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A unit of measurement equal to 1/12 the mass of a Carbon 12 atom (1.6605402 x 10–24 grams).
Atomic Mass Unit (AMU)
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Sub-atomic particle that makes up an atom, has a mass of 0.00055 AMU, a negative charge, and is located outside the nucleus in probability shells (orbits).
Electron
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Amount of kinetic energy (eV) gained by an electron when accelerated through an electric potential difference of 1 volt
Electron Volt (eV)
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A basic substance that cannot be broken down into any simpler substance after it is isolated from a compound, but can be combined with other elements to form compounds.
Element
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A nucleus of the same element (same number of protons) with a different number of neutrons.
Isotopes
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Sub-atomic particle that makes up an atom, has a mass of 1.00866 AMU, a neutral charge, and is located in the nucleus.
Neutron
-
Any particle that is part of the nucleus of an atom, neutrons and protons
Nucleon
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Any atom containing a unique combination of neutrons and protons in the nucleus.
Nuclide
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Sub-atomic particle that makes up an atom, has a mass of 1.00727 AMU, a positive charge, and is located in the nucleus.
Proton
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The energy equivalent of the mass defect (MeV). Represents the amount of energy that is released when an atom is formed from its component protons and neutrons. Also, represents the amount of energy that must be supplied to the atom to completely separate it into its individual protons and neutrons.
Binding Energy (BE)
-
Average energy required to remove a nucleon from the nucleus.
Binding Energy (BE) Per Nucleon
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The attractive or repulsive force that exist between two objects due to their electrical charge.
Electrostatic Force
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The splitting of an atoms nucleus resulting from an energy input (excitation energy) into the nucleus greater than the nuclear forces holding the nucleus together.
Fission
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The difference in mass between a nucleus and the sum of the masses of the individual protons and neutrons in the nucleus (AMU).
Mass Defect (Dm)
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The conversion factor equating mass to energy
Mass-Energy Equivalence
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The strong attractive force in a nucleus between to adjacent nucleons.
Nuclear Force
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The inherent ability of an atom to resist changing its atomic structure or energy level.
Nuclear Stability
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The process by which an unstable nucleus spontaneously transmutes from one form to another to reach a more stable state.
Radioactive Decay
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The unstable nucleus of an atom immediately following the absorption of a neutron.
Compound Nucleus
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The new nucleus present after the decay event.
Daughter Nuclide
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A process involving the decay of a daughter product of radioactive decay, which may result in transformation to another daughter product that decays, etc.
Decay Chain
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The probability per unit time that a decay event will occur within a radioactive sample
Decay Constant
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The rate at which the atoms of a sample of radioactive material disintegrates.
Decay Rate
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The interaction between a neutron and nucleus of an atom resulting in the neutron transforming some of its kinetic energy to the nucleus with all kinetic energy shared between the neutron and nucleus and total KE conserved.
Elastic Scattering
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Any condition that results in an atom being electrically charged or at an energy level above its ground state energy.
Excited State Energy
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Highly excited radionuclides that are the result of a fission event and generally initiate a decay chain with beta decay.
Fission Fragments
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Any electron that is not electrically bound to an atom’s nucleus.
Free Electron
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A type of electromagnetic radiation emitted from an unstable nucleus allowing the nucleus to give off energy and return to a stable ground state
Gamma Ray
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The normal energy level of an atom when it is electrically neutral and not influenced by any outside energy inputs.
Ground State Energy
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The time required for a radioactive sample to decay to one half of its original value.
Half-Life
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The interaction between a neutron and nucleus of an atom resulting in some of the kinetic energy being transferred from the neutron to the nucleus and causing excitation of the nucleus such that it returns to ground state by gamma emission. KE is not conserved.
Inelastic Scattering
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An atom or a group of atoms that has acquired a net electric charge by gaining or losing one or more electrons.
Ion
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Any process that causes an atom or group of atoms to have a net electric charge resulting from losing or gaining one or more electrons
Ionization
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The energy required to remove one or more electrons from an atom
Ionization Energy
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The interaction between a neutron and nucleus resulting in capture of the neutron with enough energy to cause the resulting excited nucleus to split into two fission fragments and the release of neutrons and radiation.
