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Nuclear reactor that uses moderated neutrons
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
Thermal-neutron_reactor
Kinetic energy of an unbound neutron
nuclear reactor because most fissile fuel has a higher reaction rate with thermal neutrons. Fast neutrons can be rapidly changed into thermal neutrons via
Neutron_temperature
Nuclear reactor where fast neutrons maintain a fission chain reaction
fast neutrons (carrying energies above 1 MeV, on average), as opposed to slow thermal neutrons used in thermal-neutron reactors. Such a fast reactor needs
Fast-neutron_reactor
Type of nuclear reactor that uses normal water
light-water reactor (LWR) is a type of thermal-neutron reactor that uses normal water, as opposed to heavy water, as both its coolant and neutron moderator;
Light-water_reactor
Type of nuclear fission reactor
various reactor types, including generation IV, thermal-neutron reactors, fast-neutron reactors, molten salt reactor, and gas-cooled reactor models. Many
Small_modular_reactor
Substance that slows down particles with no electric charge
engineering, a neutron moderator is a medium that reduces the speed of fast neutrons, ideally without capturing any, leaving them as thermal neutrons with only
Neutron_moderator
Device for controlled nuclear reactions
single neutrons and split, releasing energy and multiple neutrons, which can induce further fission. Reactors stabilize this, regulating neutron absorbers
Nuclear_reactor
Field of physics dealing with nuclear reactors
nuclear reactor, the neutron population at any instant is a function of the rate of neutron production (due to fission processes) and the rate of neutron losses
Nuclear_reactor_physics
Nuclear reactor where water boils in core
of electricity-generating nuclear reactor after the pressurized water reactor (PWR). BWRs are thermal neutron reactors, where water is thus used both as
Boiling_water_reactor
Type of nuclear reactor cooled by molten sodium
sodium-cooled fast reactor (SFR) is a fast neutron reactor cooled by liquid sodium. It offers several advantages over light-water reactors (LWRs), including
Sodium-cooled_fast_reactor
Class of nuclear reactor used for education and research
thermal neutrons. Like most reactors, TRIGA is a thermal-neutron reactor in which fast neutrons produced by fission are slowed by a neutron moderator
TRIGA
Neutron source used to start nuclear reactors
A startup neutron source is a neutron source used for stable and reliable initiation of nuclear chain reaction in nuclear reactors, when they are loaded
Startup_neutron_source
Nuclear research reactor in Oak Ridge, Tennessee
highest steady-state neutron fluxes of any research reactor in the world. The thermal and cold neutrons produced by HFIR are used to study physics, chemistry
High_Flux_Isotope_Reactor
Isotope of uranium
it cannot sustain a chain reaction in a thermal-neutron reactor. However, it is fissionable by fast neutrons, and is fertile, meaning it can be transmuted
Uranium-238
Subatomic particle with no charge
R-process S-process Thermal-neutron reactor Neutron generator Neutron source Neutron bomb Neutron diffraction Neutron flux Neutron imaging Neutron transport Cosmogenic
Neutron
Substance that can absorb large quantities of neutrons in a reactor core
such as nuclear reactors, a neutron poison (also called a neutron absorber or a nuclear poison) is a substance with a large neutron absorption cross-section
Neutron_poison
Measure of neutron interaction likelihood
neutron resonances is a very important phenomenon and improves nuclear reactor stability. The prompt temperature coefficient of most thermal reactors
Neutron_cross_section
as time goes on. Generation II thermal-neutron reactors (today's most numerous nuclear power stations) can reuse reactor-grade plutonium only to a limited
Reactor-grade_plutonium
Material capable of sustaining a nuclear fission chain reaction
either slow neutrons (i.e., a thermal system) or fast neutrons. Fissile material can be used to fuel thermal-neutron reactors, fast-neutron reactors and nuclear
Fissile_material
Physical phenomenon
thermal neutrons, which have kinetic energies below 1 eV (T < 500K). Thermal neutrons are used to maintain a nuclear chain reaction in a nuclear reactor, and
Neutron_scattering
Part of a reactor containing the fuel
moderate the neutron reactions. There are also graphite moderated reactors in use. One type uses solid nuclear graphite for the neutron moderator and
Nuclear_reactor_core
Fast-neutron nuclear reactor cooled by molten lead
these reactors operate with fast neutrons. The concept is generally similar to sodium-cooled fast reactors, and most liquid-metal fast reactors have used
