Editing Thermal-neutron reactor (section)

{{Short description|Nuclear reactor, uses moderated neutrons}}
{{Main|Nuclear reactor}}
A '''thermal-neutron reactor''' is a [[nuclear reactor]] that uses slow or [[thermal neutron]]s. ("Thermal" does not mean hot in an absolute sense, but means in [[thermal equilibrium]] with the medium it is interacting with, the reactor's fuel, moderator and structure, which is much lower energy than the [[fast neutron]]s initially produced by fission.) 

A [[fast-neutron reactor]], on the other hand, operates using high-energy neutrons that are not slowed by a moderator. These reactors can efficiently use a broader range of fuels, including plutonium and other heavy atoms, and have the capability to breed more fissile material, such as uranium-238 into plutonium-239, which is not possible in thermal reactor. In contrast to thermal-neutron reactors, [[Integral fast reactor|integral fast reactors]] (IFRs) operate using fast neutrons and are designed for increased fuel efficiency. These reactors are capable of recycling nuclear waste and breeding new fuel, which enhances sustainability. Additionally, IFRs incorporate passive safety features that allow them to safely shut down without external power or human intervention

Most [[nuclear power plant]] reactors are thermal reactors and use a [[neutron moderator]] to slow [[neutron]]s until they approach the average [[kinetic energy]] of the surrounding particles, that is, to reduce the speed of the neutrons to low-velocity, thermal neutrons. Neutrons are uncharged, this allows them to penetrate deep in the target and close to the nuclei, thus scattering neutrons by nuclear forces, some nuclides are scattered large.<ref name="Squires, G.L.">{{Cite book |last=Squires |first=G. L. |url=https://books.google.com/books?id=KUVD8KJt7_0C&dq=thermal-neutron+reactor&pg=PR9 |title=Introduction to the Theory of Thermal Neutron Scattering |date=2012-03-29 |publisher=Cambridge University Press |isbn=978-1-107-64406-9 |language=en}}</ref>

The [[nuclear cross section]] of [[uranium-235]] for slow thermal neutrons is about 1000 [[Barn (unit)|barns]], while for fast neutrons it is in the order of 1 barn.<ref name="Some Physics of Uranium">{{cite web|url=http://www.uic.com.au/uicphys.htm |title=Some Physics of Uranium |accessdate=2009-01-18 |url-status=dead |archiveurl=https://web.archive.org/web/20080303234940/http://www.uic.com.au/uicphys.htm |archivedate=March 3, 2008 }}</ref> Therefore, thermal neutrons are more likely to cause uranium-235 to [[nuclear fission]] than to be captured by [[uranium-238]]. If at least one neutron from the U-235 fission strikes another nucleus and causes it to fission, then the [[chain reaction]] will continue. If the reaction will sustain itself, it is said to be [[Critical reaction|critical]], and the mass of U-235 required to produce the critical condition is said to be a [[Critical mass (nuclear)|critical mass]].

'''Thermal reactors consist of the following''':

* [[Neutron moderator]] to slow down the [[neutron]]s. In [[light water reactor]]s and [[heavy water reactor]]s it doubles as the [[nuclear reactor coolant]].
* [[Nuclear fuel]], which is a [[fissile material]], usually [[uranium]].
* [[Reactor vessel]] that is a [[pressure vessel]] containing the [[coolant]] and [[reactor core]].
* [[Radiation shield]]ing to protect people and the environment from the harmful effects of [[ionizing radiation]].
* [[Containment building]]s which are designed to contain the escape of [[radiation]] in an emergency.
* Instrumentation to monitor and control the reactor's systems.