Neutron Induced Fission
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The original nucleus that decays
Parent Nuclide
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The interaction between a neutron and nucleus resulting in capture of the neutron and excitation of the nucleus such that it returns to ground state by gamma emission.
Radiative Capture
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The process by which an unstable nucleus spontaneously transmutes from one form to another to reach a more stable state.
Radioactive Decay
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Any fission event that occurs independent of neutron induced fission. Generally occurs in radioisotopes with atomic numbers of 92 and above.
Spontaneous Fission
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Any of the radionuclides with atomic numbers greater than 92.
Transuranic Element
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A bundle of energy (photon) emitted from the electron shell of an excited atom.
X-Ray
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The number of atoms of a given isotope in a unit volume. Atomic density uses the symbol “N” as a designation, and the units are atoms per cubic centimeter.
Atomic Density
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Unit of measurement, where 1 barn is equal to 1 ´ 10‑24 square centimeters
Barn
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The minimum amount of energy required for fission to occur in a specific fuel type.
Critical Energy (Ec)
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A neutron born more than 1 ´ 10‑14 seconds after a fission event.
Delayed Neutron
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The delayed energy released by decay of the fission fragments after reactor shutdown.
Decay
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A neutron that has a kinetic energy greater than 0.1 MeV.
Fast Neutron
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A fuel type that will fission due to the binding energy of an incident neutron.
Fissile Material
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A neutron reaction in which an incident neutron is absorbed by a target nucleus, resulting in the splitting of the target nucleus into two new atoms, some neutrons, and gamma rays.
Fission
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A neutron emitted as a direct result of the fission process.
Fission Neutron
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Any particle created as the result of a fission event.
Fission Product
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A fuel type that requires kinetic energy in addition to binding energy of an incident neutron for fission to occur.
Fissionable Material
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A neutron that has a kinetic energy between 0.1 MeV and 1 eV
Intermediate Neutron
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A measure of the probability that a given interaction will occur between a single target nucleus and an incident neutron. The effective area presented by the target nucleus to the incident neutron, for a particular reaction.
Macroscopic Cross Section
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The average distance a neutron travels before an interaction occurs.
Mean Free Path
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The probability that a given interaction will occur between a target nucleus and neutron (barns or cm2).
Microscopic Cross Section
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A neutron that is emitted within 10-14 seconds of a fission event and is a direct result of the fission process (fission neutron).
Prompt Neutron
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A neutron that has a kinetic energy less than 1 eV.
Slow Neutron
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A neutron that is produced independently of neutron induced fission.
Source Neutron
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Any fission that results in the production of three fission fragments.
Ternary Fission
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A neutron that is in thermal equilibrium with its surroundings.
Thermal Neutron
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The condition of the reactor where the number of neutrons produced by fission in one generation equals the number of neutrons produced by fission in the previous generation (keff = 1) (r = 0).
Critical
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The factor by which the number of neutrons produced by fission in one generation must be multiplied to determine the number of neutrons produced by fission in the next generation.
Effective Multiplication Factor (keff)
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The ratio of fast neutrons produced from all fission events divided by fast neutrons produced by thermal fission events.
Fast Fission Factor (e)
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The ratio of the number of fast neutrons that start to slow down divided by the number of fast neutrons produced from all fissions.
Fast Non-Leakage Probability
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The time from the birth of one generation of neutrons to the time of the birth of the next generation of neutrons.
Neutron Generation Time
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The fractional change in fission neutron population per generation, or the measure of the departure of a reactor from criticality
Reactivity
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The ratio of fast neutrons produced by thermal fission events divided by the number of thermal neutrons absorbed in the fuel.
Reproduction Factor
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The ratio of fast neutrons that become thermal divided by the number of fast neutrons that start to slow down.
Resonance Escape Probability
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Used to describe the processes that occur during the neutron life cycle.
Six Factor Formula
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The condition in which the number of neutrons produced by fission in one generation is less than the number of neutrons produced by fission in the previous generation (keff < 1) (negative r).
