Core Power Utilization of Neutrons in Chain Reactors
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Core Power Utilization of Neutrons in Chain Reactors

Perspective - (2022) Volume 6, Issue 3

R. Edward*
*Correspondence: R. Edward, Department of Economic, University of Oulu, Oolu, Finland, Email:

Author info »


Depending on the power level, a nuclear reactor core is normally made up of a few hundred components. The moderator helps to slow down the neutrons produced by fission in order to maintain the chain reaction. When some of the neutrons hit other atoms, they fission as well and release further neutrons. It’s known as a chain reaction. Control rods are commonly used for this, and they are made of neutron-absorbing materials like silver and boron.

In general, the reactor core control includes the axial power difference (or power distribution) control of the core as well as power control (or coolant temperature) control. The core power control regulates the core power, and the core load controlling regulates both the core power and axial power difference at the same time.

A nuclear fission chain reaction produces heat in the reactor, which is sent to a primary coolant circuit and subsequently a secondary coolant circuit. The steam produced when the secondary coolant circuit is heated to boiling point and sent to a steam turbine causes the turbine rotor to rotate. Last but not least, a generator rotor that is mechanically connected to the steam turbine rotor rotates as well. This produces an electrical current in the generator stator, which may subsequently be used to distribute electricity to customers via an electrical transformer.

Therefore, calculating the steam mass flow rate accurately enough and capturing the impact of transients on delivered steam are essential components of the nuclear reactor subsystem model. The combined thermal output of separate modules makes up the output of a Small Modular Reactors (SMR) plant complex. Therefore, the nuclear plant may continue to run even if one module is out of commission for refueling or a significant maintenance task.

For the development of nuclear energy that is economically viable, safe, and sustainable, reactor cycle models are essential. These reactor cycles can simulate neutron processes, core criticality, the burning up of nuclear fuel, and nuclear transmutation, among other things. Similar to neutron poison in their ability to capture neutrons, control rods are employed for finer reaction control or full reactor shutdown (SCRAM), in which case they are known as safety rods. According to the intended reaction rate and power, some control rods in reactors are kept in the core to ensure an even reaction profile, while others are kept outside the core or partially inserted.

The fuel pellets’ surrounding cladding material, on the other hand, is made of materials with low neutron absorption cross sections, allowing neutrons to travel through it with little loss. Since neutron-neutron interactions are ignored in the simulations in favor of neutron-matter interactions, the neutron cross-section, which has a dimension of area, describes the likelihood of reactions occurring.

It is referred to as inelastic neutron scattering if the neutron is first absorbed by the nucleus, changing its kinetic energy to the internal energy of the nucleus and remitting the neutron at a substantially lower energy, leaving the nucleus in an excited state. Although the fission reaction is what produces energy, it can only do so under the right circumstances. The energy that is released by the fission process, last but not least, is what is mostly employed to produce power. The incident neutron collides with the fissionable nucleus and penetrates it, forming a compound nucleus and energizing it to energies that are significantly higher than the nucleus’ critical energy. The incident neutron energy has a significant impact on neutron cross-sections. Until it reaches the thermal spectrum of energy, the fast neutron’s kinetic energy is reduced via scattering reactions.

Author Info

R. Edward*
Department of Economic, University of Oulu, Oolu, Finland

Received Date: Oct 03, 2022 / Manuscript No: JNEPGT-22-78866 / Editor Assigned: Oct 06, 2022 PreQC No: JNEPGT-22-78866(PQ) / Reviewed Date: Oct 26, 2022 / QC No: JNEPGT-22-78866 / Revised Date: Nov 02, 2022 Revised Manuscript No: JNEPGT-22-78866(R) / Published Date: Nov 09, 2022 Doi: 10.11131/JNEGPT-22/1000014

Copyright: © 2022 R. Edward. This is an open-access article distributed under the terms of the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original author and source are credited.