Compact Medical Neutron Source with Start-Stop Control

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Solution Overview

Problem

Current neutron therapy devices for cancer treatment are complex, cumbersome, and costly, with high-enrichment fuel that limits their widespread use and requires extensive infrastructure, making them unsuitable for clinical settings and difficult to operate in a start-stop mode for precise tumor irradiation.

Innovation Solution

A small-sized, low-power nuclear reactor with a start-stop mode and minimal radioactive waste production, designed for direct clinical use, featuring a collimator, neutron filter, and movable gates to provide controlled neutron flux for neutron capture and fast neutron therapy, using uranium dioxide fuel with 15-20% enrichment and boron carbide control rods, and a coolant system for stable operation.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Quantity of substance

If conventional neutron therapy devices are used, then neutron flux density is achieved, but device complexity and infrastructure requirements increase significantly

Engineering Contradiction:
Improveneutron flux densityVSAvoiddevice complexity
Core Design Contradiction:
Quantity of substanceVSDevice complexity

Solution Approach 1:

The device is divided into distinct functional modules: a compact nuclear reactor core, a separate collimator system with movable gates, and an independent neutron filter. This segmentation allows each component to be optimized independently and simplifies the overall system architecture, reducing infrastructure requirements while maintaining high neutron flux density for therapy.

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

The invention extracts only the essential neutron-generating function from complex conventional reactors, creating a simplified compact reactor design that produces neutron flux without requiring extensive support infrastructure. The collimator and filter systems are also designed as standalone components that can be independently adjusted.

Inventive Principle:
Principle #2Taking out (Extraction)

2Productivity

If high-enrichment fuel is used, then neutron production efficiency is improved, but safety and proliferation risks worsen

Engineering Contradiction:
Improveneutron production efficiencyVSAvoidsafety and proliferation risks
Core Design Contradiction:
ProductivityVSObject-affected harmful factors

Solution Approach 1:

The invention changes the enrichment parameter from conventional high-enrichment (typically >20% U-235) to a reduced enrichment level (10-20% U-235). This parameter change maintains sufficient neutron production efficiency for therapeutic applications while significantly reducing safety concerns and nuclear proliferation risks, allowing the reactor to operate safely in a clinical environment.

Inventive Principle:
Principle #35Parameter changes

3Stability of the object's composition

If continuous operation mode is used, then neutron beam stability is improved, but ability to perform precise start-stop irradiation worsens

Engineering Contradiction:
Improveneutron beam stabilityVSAvoidstart-stop operation capability
Core Design Contradiction:
Stability of the object's compositionVSEase of operation

Solution Approach 1:

The collimator system incorporates movable gates that can dynamically adjust the neutron beam path, enabling precise start-stop irradiation of tumors. The reactor core design includes control elements that allow rapid power adjustment, maintaining neutron beam stability during operation while providing the operational flexibility to start and stop irradiation precisely when needed for therapeutic accuracy.

Inventive Principle:
Principle #15Dynamics

4Volume of moving object

If reactor size is reduced for clinical use, then ease of deployment is improved, but neutron flux intensity worsens

Engineering Contradiction:
Improvereactor sizeVSAvoidneutron flux intensity
Core Design Contradiction:
Volume of moving objectVSQuantity of substance

Solution Approach 1:

The reactor core employs composite fuel elements combining uranium dioxide with specific moderators and reflectors in a optimized configuration. This composite structure maximizes neutron production efficiency within a compact volume, achieving sufficient neutron flux intensity for therapy despite the reduced reactor size required for clinical deployment.

Inventive Principle:
Principle #40Composite materials

Solution Approach 2:

The neutron flux is concentrated locally at the treatment position through the collimator system and movable gates, which focus the neutron beam precisely on the tumor target. This local concentration of neutron quality compensates for the reduced overall reactor size, delivering intense neutron flux exactly where needed for effective therapy.

Inventive Principle:
Principle #3Local quality

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 solution provides a safe, cost-effective, and reliable neutron source for cancer therapy, capable of maintaining the required neutron flux density for therapeutic sessions with minimal radioactive waste and operational complexity, ensuring precise tumor irradiation while minimizing harm to healthy tissue.

Implementation Method 1

nuclear reactor with a core in the form of a parallelepiped... using uranium dioxide fuel with 15-20% enrichment

Methodology Applied
Scientific EffectNuclear fission: Nuclear Fission

Implementation Method 2

collimator, neutron filter, and movable gates to provide controlled neutron flux for neutron capture and fast neutron therapy

Methodology Applied
Scientific EffectNeutron beam direction and collimation:

Implementation Method 3

The required spectrum of epithermal neutrons can be formed behind a filter several dozen centimeters thick

Methodology Applied
Scientific EffectNeutron energy spectrum filtering: Filter (physical)

Implementation Method 4

a coolant system for stable operation

Methodology Applied
Scientific EffectHeat transfer: Conduction (thermal)

Data Source

PatentUS11291862B2Medical source of neutrons, nuclear reactor for a medical neutron source, and method of application of a medical neutron source
Publication Date: 2022.04.05 OBSHSHESTVO S OGRANICHENNOJ OTVETSTVENNOSTYU "NAUCHNO-TEKHNICHESKIJ TSENTR INNOVATSIJ"
  • US11291862B2 patent drawing
  • US11291862B2 patent drawing
  • US11291862B2 patent drawing

AI summary

A coolant having a set temperature is fed into the nuclear reactor core of a medical neutron source, which is in a subcritical state. The nuclear reactor core is transitioned from the subcritical state to a critical state until the nominal power of the nuclear reactor is achieved. A neutron output channel is opened in order to conduct a neutron therapy session, and the operation of the reactor is maintained at nominal power while the neutron therapy session is conducted. At the end of the session, the neutron output channel is closed at the same time as the reactor core is transitioned to a subcritical state. The temperature of the coolant entering the core is maintained unchanged and equal to a set temperature, both when the core is transitioned to a critical state and during the operation of the nuclear reactor at nominal power.