Subcritical
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The condition in which the number of neutrons produced by fission in one generation is greater than the number of neutrons produced by fission in the previous generation (keff > 1) (positive r).
Supercritical
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The ratio of the number of thermal neutrons absorbed in the core divided by the number of fast neutrons that become thermal.
Thermal Non-Leakage Factor
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The ratio of the number of thermal neutrons absorbed in fuel divided by the number of thermal neutrons absorbed in the core.
Thermal Utilization Factor
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The weighted average of the decay constants for the six groups of delayed neutron precursors in the reactor core (sec–1).
Average Delayed Neutron Precursor Decay Constant
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The weighted average of the effective delayed neutron fraction for all fissile nuclides in the reactor core. equals the number of fissions caused by delayed neutrons divided by the total number of fissions caused by fission neutrons.
Average Effective Delayed Neutron Fraction
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The average time between the absorption of a neutron which causes fission and the absorption of resultant neutrons
Average Neutron Generation Time
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A reactivity unit related to a dollar of reactivity, where one cent is one-hundredth of a dollar
Cent
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The weighted average of the delayed neutron fractions for all fissile/fissionable nuclides in the reactor core
Core Average Delayed Neutron Fraction
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A neutron born approximately 12.7 seconds after a fission event
Delayed Neutron
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The fraction of neutrons born delayed from fission of a particular nuclide. b equals the number of neutrons born delayed divided by the total number of neutrons born from fission of a particular nuclide.
Delayed Neutron Fraction
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The total time from the fission event to absorption of a delayed neutron born from a delayed neutron precursor resulting from that fission event. » 12.7 seconds
Delayed Neutron Lifetime
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The decay constant for a delayed neutron precursor. It is the probability that a nucleus will decay per unit time (sec–1).
Delayed Neutron Precursor Decay Constant
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A unit of reactivity where one dollar of reactivity is equivalent to the effective delayed neutron fraction . If the reactivity of the core is one dollar, the reactor is prompt critical
Dollar ($)
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The time required for a reactor to double in power. DT is used to estimate reactor period (sec).
Doubling Time (DT)
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The fraction of neutron induced fissions caused by delayed neutrons of a particular nuclide
Effective Delayed Neutron Fraction
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The percentage of fissions that occur in the reactor for each particular fuel type present
Fission Fraction
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The percentage of fissions that occur in the reactor for each particular fuel type present
Fission Yield
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The average time required for one-half of the atoms of a material to decay
Half-Life (T1/2)
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Represents how long, on the average, a delayed neutron precursor will exist before decaying.
Mean Life
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The condition of the reactor reaching criticality on prompt neutrons alone. It will occur when positive reactivity added
is equal to, or greater than, the average effective delayed neutron fraction
Prompt Critical
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The initial rapid decrease in neutron population following a step insertion of negative reactivity
Prompt Drop
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The initial rapid increase in neutron population following a step insertion of positive reactivity
Prompt Jump
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The total time from the fission event to absorption of a prompt neutron born from that fission event. » 1 ´ 10–4 sec
Prompt Neutron Lifetime
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The time, in seconds, required to change reactor power by a factor of e (2.718).
Reactor Period
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The time (in minutes) required to change reactor power by a factor of 10. Expressed as DPM (decades per minute). It is a measure of the rate of change of reactor power in DPM
Startup Rate (SUR)
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The widening and flattening effect on resonance capture probability peaks for epithermal neutrons due to increased kinetic energy of target atoms resulting from increased fuel temperature.
Doppler Broadening
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The reactivity coefficient that relates the change in reactivity due to a change in fuel temperature.
Doppler Coefficient or Fuel Temperature Coefficient
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The reactivity coefficient that relates the change in reactivity due to a change moderator temperature
Moderator Temperature Coefficient
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Discrete excitation energy levels exist within a nucleus
Resonance Energy
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Reactivity coefficient that relates the change in reactivity due to a change in void fraction
Void Coefficient
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The temperature decrease per unit time usually measured at the vessel skin, steam dome, and recirculation loop
Cooldown Rate
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The reactor sustains a chain reaction with a stable neutron count rate and an infinite reactor period
Criticality
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The heat generated in the core from the decay of fission products.
