Breech-Loading Neutron Gun for Controlled Nuclear Energy Release

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Solution Overview

Problem

Current nuclear power generation methods lack control and safety, relying on fuel rods and thorium with salt beds that pose environmental and safety hazards, and are not economically efficient.

Innovation Solution

A breech-loading neutron gun system that regulates neutron release by aligning ceramic discs with varying amounts of Americium or no radioactive material, allowing precise control of neutron density into a containment unit, reducing the need for fuel rods and enhancing safety and efficiency.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Power

If fuel rods or thorium with salt beds are used for nuclear energy generation, then nuclear power can be produced, but control over energy release is insufficient and safety hazards arise

Engineering Contradiction:
Improvenuclear energy releaseVSAvoidcontrol and safety
Core Design Contradiction:
PowerVSReliability

Solution Approach 1:

The neutron source is segmented into multiple ceramic discs, each containing different amounts of Americium or other radioactive material. By selectively positioning specific discs in the neutron beam path, the system can precisely control the neutron flux and thus the energy release rate, providing fine-grained control over nuclear power generation while maintaining safety

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

The breech assembly is made movable, allowing dynamic adjustment of which ceramic disc is positioned in the neutron beam path. This mechanical mobility enables real-time control of neutron emission levels, transforming the system from static to dynamic control of energy release, thereby improving both safety and reliability

Inventive Principle:
Principle #15Dynamics

2Ease of operation

If control rods are used to regulate energy release, then some control is achieved, but the degree of control is insufficient for safe and efficient operation

Engineering Contradiction:
Improveenergy release controlVSAvoidsafety and efficiency
Core Design Contradiction:
Ease of operationVSReliability

Solution Approach 1:

Different ceramic discs are prepared with locally different qualities - specifically, different concentrations of Americium or other radioactive material. This allows each disc to produce a specific neutron flux level, enabling precise local control of the neutron source strength to match operational requirements, thereby achieving both ease of operation and high reliability

Inventive Principle:
Principle #3Local quality

Solution Approach 2:

The system controls energy release by changing the parameter of neutron source strength through selective positioning of ceramic discs with varying radioactive material content. This direct parameter control method provides more precise and reliable regulation compared to control rods, enabling safe and efficient operation across different power levels

Inventive Principle:
Principle #35Parameter changes

3Power

If thorium with salt beds is used for energy generation, then nuclear power is produced, but safety hazards increase due to lack of control

Engineering Contradiction:
Improvenuclear energy generationVSAvoidsafety hazards
Core Design Contradiction:
PowerVSObject-affected harmful factors

Solution Approach 1:

The ceramic discs containing radioactive material serve as an intermediary between the neutron beam and the thorium fuel. By controlling which disc is positioned in the beam path, the system mediates the neutron flux reaching the thorium, thereby controlling the fission rate and eliminating the safety hazards associated with uncontrolled energy release while maintaining efficient power generation

Inventive Principle:
Principle #24Intermediary (Mediator)

Applied Scientific Principles

This section explains which scientific principles are used to turn an abstract innovation direction into a practical engineering solution.

Function Achieved in This Case

The system provides a high degree of control over nuclear energy release, ensuring safe, economical, and environmentally friendly power generation by adjusting neutron density based on sensor feedback, allowing for precise energy output and cooling management.

Implementation Method 1

ceramic discs are placed which contain varying degrees of Americium or other nuclear material... the appropriate amount of neutrons can be released into the containment unit containing thorium or other radioactive material

Methodology Applied
Scientific EffectRadioactive decay: Radioactive Decay

Implementation Method 2

provides a method and system for controlling the release of nuclear energy... regulating neutron release by aligning ceramic discs with varying amounts of Americium or no radioactive material, allowing precise control of neutron density into a containment unit

Methodology Applied
Scientific EffectNuclear fission: Nuclear Fission

Implementation Method 3

sensors for measuring heat level or other parameters inside the containment unit which is measured by such sensors... transmit the temperature or other parameter measurement to the software program for the regulation of the movement of the breech

Methodology Applied
Scientific EffectThermal radiation detection: Thermal Radiation

Data Source

PatentUS11373767B2Neutron emitter for a nuclear-fuel reactor
Publication Date: 2022.06.28 COSMIC ENERGY POWER INC
  • US11373767B2 patent drawing
  • US11373767B2 patent drawing
  • US11373767B2 patent drawing

AI summary

A breech-loading neutron gun providing neutrons to stimulate the release of energy from nuclear materials in a containment vessel in a regulated fashion includes a chamber among a plurality of chambers located in a breech where one or more of the plurality of chambers are configured and arranged to load with a neutron source, and a mechanism for controllably moving the breech or the chamber relative to an access cavity of the containment vessel and exposing the nuclear materials to neutrons from the chamber when the chamber containing the neutron source aligns with the access cavity.