Information of secondary neutron source in French PWR

In summary, a secondary neutron source in a French pressurized water reactor (PWR) is a component that helps to maintain the stability and efficiency of the reactor. It is typically located in the upper part of the reactor and is responsible for producing additional neutrons that can sustain the nuclear reaction. This source is necessary because the primary source of neutrons, the fuel rods, eventually deplete and need to be replaced. The secondary neutron source in a French PWR is usually made of beryllium or graphite and is constantly monitored and controlled to ensure safe and optimal operation of the reactor.
  • #1
Pengtaofu
23
2
The specific information of secondary neutron source in French 1300MWe and N4 PWRs are needed, e.g.the total mass of Sb-Be in core and the thickness of Sb-Be cladding with stainless steel, but unfornately I couldn't find any useful information in google in English. I guess some informatio could be found in google in Fench,Could anyone help me to search information? Thank you very much for any help.
 
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  • #2
The following article contains some data, e.g., density of Sb and Be, and SS, but unfortunately the design is for a 16x16 OP-1400 fuel design (similar to CE System 80).
http://www.sciencedirect.com/science/article/pii/S1738573316300572

Typically there are 4 source rods per assembly in two assemblies, or sometimes four assemblies.

For a typical 17x17 core, with a core height of 3.66 m, there is a diagram of an Sb-Be secondary source here
http://www.pnl.gov/main/publications/external/technical_reports/PNNL-19151.pdf.

The length of Sb-Be is 88 inches (223.5 cm). The stainless steel (SS 304 or 316) cladding outer diameter is approximately 0.968 cm, and the wall thickness is approximately 0.057 cm. It's possible that a longer Sb-Be would be used for the 4.27 m core, e.g., 260 cm.
 
  • #3
Astronuc said:
The following article contains some data, e.g., density of Sb and Be, and SS, but unfortunately the design is for a 16x16 OP-1400 fuel design (similar to CE System 80).
http://www.sciencedirect.com/science/article/pii/S1738573316300572

Typically there are 4 source rods per assembly in two assemblies, or sometimes four assemblies.

For a typical 17x17 core, with a core height of 3.66 m, there is a diagram of an Sb-Be secondary source here
http://www.pnl.gov/main/publications/external/technical_reports/PNNL-19151.pdf.

The length of Sb-Be is 88 inches (223.5 cm). The stainless steel (SS 304 or 316) cladding outer diameter is approximately 0.968 cm, and the wall thickness is approximately 0.057 cm. It's possible that a longer Sb-Be would be used for the 4.27 m core, e.g., 260 cm.
Thank you very much for providing so much useful information and document.
There are some clues about configuration of Westinghouse-type secondary sources assembly and the most univesal configuration contains 4 source rod, which could been foungd at Page 25/56 in document Integrity of Neutron-Absorbing Components of LWR Fuel Systems.pdf http://www.osti.gov/scitech/servlets/purl/5980553/.
However, there are seldom information of secondary source in French 1300MW and N4 unit in web. It may get some clues if one seach in French.
As I know, more Sb-Be rods with shorter actived length are used for about 4.2m reactor core in EPR, but not more longer source rod.
 
  • #4
The description of the Westinghouse AP-1000 (~4.2 m core) has the following as some information on the secondary source rods.

http://www.nrc.gov/docs/ML1117/ML11171A444.pdf

The primary and secondary source rods both use the same cladding material as the absorber rods.
The secondary source rods contain antimony-beryllium pellets stacked to a height of
approximately 88 inches [223.5 cm]. The primary source rods contain capsules of californium (plutonium beryllium
possible alternate) source material and alumina spacers to position the source material
within the cladding. The rods in each assembly are fastened at the top end to a hold-down
assembly.

The other structural members, except for the springs, are constructed of Type 304 stainless steel.
The springs exposed to the reactor coolant are nickel-chromium-iron Alloy 718.See Figure 4.2-15 Secondary Source Assembly

There is a conflict between this figure Ref: 97.0 absorber length [246.4 cm] and the 88 inches [223.5 cm] in the text. The figure is probably correct, and that would likely apply to the 4.2 m cores of the CPY and N4/P4 plants.

There may be some information here
http://www.irsn.fr/fr/documents/ra2010/irsn_dsu-217_tritium-sources-production.pdf
 

1. What is a secondary neutron source in a French PWR?

A secondary neutron source in a French PWR (pressurized water reactor) is a component that produces additional neutrons in the reactor core. These neutrons are used to sustain the nuclear chain reaction and generate heat for electricity production.

2. How does the secondary neutron source work in a French PWR?

The secondary neutron source in a French PWR is typically made of beryllium or graphite material, which is bombarded by high-energy protons from the reactor's primary coolant. This process produces additional neutrons that are used to maintain the nuclear reaction and generate heat.

3. What is the purpose of the secondary neutron source in a French PWR?

The secondary neutron source in a French PWR plays a crucial role in maintaining the nuclear reaction and ensuring a steady supply of heat for electricity production. It also helps to control the reactor's power output and maintain safe operation.

4. How is the secondary neutron source controlled and monitored in a French PWR?

The secondary neutron source in a French PWR is controlled and monitored through a series of safety systems and procedures. These include regulating the flow of primary coolant, monitoring neutron flux levels, and using control rods to adjust the reactor's power output.

5. Are there any safety concerns associated with the secondary neutron source in a French PWR?

Like all components in a nuclear power plant, the secondary neutron source in a French PWR is subject to rigorous safety regulations and inspections. Proper maintenance and monitoring of the source are essential to ensure safe and efficient operation of the reactor. In the rare event of a malfunction, there are multiple safety systems in place to shut down the reactor and prevent any potential hazards.

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