. W. Conn, V. A. Chuyanov, N. Inoue, D. R. Sweetman, The International Thermonuclear Experimental Reactor, ientific American, April 1992, 75 J. G. Cordey, R. J. Goldston, R. R. Parker, Progress Toward a Tokomak Fusion Reactor, Physics Today, Jan. 1992, 22... 

The preparation and fabrication methods and their conditions described in Chapter 3 dictate the general characteristics of the membranes produced which, in turn, affect their performance as separators or reactors. Physical, chemical and surface properties of inorganic membranes will be described in detail without going into discussions on specific applications which will be treated in later chapters. Therefore, much of this chapter is devoted to characterization techniques and the general characteristics data that they generate. 

Cordey, J. Geoffrey. Progress toward a Tokamak Fusion Reactor. Physics Today January 1992, pp. 22-30. 

GPT is a method of evaluating the effects of cross-section perturbations on quantities that can be formulated as integral responses, such as reactivity and power density. An initial requirement is an exact solution of a reactor physics model for a reference core configuration. In FORMOSA-P the reference neutronics model is a two-dimensional Cartesian [x-y] geometry implementation of the nodal expansion method (NEM) to solve the two-group, steady-state neutron diffusion equation ... 

D.J. Kropaczek, P.J. Turinsky, G.T. Parks and G.I. Maldonado, Reactor Physics and Reactor Computations (Edited by Y.Ronen and E.Elias), Ben Gurion University of the Negev Press (1994) 572. 

E.L. Wachspress, Iterative Solution to Elliptic Systems and Applications to the Neutron Diffusion Equations of Reactor Physics, Prentice-Hall, Englewood Cliffs, NJ (1966). 

I have been appointed to the position of Director of the Nuclear Science and Energy Directorate, which covers from the fundamental studies such as nuclear data, reactor physics, materials sciences as well as the research development on VHTR and nuclear hydrogen research. 

Hamilton, David P, EDITOR "A Fusion First", Science Scope, Science, Vol. 254, No. 5034, November 15,1991, Page 927 Sweet, William, Super Powers Promote Design Effort for Fusion Demonstration Reactor", Physics Today, January 1988, Page 75 Thon en, D. E., "Charging Their Way Toward Fusion , Science News, December 21, 1985, Page 389... 

In this paper we will discuss the application of a general batch reactor model that considers the reaction kinetics, heats of reaction, heat transfer properties of the reactor, physical properties of the reactants and the products, to predict 1) The concentration profile of the products, thus enabling process optimization 2) Temperature profile during the reaction, which provides a way to avoid conditions that lead to a thermal runaway 3) Temperature profile of the jacket fluid while maintaining a preset reactor temperature 4) Total pressure in the reactor, gas flow rates and partial pressure of different components. The model would also allow continuous addition of materials of different composition at different rates of addition. 

Thus the constant of proportionality has decreased by about 30% over the life of the core. More accurate relationships between thermal power density and neutron density at different stages of the reactor run may be available from the design calculations or from plant-specific reactor physics data. 

The neutron energy cycle of the one-group reactor-physics model to be used is shovm in Fig. 3.28. 

We shall be interested in estimating the fuel-cycle performance of this reactor during a steady-state cycle, in which fresh fuel has a enrichment of 3.2 w/o and spent fuel has a enrichment of around 1.0 w/o and also contains around 0.6 w/o fissile plutonium. The reference design condition used to evaluate effective neutron cross sections and other reactor physics parameters during irradiation is taken to be 2.7 w/o This value, slightly hi er than the arithmetic mean of the fissile content of fuel at the begiiming and end of irradiation, is intended to reflect the hl er cross section of fissile plutonium compared with... 

Templin, L. J. Reactor Physics Constants, Report ANI SSOO, 1963. 

B. G. Carlson and K. D. Lathrop, Transport Theory—The Method of Discrete Ordinates, in H. Greenspan, G N. Kelber, and D. Okrent (eds.), Computing Methods in Reactor Physics, Gordon and Breach, New York, 1968. 

The calculation of average cross sections is beyond the scope of this text. The reader should consult the proper books on reactor physics. The main purpose of this short discussion is to alert the reader to the fact that when polyenergetic neutrons are involved, an appropriate average cross section should be used for the calculation of reaction rates. 

Fusion Reactor Physics-Principles and Technology Kammash 1975... 

J. G. Cordey, R. j. Goldston and R. R. Parker, Progress Toward a Tokamak Fusion Reactor, Physics Today, Jan. 1992, 22. 

---