Lead-cooled_fast_reactor
Thermal-neutron research reactor at Argonne National Laboratory (1954–1979)
CP-5 was a thermal-neutron reactor using enriched uranium as fuel and heavy water as coolant and as a neutron moderator. It produced neutrons for use in
Chicago_Pile-5
Material with the ability to reflect neutrons; used to control fission reactions
of a core. Neutron reflectors serve as a thermal and radiation shield of a reactor core. Tamper (nuclear weapon) Neutron scattering Neutron supermirror
Neutron_reflector
Type of nuclear reactor
water reactors and pressurized heavy‑water reactors). In a PWR, water is used both as a neutron moderator and as coolant fluid for the reactor core. In
Pressurized_water_reactor
Nuclear reactor that killed 3 in 1961
central control rod, a component designed to absorb neutrons in the reactor's core. This caused the reactor to go from shut down to prompt critical. Within
SL-1
Device that achieves nuclear fission without triggering a chain reaction
therefore require a fast reactor for being fissioned. While they can be transmuted into fissile material with thermal neutrons, some nuclides need as many
Subcritical_reactor
When one nuclear reaction causes more
For "thermal" (slow-neutron) fission reactors, the typical prompt neutron lifetime is on the order of 10−4 seconds, and for fast fission reactors, the
Nuclear_chain_reaction
Nuclear reactor design
integral fast reactor (IFR), originally the advanced liquid-metal reactor (ALMR), is a design for a nuclear reactor using fast neutrons and no neutron moderator
Integral_fast_reactor
Family of nuclear research reactors
but provide neutron fluxes higher than available from a small particle accelerator or other radioactive sources. The SLOWPOKE-2 reactors (most numerous
SLOWPOKE_reactor
Nuclear spacecraft propulsion technology
Although more than ten reactors of varying power output have been built and tested, as of 2025[update], no nuclear thermal rocket has flown. Whereas
Nuclear_thermal_rocket
Ionizing radiation that presents as free neutrons
still a common neutron source. The neutrons in nuclear reactors are generally categorized as slow (thermal) neutrons or fast neutrons depending on their
Neutron_radiation
Type of Soviet nuclear power reactor
addition, RELAP5-3D models of RBMK-1500 reactors were developed for use in integrated thermal-hydraulics-neutronics calculations for the analysis of specific
RBMK
Delayed emission of neutrons after nuclear fission
like the thermal dilatation of the core, or the increased resonance absorptions of neutrons, that usually tend to decrease the reactor's reactivity
Delayed_neutron
Component of nuclear fission or fusion reactors
scenarios, neutron radiation is converted into thermal energy in the blanket, leading it to require its own cooling system. Breeder reactors come in two
Breeding_blanket
Nuclear reactor generating more fissile material than it consumes
uranium-233 from thorium, if desired. Thermal breeder reactors which use 'thermal-spectrum' or 'slow' (i.e. moderated) neutrons to breed fissile uranium-233 from
Breeder_reactor
Immediate emission of neutrons after nuclear fission
like the thermal dilatation of the core, or the increased resonance absorptions of neutrons, that usually tend to decrease the reactor's reactivity
Prompt_neutron
Type of nuclear reactor that uses molten material as fuel
uranium-233 in the thermal neutron spectrum. The LFTR concept was first investigated at the Oak Ridge National Laboratory Molten-Salt Reactor Experiment in
Liquid fluoride thorium reactor
Liquid_fluoride_thorium_reactor
Nuclear reactor where the coolant is liquid metal
metal coolant has been applied to both thermal- and fast-neutron reactors. To date, most fast neutron reactors have been liquid metal cooled and so are
Liquid_metal_cooled_reactor
Uranium processed to increase the percentage of uranium-235
thus unavoidable in any thermal neutron reactor with 235 U fuel. HEU reprocessed from nuclear weapons material production reactors (with an 235U assay of
Enriched_uranium
Research nuclear reactor in Australia
Institute's park of neutron scattering instruments. Neutron guide The instrument is located on the TG1 thermal neutron guide of the OPAL reactor. The distance
Open-pool Australian lightwater reactor
Open-pool_Australian_lightwater_reactor
Problem in nuclear reactor start-up
weak neutron absorber. It builds up in the reactor at a rate proportional to the rate of fission, which is proportional to the reactor thermal power
Iodine_pit
Study of motions and interactions of neutrons