Decay Heat
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The negative reactivity contributed to the core by the Doppler coefficient when the core void fraction is decreased using recirculation flow.
Doppler Defect
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An estimate, made by the reactor engineers that determines on what rod pattern what rod, and what rod position the reactor is expected to go critical
Estimated Critical Position
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The temperature rise per unit time usually measured at the vessel skin, steam dome, and recirculation loop
Heatup Rate
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The point during a reactor startup where heat production from fission exceeds ambient heat losses. A further increase
in power will raise the temperature of fuel and moderator
Point of Adding Heat
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A plot using the inverse count ratio (ICR) following reactivity change events to obtain a conservative estimate of critical rod position. May also be used during fuel loading to monitor for inadvertent criticality. This is sometimes also referred to as an inverse count ratio plot or an inverse count rate ratio plot.
1/M Plot
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The instantaneous amount of reactivity by which a reactor is sub-critical or would be sub-critical from its present condition assuming all control rods are fully inserted except for the single rod with the highest integral worth and equilibrium xenon removed
Shutdown Margin
-
______ scattering is the type of scattering reaction where kinetic energy raises the internal energy of the target nucleus.
Inelastic
-
Any process that causes an atom or group of atoms to have a net electric charge resulting from losing or gaining one or more electrons can be referred to as:
Ionization
-
Identify the 4 basic types of Radiation
-
The difference in mass between a nucleus and the sum of the masses of individual protons and neutrons in the nucleus is called the _______
Mass Defect
-
The splitting of an atom's nucleus resulting from an energy input (excitation energy) into the nucleus greater than the nuclear force holding the nucleus together is called ______
fission
-
What is the attractive or repulsive force that exists between two objects due to their electrical charge?
Electrostatic Force
-
At time t = 0, a radioactive sample contains 1x1010 atoms. After 31 days, the sample contains 3.6x104 atoms. Determine the half life of the sample
t1/2=1.7 days
-
When will a reactor respond to a set amount of added reactivity?
End of Life EOL
-
The departure from criticality can be used to describe what?
reactivity
-
What is the Effective Delayed Neutron Fraction Beff?
The fraction of neutron induced fission caused by delayed neutrons of a particular nuclide
-
When a reactor has reached an equilibrium in the number of neutrons produced from one generation to another (the reactor is critical keff=1), what is the reactivity?
0
-
A neutron that has kinetic energy less than 1 eV is know as a ______
slow neutron
-
A neutron that has a kinetic energy greater than 0.1 MeV is known as a _______
Fast neutron
-
A fuel type that requires kinetic energy in addition to binding energy of an incident neutron for fission to occur is known as a _____ material
fissionable
-
What are the two nuclides present in large amounts in the fuel of some reactors with large resonant peaks that dominate the Doppler Effect?
U238 Pu240
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The time in minutes required to change the reactor power by a factor of 10, expressed in DPM, which is a measure of the rate of change of reactor power is known as the _____
Start Up Rate SUR
-
Which electrons have the higher energy, the inner or outer electrons
Outer
-
The energy equivalent of the mass defect is also known as the ______
Binding Energy
-
The name given to the strong attractive force in the nucleus between two adjacent nucleons is known as the ____
Strong Nuclear Force
-
The average distance that a neutron travels before an interaction occurs is known as the ____
Mean Free Path
-
Given AZX define A, X, and Z
- A = Nucleons and the Atomic Mass Number
- X = The Atomic symbol
- Z = The number of protons and Atomic Number
-
Given an electrically neutral isotope 92U235, how many n, p+ and e- are there?
- protons = 92
- electrons = 92
- neutrons = 143
-
Any fission event that occurs independent of neutron induced fission is known as _______.
