Nuclear Engineering Handbook by Kenneth D. Kok (ed.)

By Kenneth D. Kok (ed.)

Building upon the good fortune of the 1st version, the Nuclear Engineering Handbook, Second Edition, offers a finished, up to date review of nuclear energy engineering. along with chapters written through prime specialists, this quantity spans a variety of themes within the parts of nuclear energy reactor layout and operation, nuclear gas cycles, and radiation detection. Plant issues of safety are addressed, and the economics of nuclear energy new release within the 21st century are awarded. the second one version additionally comprises complete assurance of new release IV reactor designs, and new details on MRS applied sciences, small modular reactors, and speedy reactors.

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By Kenneth D. Kok (ed.)

Building upon the good fortune of the 1st version, the Nuclear Engineering Handbook, Second Edition, offers a finished, up to date review of nuclear energy engineering. along with chapters written through prime specialists, this quantity spans a variety of themes within the parts of nuclear energy reactor layout and operation, nuclear gas cycles, and radiation detection. Plant issues of safety are addressed, and the economics of nuclear energy new release within the 21st century are awarded. the second one version additionally comprises complete assurance of new release IV reactor designs, and new details on MRS applied sciences, small modular reactors, and speedy reactors.

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3 BTRS The primary function of the BTRS is to vary the RCS boron concentration during reactor power changes which include daily load follow operations. Boron concentration changes are accomplished automatically by the BTRS through an ion exchange (passive) method. The BTRS makes use of a temperature-dependent ion exchange process to store boron from and release boron to the RCS. Operation of the BRS and evaporators is not required during normal load follow operation. As a result, there is a significant reduction in the water to be processed during normal plant operations and a reduction in BRS requirements.

To a large extent, the design of the non-nuclear portion of a Rankine cycle power plant depends only on the steam conditions of temperature, pressure, steam “quality” (how little liquid is present with the vapor), and flow arriving at the turbine, regardless of the heat source. There are safety systems in the non-nuclear part of a nuclear plant that are unique, such as a diesel generator for emergency power. All essential nuclear systems are discussed below. 1) that contains radioactivity is surrounded by a sturdy containment structure whose main purpose is to protect operating personnel and the public.

5 m) 11 ft, 3 in. 7 bar) 35,075,000 lb/h (4419 kg/s) 621°F (327°C) 558°F (292°C) Shell material Channel head material Tube sheet material Tube material Mn–Mo steel Carbon steel clad internally with stainless steel Ni–Mo–Cr–V clad Inconel on primary face Thermally treated Inconel Steam generator weights Dry weight, in place Normal operating weight, in place Flooded weight (cold) 346 tons (314,000 kg) 422 tons (384,000 kg) 560 tons (508,000 kg) 920 psia (63 bar) 964 psia (66 bar) 1000 psia (69 bar) chemical neutron absorbers and appropriate allowance for physical phenomena that influence reactivity.

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