transfer of neutrons and is commonly used to determine the behavior of nuclear reactor cores and experimental or industrial neutron beams. Neutron transport
Neutron_transport
Atomic nuclear process
as in a nuclear reactor, a single neutron is captured by a nucleus. For example, when natural gold (197Au) is irradiated by neutrons (n), the isotope
Neutron_capture
primarily seen in nuclear reactors, where the release of high-energy neutrons causes the long-term degradation of the reactor materials. The embrittlement
Neutron_embrittlement
Type of nuclear reactor cooled by a gas
gas-cooled fast reactor (GFR) system is a nuclear reactor design in development. Classed as a Generation IV reactor, it features a fast-neutron spectrum and
Gas-cooled_fast_reactor
Naturally occurring uranium self-sustaining nuclear chain reactions
it being both consumed by neutron capture and produced from 235 U by fast-neutron-induced (n,2n) reactions in nuclear reactors. In Oklo, any possible deviation
Natural nuclear fission reactor
Natural_nuclear_fission_reactor
Electricity generation by nuclear fusion
energetic neutron. Fusion fuel is extremely energy-dense, but tritium is scarce on Earth and decays with a half-life of about 12.3 years. Future reactors plan
Fusion_power
Nuclear reactor cooled or moderated by an organic liquid
An Organic nuclear reactor or Organic-cooled reactor (OCR) is a class of nuclear reactor in which the primary coolant or neutron moderator is an organic
Organic_nuclear_reactor
Type of British nuclear reactor
These are the second generation of British gas-cooled reactors, using graphite as the neutron moderator and carbon dioxide as coolant. They have been
Advanced_gas-cooled_reactor
Measure of the efficiency of a nuclear fission reaction
order to maintain a chain reaction in a nuclear reactor, a neutron moderator is used to slow the neutrons down. This moderator is often used as the coolant
Neutron_economy
Type of nuclear reactor cooled by molten salt
They can be fast or thermal or epithermal. Thermal reactors typically employ a moderator (usually graphite) to slow the neutrons down and moderate temperature
Molten-salt_reactor
Australia's first nuclear reactor
power reactors their entire expected lifetime neutron exposure in a relatively short period. HIFAR was used for research, particularly neutron diffraction
High_Flux_Australian_Reactor
Type of very-high-temperature reactor
with the graphite serving as a neutron moderator. Pebble-bed reactors are typically high temperature gas-cooled reactors (HTGRs), and are capable of being
Pebble-bed_reactor
Idaho National Laboratory research neutron source
water reactor (LWR), using water as both coolant and moderator. The core is surrounded by a beryllium neutron reflector to concentrate neutrons on experiments
Advanced_Test_Reactor
Pair of research nuclear reactors in Nilore, Islamabad, Pakistan
The Pakistan Atomic Research Reactor or (PARR) are two nuclear research reactors and two other experimental neutron sources located in the PINSTECH Laboratory
Pakistan Atomic Research Reactor
Pakistan_Atomic_Research_Reactor
Nuclear research reactor
the only reactor of Polish design. Research done with Maria includes the production of radioisotopes, research using neutron beams, neutron therapy, and
Maria_reactor
Decommissioned nuclear reactor in Tennessee, US
The centerpiece of this was the X-10 Graphite Reactor. It was air-cooled, used nuclear graphite as a neutron moderator, and pure natural uranium in metal
X-10_Graphite_Reactor
Power generated from nuclear reactions
breeder reactors. As opposed to light water thermal-neutron reactors, which use uranium-235 (0.7% of all natural uranium), fast-neutron breeder reactors use
Nuclear_power
Material in core during nuclear meltdown
re-criticality (resumption of neutron-induced fission) in parts of the corium is a theoretical but remote possibility with commercial reactor fuel, due to low enrichment
Corium_(nuclear_reactor)
spectrometer. PUMA – a thermal neutron triple-axis spectrometer with multianalyser-detector option. TRISP – a thermal neutron triple-axis spin echo spectrometer
Neutron triple-axis spectrometry
Neutron_triple-axis_spectrometry
Device that emits neutrons
made by irradiating uranium or a transuranic element in a nuclear reactor, where neutrons are absorbed in the starting material and its subsequent reaction
Neutron_source
Type of nuclear reactor, CO2 or He cooled
A gas-cooled reactor (GCR) is a nuclear reactor that uses graphite as a neutron moderator and a gas (carbon dioxide or helium in extant designs) as coolant
Gas-cooled_reactor
Design project of a nuclear reactor coupled to a proton accelerator
