Radioactive Waste Container with Finned Ferrule Neutron Shielding
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Solution Overview
Problem
Existing containers for radioactive waste, particularly spent fuel from nuclear power plants, rely heavily on thick forged steel layers for protection, which are costly and difficult to handle, and lack efficient neutron radiation shielding.
Innovation Solution
A container design that maintains an optimal proportion between protection layers by using a radionuclide containment barrier with a first ferrule and a gamma radiation shield with a second ferrule featuring fins to house neutron shielding material, reducing the need for thick forged steel.
Engineering Contradictions & Design Principles
Engineering Contradiction Analysis
1Object-affected harmful factors
If a thick layer of forged steel is used for gamma radiation shielding, then radiation protection is improved, but manufacturing cost and handling difficulty increase
Solution Approach 1:
The patent replaces the traditional thick forged steel layer with a composite structure consisting of a thinner steel layer combined with a neutron poison layer (boron carbide or boron steel). This composite material approach achieves equivalent or superior gamma radiation shielding with reduced thickness and improved manufacturability, as the neutron poison materials provide additional shielding efficiency per unit thickness.
Solution Approach 2:
The invention changes the material composition parameters by introducing neutron poison materials (boron carbide or boron steel) with specific boron content (at least 10% by weight). This parameter change allows the shielding layer to achieve the required protection with reduced thickness, directly addressing the manufacturing and handling difficulties of thick forged steel.
2Object-affected harmful factors
If forged steel is used for gamma radiation protection, then shielding efficiency is improved, but the need for additional neutron shielding increases device complexity
Solution Approach 1:
The patent merges the gamma radiation shielding function and neutron radiation shielding function into a single integrated layer. The composite layer combines steel (for gamma shielding) with neutron poison materials (for neutron shielding), eliminating the need for separate layers and reducing overall device complexity while maintaining dual protection capabilities.
Solution Approach 2:
By using composite materials containing both steel and neutron poison substances in a single layer, the invention simultaneously addresses gamma and neutron radiation protection needs, reducing the number of components and simplifying the overall container structure compared to using thick forged steel alone.
3Strength
If thick forged steel is used to ensure structural integrity, then mechanical strength is improved, but weight and handling difficulty increase
Solution Approach 1:
The invention changes the thickness parameter of the steel layer by introducing high-efficiency neutron poison materials that provide additional radiation shielding per unit thickness. This allows reduction of the steel layer thickness from 200-300 mm to a thinner configuration while maintaining both structural integrity and radiation protection, thereby reducing overall weight.
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 container provides effective protection against both gamma and neutron radiation without the high cost and handling difficulties of thick forged steel, while maintaining optimal structural integrity and thermal management.
Implementation Method 1
a neutron shielding material arranged in the gaps defined between the fins of the second ferrule
Implementation Method 2
Thermal bridge to evacuate the waste heat stored in the fuel elements
Implementation Method 3
whose main critical function is the protection against mechanical stresses such as impacts, seismic stresses or others
Implementation Method 4
which given its high density has a high shielding ability against photonic radiation
Data Source
AI summary
A radioactive waste container comprising: a radionuclide containment barrier (1) delimiting a housing (16) for radioactive waste and comprising a first ferrule (11), a bottom (12), an upper flange (13), and a lid (14) fixed by bolts (15) to said upper flange (13); a shield (2) against gamma radiation, arranged externally with respect to the containment barrier (1) and comprising a second ferrule (21) with external fins (22) defining gaps between them, a lower closing flange (23), an outer lid (24) provided with bolts (25) for fixing to the upper flange (13) of the containment barrier (1), and an outer bottom (26) fixed to the lower closing flange (23); and a neutron shielding material (3) arranged in the gaps defined between the fins (22) of the second ferrule.