Shielded Decay Station for Flexible Irradiation Target Discharge

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Solution Overview

Problem

Existing radionuclide production systems in nuclear reactors face challenges with delivery intervals longer than client demands, produce undesirable short-lived radioactive isotopes, and require expensive hot cells for safe disposal, which are impractical in commercial reactors due to space constraints.

Innovation Solution

A decay station with radiation shielding and controlled distribution mechanisms allows for selective transfer and temporary storage of irradiation targets, enabling shorter delivery intervals and safe disposal without hot cells, using a diverter for flexible target routing.

Engineering Contradictions & Design Principles

VSEngineering Contradiction Analysis

1Productivity

If radionuclides are produced through exposure to neutron flux in the core of the nuclear reactor, then the desired radionuclides are generated, but the delivery interval is longer than the time required for client demands

Engineering Contradiction:
Improvedelivery interval of radionuclidesVSAvoidactivation time for producing radionuclides
Core Design Contradiction:
ProductivityVSLoss of time

Solution Approach 1:

The system segments the irradiation process by using multiple instrumentation tubes (at least two tubes) that can be independently loaded and irradiated. This allows parallel production of radionuclides, reducing the overall delivery interval by having multiple batches available simultaneously rather than processing sequentially through a single tube.

Inventive Principle:
Principle #1Segmentation

Solution Approach 2:

The system implements preliminary action by pre-loading irradiation targets into instrumentation tubes before reactor operation. The tubes are prepared and positioned in advance, allowing immediate irradiation when the reactor is operational, thus reducing the total time from production initiation to radionuclide availability.

Inventive Principle:
Principle #10Preliminary action

2Reliability

If activated irradiation targets containing short-lived highly radioactive isotopes are discharged into conventional storage containers, then the desired radionuclides can be stored, but the radiation transmission to the environment becomes unacceptably high

Engineering Contradiction:
Improvesafety of radionuclide storageVSAvoidradiation transmission to environment
Core Design Contradiction:
ReliabilityVSObject-generated harmful factors

Solution Approach 1:

The patent introduces an intermediary shielding structure (at least one shielding structure) positioned between the activated irradiation targets and the environment. This shielding structure contains radiation-absorbing materials that intercept and absorb the harmful radiation from short-lived isotopes, allowing safe discharge into conventional storage containers without unacceptably high radiation transmission to the environment.

Inventive Principle:
Principle #24Intermediary (Mediator)

3Object-affected harmful factors

If a hot cell is added for receiving activated irradiation targets prior to discharging them into storage containers, then the radiation safety is improved, but the construction cost and space occupation become very high

Engineering Contradiction:
Improveradiation exposure protectionVSAvoidconstruction cost and space of hot cell
Core Design Contradiction:
Object-affected harmful factorsVSDevice complexity

Solution Approach 1:

The patent employs disposable or replaceable shielding structures that can be positioned temporarily during target discharge and then removed or replaced. These simpler, potentially disposable shielding components provide the necessary radiation protection without the permanent, expensive infrastructure of a hot cell. The shielding structures are designed to be moved in and out as needed, reducing overall system complexity and cost.

Inventive Principle:
Principle #27Cheap short-living objects (Disposable)

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 enables cost-effective, compact, and safe disposal of activated targets with reduced environmental risk, allowing for flexible integration into existing installations and efficient production of radionuclides.

Implementation Method 1

a radiation shielding, configured for shielding the environment of the decay station from the radiation emitted by the irradiation targets contained in the decay station

Methodology Applied
Scientific EffectRadiation shielding: Absorption (EM radiation)

Implementation Method 2

The activation of the irradiation targets in the core of the nuclear reactor results in the production of the desired radionuclides, but also of short-lived highly radioactive isotopes as by-products

Methodology Applied
Scientific EffectNeutron activation: Nuclear Fission

Data Source

PatentUS12592326B2Installation and method for producing activated irradiation targets in an instrumentation tube system of a nuclear reactor
Publication Date: 2026.03.31 FRAMATOME SA
  • US12592326B2 patent drawing
  • US12592326B2 patent drawing
  • US12592326B2 patent drawing

AI summary

A decay station includes a housing comprising a radiation shielding. The housing delimits a decay conduit intended for containing the irradiation targets in the predetermined linear order. The decay conduit includes a decay conduit inlet, intended to be connected to the structure of the core of the nuclear reactor for receiving the irradiation targets therefrom; and a decay conduit outlet, intended to be connected to an irradiation target discharge system for discharging the irradiation targets from the decay station. The decay station further includes an inlet distributor, located at the decay conduit inlet, and configured for releasing only a predetermined amount of irradiation targets at a time from the decay station towards the structure of the core of the nuclear reactor. The inlet distributor is configured for releasing the irradiation targets closest to the decay conduit inlet, while retaining the remaining irradiation targets in the decay conduit. The decay station further includes an inlet counter configured for counting the number of irradiation targets entering or exiting the decay conduit through the decay conduit inlet. The inlet counter is located at the decay conduit inlet. The decay station further includes an outlet radiation detector configured for measuring the radiation emitted by an irradiation target located at the decay conduit outlet.