increase its versatility the reactor is also designed to operate in critical mode with fast neutron and thermal neutron zones. The accelerator will accelerate
MYRRHA
Early nuclear reactor that provided essential research for future reactors
and a fuel management canal were enclosed in a reactor building The neutron flux was about 2e14 thermal (in the reflector) and 1e14 fast (E > 1 MeV). About
Materials_Testing_Reactor
Nuclear reactor design
pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water (deuterium oxide D2O) as its coolant and neutron moderator. PHWRs frequently
Pressurized heavy-water reactor
Pressurized_heavy-water_reactor
Nonsurgical treatment for locally invasive malignant tumors
there transitioned from a reactor neutron source to accelerators that would produce high-energy neutrons that become thermalized as they penetrate tissue
Neutron capture therapy of cancer
Neutron_capture_therapy_of_cancer
Nuclear fuel cycle
thorium cycle, fuel is formed when 232 Th captures a neutron (whether in a fast reactor or thermal reactor) to become 233 Th. This normally emits an electron
Thorium_fuel_cycle
Formula used to calculate nuclear chain reaction growth rate
probability that a fast neutron absorption in fuel causes fission. P T A F {\displaystyle P_{TAF}} is the probability that a thermal neutron absorption in fuel
Six_factor_formula
New nuclear reactor technologies under development
protection. A thermal reactor is a nuclear reactor that uses slow or thermal neutrons. A neutron moderator is used to slow the neutrons emitted by fission
Generation_IV_reactor
Lead-cooled reactor family designed in Russia
nuclear reactor design, the fuel is only able to reach criticality when the neutrons produced in the fission reactions are slowed down using a "neutron moderator"
BREST_(reactor)
World's first continuous fast-neutron reactor
first continuous fast-neutron reactor, also known as the Los Alamos fast plutonium reactor. It was an experimental-scale reactor. The maximum output was
Clementine_(nuclear_reactor)
Nuclear reactor, Oak Ridge 1965–1969
reactor simulating the neutronic "kernel" of a type of inherently safer epithermal thorium breeder reactor called the liquid fluoride thorium reactor
Molten-Salt Reactor Experiment
Molten-Salt_Reactor_Experiment
Chemical element with atomic number 96 (Cm)
rate of 247Cm in thermal neutron reactors is low because it is prone to fission due to thermal neutrons. Synthesis of 250Cm by neutron capture is unlikely
Curium
Formula used to calculate nuclear chain reaction growth rate
probability that a fast neutron absorption in fuel causes fission. P T A F {\displaystyle P_{TAF}} is the probability that a thermal neutron absorption in fuel
Four_factor_formula
Nuclear power plant design
salt blend also acts as the primary coolant for the reactor. The IMSR is a thermal-neutron reactor moderated by vertical graphite elements. The molten
Integral_Molten_Salt_Reactor
Concept nuclear reactor whose water operates at supercritical pressure
water flow, and the feedback can make the reactor power harder to predict and control. Neutronic and thermal hydraulic coupled calculation is needed to
Supercritical_water_reactor
Method used for determining the concentrations of elements in many materials
placed in the reactor; if epithermal neutrons are required for the irradiation then cadmium can be used to filter out the thermal neutrons. A relatively
Neutron_activation_analysis
Fission from a high energy neutron
high-energy neutron, called a fast neutron, and splits. Most fissionable materials need thermal neutrons, which move more slowly. Fast neutron reactors use fast
Fast_fission
Breeder reactor in Idaho, US
theory that suggested that a breeder reactor should be possible. The concept suggested using a reactor's neutron radiation to convert or "breed" a blanket
Experimental Breeder Reactor I
Experimental_Breeder_Reactor_I
Type of nuclear reactor design
production. These neutrons activate the thorium, enabling fission without needing to make the reactor critical. One benefit of such reactors is the relatively
Accelerator-driven subcritical reactor
Accelerator-driven_subcritical_reactor
Coolant in a nuclear reactor
reactor. Almost all currently operating nuclear power plants are light water reactors using ordinary water under high pressure as coolant and neutron
Nuclear_reactor_coolant
Naval nuclear reactor
are pressurized water reactors fueled by highly enriched uranium-235. Light water is used as both neutron-moderator and reactor coolant. Hafnium Control
A2W_reactor
Type of nuclear power reactor
neutron reactor, thereby combining the established and proven technology of light water reactors with the desired features of fast neutron reactors.