Generally, this occurs in radioisotopes with very large atomic numbers.
spontaneous fission
-
Any particle that is part of the nucleus (neutrons and protons) is known as a ________
nucleon
-
Using the Chart of Nuclides, calculate the mass defect of Nickel-58
- mass defect = (Z*hydrogen)+(A-Z)(neutron)-Matom
- mass defect = (28*1.0078)+(58-28)(1.0087)-57.935348
- mass defect = 28.2184 + 30.261 - 57.935348
- mass defect = 0.544052 AMU
-
The average energy required to remove a nucleon from the nucleus is known as the ____
Binding Energy per Nucleon
-
Define a thermal neutron
A neutron in thermal equilibrium with its surroundings
-
The probability of an incident neutron interacting with a target nucleus per unit length of travel of the incident neutron (∑) and in units or cm-1 is known as the __________, while the measure of the probability that a given interaction will occur between a single target nucleus and an incident neutron is known as the _______ and is represented as (σ). This is defined as the effective area presented by the target nucleus to the incident neutron for a particular reaction (units of barns = 1 x 10-24cm2)
Macroscopic cross section, microscopic cross section
-
Given a sample of radioactive element containing 4.8x1024 atoms and a half-life of 1 day, how many atoms remain after 5 days?
-
Using your chart of nuclides, name the element Xe and determine the number of stable isotopes.
Xe is Xenon and has 9 stable isotopes
-
The decay heat produced by a reactor shutdown from full power is initially what % of thermal rated reactor power?
~ 6% to 7%
-
Any fission that results in the production of 3 fission fragments is known as a ______. This is not as common as a regular fission where the nucleus splits into two masses of _____ sizes.
Ternary fission, unequal
-
The process where a high energy gamma (>1.02MeV) interacts with the electric field and is converted to mass (electrons and positrons) is known as ______. Mid energy reactions with a photon, where some energy is transferred to the electron, the electron is knocked out and the gamma is scattered is known as ______. The low energy photon reaction, where the total energy of the γ is absorbed by the electron and the electron is ejected is known as ______
pair production, compton scattering, photoelectric effect
-
What is the cutoff for the time in which a prompt neutron is produced? What is the average time for the production of a delayed neutron?
- Prompt < 1x10-14 seconds
- Delayed 12.7 second
-
In the 6 factor formula, the factor f represents which factor. expressed as
f=thermal neutrons absorbed in fuel / thermal neutrons absorbed in core
Thermal Utilization Factor
-
When a reactor has a keff=1 the reactor is ______.
critical
-
The ratio of fast neutrons that become thermal, divided by the number of fast neutrons that start to slow down is known as the _______, and is expressed as
p=fast neutrons that become thermal/fast neutrons that start to slow down
Resonance escape probability
-
A control rod withdrawal results in the keff of a reactor changing from 0.975 to 0.980, calculate how much reactivity was added to the core, in pcm (percent milli)
- ρ = keff - 1 / keff
- 1 pcm = 1x10-5 Δk/k
- ρ = 0.975 - 1 / 0.975 = -0.025641026
- ρ = 0.980 -1 / 0.980 = -0.020408163
- Δρ = 0.005232863
- 523.2863 pcm
-
What is the widening and flattening effect on resonance capture probability peaks for epithermal neutrons due to increased kinetic energy of target atoms resulting from increased fuel temperature?
Doppler broadening
-
What is the name given to the instantaneous amount of reactivity by which a reactor is sub-critical or would be from its present condition assuming all control rods are fully inserted except for the single rod with the highest integral worth and equilibrium Xe removed?
Shutdown Margin
-
What is the condition where the reactor period is reduced to the prompt neutron component? It is associated with rapid increase in neutron power.
Prompt Critical
-
What type of neutron is more likely to cause fast fission in U238?
Prompt Neutrons
-
What are the 3 factors that effect decay heat after a reactor is shutdown?
- Pre-shutdown power level
- How long the reactor has been operated
- Time since last shutdown
-
The condition in which the number of neutrons produced by fission in one generation is greater than the number of neutrons produced by fission in the previous generation is known as ______.
Supercritical
-
The factor by which the number of neutrons produced by fission in one generation must be multiplied by to determine the number of neutrons produced by fission in the next generation is know as the _______. In order to have a critical reactor this value must be _______, meaning that the reactor is able to sustain a chain reaction.
Effective Multiplication Factor keff , 1
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