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This explains why most reactors fueled with 235 U need a moderator to sustain a chain reaction and why removing a moderator can shut down a reactor. The probability of further fission events is determined by the fission cross section, which is dependent upon the speed (energy) of the incident neutrons.
The boundaries of the valley of stability, that is, the upper limits of the valley walls, are the neutron drip line on the neutron-rich side, and the proton drip line on the proton-rich side. The nucleon drip lines are at the extremes of the neutron-proton ratio. At neutron–proton ratios beyond the drip lines, no nuclei can exist.
The test explosions codenamed Ruth and Ray used in the core uranium hydride. Ruth used the hydrogen isotope protium (1 H) and Ray used the hydrogen isotope deuterium (2 H or 2 D) as neutron moderators. The predicted yield was 1.5 to 3 kt TNT for Ruth and 0.5-1 kt TNT for Ray, however the tests produced only a yield of about 200 tons of TNT.
The mere fact that an assembly is supercritical does not guarantee that it contains any free neutrons at all. At least one neutron is required to "strike" a chain reaction, and if the spontaneous fission rate is sufficiently low it may take a long time (in 235 U reactors, as long as many minutes) before a chance neutron encounter starts a chain reaction even if the reactor is supercritical.
Schematic diagram of an RBMK Schematic side view of the layout of an RBMK reactor core The reactor hall and piping systems of the RBMK reactor. The reactor pit or vault is made of reinforced concrete and has dimensions 21.6m × 21.6m × 25.5m. It houses the vessel of the reactor, which is annular, made of an inner and outer cylindrical wall and ...
Diagram of a nuclear reactor using graphite as a moderator "Graphite reactor" directs here. For the graphite reactor at Oak Ridge National Laboratory, see X-10 Graphite Reactor. A graphite-moderated reactor is a nuclear reactor that uses carbon as a neutron moderator, which allows natural uranium to be used as nuclear fuel.
A thermal-neutron reactor is a nuclear reactor that uses slow or thermal neutrons.. ("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 neutrons initially produced by fission.)
A neutron moderator is a medium which reduces the velocity of fast neutrons, thereby turning them into thermal neutrons capable of sustaining a nuclear chain reaction involving uranium-235. A good neutron moderator is a material full of atoms with light nuclei which do not easily absorb neutrons. The neutrons strike the nuclei and bounce off.