Reduced moderation water reactor
Reduced_moderation_water_reactor
Decommissioned nuclear reactor at the University of Michigan
face Thermal Neutron Flux: 2.0×1012 n/cm2/s Fast Neutron Flux': 2.0×1010 n/cm2/s Thermal Column: Inoperative (The reactor was built with a thermal column
Ford_Nuclear_Reactor
Isotope of uranium
others reactor types require uranium enriched in U-235. Uranium-235 has a half-life of 704 million years. Its fission cross section for slow thermal neutrons
Uranium-235
Induction of radioactivity by neutron radiation
chromium-51 will form by neutron activation in chrome steel (which contains 50Cr) that is exposed to a typical reactor neutron flux. Carbon-14, most frequently
Neutron_activation
Nuclear fission reactor
pressurized water reactor (PWR) uses 20-45% enriched uranium-235 fuel to produce 190 MW of thermal power. Developed during the 1970s, these reactors were designed
OK-650_reactor
Energy Commission. The reactor is a commercial version of the Chinese Miniature Neutron Source Reactor (MNSR) design. The reactor had its first criticality
Ghana_Research_Reactor-1
Safety systems of boiling water reactors
pressurized water reactor, a boiling water reactor has a negative void coefficient, that is, the neutron (and the thermal) output of the reactor decreases as
Boiling water reactor safety systems
Boiling_water_reactor_safety_systems
Research reactor planned for operation by 2028 in France
that results in large numbers of thermal neutrons being available around the outside of the reactor core. The neutrons from this source can be used in
Jules_Horowitz_Reactor
Canadian heavy water nuclear reactor design
reactions release naturally. Most reactors use some form of neutron moderator to lower the energy of the neutrons, or "thermalize" them, which makes the reaction
CANDU_reactor
Research nuclear reactor in Portland, Oregon, US
hands-on education. The Reed Research Reactor is intended to produce thermal neutrons. It is used primarily for neutron activation to produce radioisotopes
Reed_Research_Reactor
Nuclear research reactor in Moscow, Russia
equipment. The weight of graphite is 400 tons, uranium is 50 tons. Thermal power of the reactor is from 100 W to 1 MW. Air cooling, if necessary, was provided
F-1_(nuclear_reactor)
First industrial-scale nuclear reactor
1944, the D Reactor in December 1944 and the F Reactor in February 1945. The initial operation was halted by a problem identified as neutron absorption
B_Reactor
Algerian nuclear reactor
research reactor, also known as the Aïn Oussara nuclear reactor, is a nuclear research reactor in Algeria. The reactor can produce 15 megawatts-thermal and
Es-Salam_nuclear_reactor
Probability that a high-energy neutron is not captured
heterogeneous geometry of a reactor, because fast neutrons resulting from fission can leave the fuel and slow to thermal energies in a moderator, skipping
Resonance_escape_probability
Type of nuclear fuel
actinides than thermal reactors. Because thermal reactors use slow or moderated neutrons, the actinides that are not fissionable with thermal neutrons tend to
MOX_fuel
Nuclear fission reactor family
are pressurized water reactors (PWR) fueled by either 30–40% or 90% enriched uranium-235 fuel to produce 135 to 171 MW of thermal power. The KLT-40S variant
KLT-40_reactor
Nuclear reactor concept
creates a Maxwellian thermal neutron flux profile, the neutron energy profile from delayed neutrons varies widely. In a conventional reactor, he theorizes,
Clean and Environmentally Safe Advanced Reactor
Clean_and_Environmentally_Safe_Advanced_Reactor
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THERMAL NEUTRON-REACTOR
THERMAL NEUTRON-REACTOR
THERMAL NEUTRON-REACTOR
THERMAL NEUTRON-REACTOR
THERMAL NEUTRON-REACTOR
THERMAL NEUTRON-REACTOR
THERMAL NEUTRON-REACTOR
THERMAL NEUTRON-REACTOR
THERMAL NEUTRON-REACTOR
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