Reactor burn-up physics by Panel on Reactor Burn-up Physics Vienna 1971.

Cover of: Reactor burn-up physics | Panel on Reactor Burn-up Physics Vienna 1971.

Published by International Atomic Energy Agency in Vienna .

Written in English

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Subjects:

  • Nuclear fuels -- Congresses.,
  • Nuclear reactors -- Congresses.

Edition Notes

Book details

Statementproceedings of a Panel on Reactor Burn-up Physics organized by the International Atomic Energy Agency held in Vienna, 12-16 July 1971.
SeriesPanel proceedings series, Panel proceedings series.
ContributionsInternational Atomic Energy Agency.
Classifications
LC ClassificationsTK9207 .P35 1971
The Physical Object
Pagination296 p.
Number of Pages296
ID Numbers
Open LibraryOL5462631M
LC Control Number73165268

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Reactor Fueling Characteristics. Radioactive Waste Radioactivity. Hazard Potential. Risk Factor. Burning Surplus Weapons‐Grade Uranium and Plutonium Composition of Weapons‐Grade Uranium and Plutonium.

Physics Differences Between Weapons‐ and Reactor‐Grade Plutonium‐Fueled Reactors. In short, Stacey's book is a good reference for advanced topics, but is too rushed in its explanation of fundamentals to be a primary or only reference, especially if you haven't previously studied reactor physics.

It also serves as a good "halfway point" between diffusion-based reactor physics texts, and transport theory books like Lewis & Miller/5(5). In short, Stacey's book is a good reference for advanced topics, but is too rushed in its explanation of fundamentals to be a primary or only reference, especially if you haven't previously studied reactor physics.

It also serves as a good "halfway point" between diffusion-based reactor physics texts, and transport theory books like Lewis & by: This chapter discusses the burn-up calculations that deal with the time evolution of reactor parameters over long periods involving the complete lifetime of the reactor.

Reactor burn-up physics book these calculations, the time derivative of the neutron flux can be neglected and the static form of the Boltzmann equation can be used. Purchase Physics of High-Temperature Reactors - 1st Edition.

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to most power reactors like BWR and PWR in which a multiple-batch refueling scheme is adopted. INTRODUCTION The main objective of burn up calculation is to determine the characteristics of the core that vary with operation time. Burnup calculation consists of the main parts: Flux distribution calculation with a diffusion code.

In nuclear power technology, burnup (also known as fuel utilization) is a measure of how much energy is extracted from a primary nuclear fuel source. It is measured both as the fraction of fuel atoms that underwent fission in %FIMA (fissions per initial metal atom) and as the actual energy released per mass of initial fuel in gigawatt-days/metric ton of heavy metal (GWd/tHM), or similar units.

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Fuel Burnup – Core Burnup. In nuclear engineering, fuel burnup (also known as fuel utilization) is a measure of how much energy is extracted from a nuclear fuel and a measure of fuel depletion.

The most commonly defined as the fission energy release per unit mass of fuel in megawatt-days per metric ton of heavy metal of uranium (MWd/tHM), or similar units. The "Preparatory Report" sections in this book consist of exercises that are very helpful to understand the nuclear reactor physics.

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Neutron Fluence and Fuel Burnup – Neutrons per Kilobarn. Neutron fluence can be used as a measure of fuel burnup as well. Since reaction rate is given by the product RR = Ф.Σ, the rate of burnup is proportional to the neutron accumulated burnup over a specific period of time (t) is therefore proportional to the product of flux and time (F = Ф.

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Lee.The absolute activity of each centimeter of the FE was measured and compared with reactor physics calculations. The ORIGEN2, a one-group depletion and radioactive decay computer code, was applied to calculate the activity of the Cs and the burn-up of selected by: 9.

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