Category Archives: AN INTRODUCTION. TO THE ENGINEERING. OF FAST NUCLEAR REACTORS

Computation — the Monte Carlo Method

Transport theory and diffusion theory are based on equations that describe the average behaviour of large numbers of neutrons as they interact with large numbers of nuclei. As the preceding paragraphs show the equations are complex and their solution by numerical means even more so. This is in contrast to the actual behaviour of individual neutrons, which is quite simple: […]

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COOLANT CIRCUITS AND. STEAM PLANT

1.1 INTRODUCTION 1.1.1 Choice of Coolant This chapter describes the engineering of the remainder of the plant in a fast reactor electricity-generating station, apart from the reactor core that is the subject of Chapter 3. The nature of the plant depends primarily on the coolant, which is the heat-transfer medium. The main considerations determining the choice of the coolant were […]

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Post-Accident Cooling

Best estimate transition-phase calculations, supported by the results of small-scale experiments, indicate that, after a core-disruptive acci­dent, the fuel would be in the form of a mass of debris dispersed in the primary coolant. The internal structure of the reactor vessel (in the case of a pool reactor, the inner vessel, the primary pumps, the intermediate heat exchangers and the […]

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WHAT FAST REACTORS CAN DO Chain Reactions

Early in 1939 Meitner and Frisch suggested that the correct interpreta­tion of the results observed when uranium is bombarded with neutrons is that the uranium nuclei undergo fission. Within a few months two very important things became clear: that fission releases a large amount of energy, and that fission of a nucleus by one neutron liberates usually two or three […]

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REACTIVITY COEFFICIENTS 1.6.1 Effects of Temperature

Temperature affects reactivity in a number of ways. The temperat­ure of the structure affects the dimensions of the reactor core and sometimes the relative position of the various parts: the densities of all the materials depend on temperature (but the most important effects arise from changes in the density of the coolant), and the temperature of the fuel affects the […]

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OTHER FUEL MATERIALS

2.6.1 Carbide Extensive work has been done on mixed carbide fuel in India in con­nection with the thorium-based breeder cycle. To initiate this cycle reactors fuelled with 239Pu but with 232Th rather than 238U as the fertile material are needed. In such reactors uranium is essentially redund­ant, so mixed oxide, which as indicated in section 2.3.3 is limited to about […]

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