How to find neutron capture and fission cross section

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Discussion Overview

The discussion revolves around finding neutron capture and fission cross sections, particularly in the context of Thorium utilization in nuclear reactors. Participants seek resources and clarification on interpreting data from databases related to neutron interactions across various energy ranges.

Discussion Character

  • Exploratory
  • Technical explanation
  • Debate/contested
  • Mathematical reasoning

Main Points Raised

  • One participant is looking for neutron capture and fission cross section figures for Thorium over a wide energy range, not limited to thermal energies.
  • Another participant suggests checking the ENDF VII database for relevant cross section data, specifically mentioning a range from 1 eV to 4 keV for Th-232.
  • A different participant provides a link to a database where plots of capture and fission cross sections can be found, indicating it may contain useful information.
  • One participant expresses difficulties in interpreting data from the NNDC database, particularly regarding discrepancies in cross section values for 233U at 0.05 eV, noting differences between calculated and tabulated values.
  • Another participant responds to the interpretation difficulties, suggesting that the values may be integrated over a thermal spectrum and clarifying the relationship between absorption and fission cross sections.
  • There is a mention of a potential issue with the assumption that the cross section is strictly 1/nu, which may affect the results derived from the Maxwell integral.
  • A separate post introduces a request for help with finding new problems in a textbook, indicating a shift in focus from the main topic of cross sections.

Areas of Agreement / Disagreement

Participants express differing views on the interpretation of cross section data, with some suggesting possible explanations for discrepancies while others remain uncertain about the correct values. The discussion does not reach a consensus on the interpretation of the data or the errors involved.

Contextual Notes

Participants highlight limitations in the data interpretation, including the dependence on definitions and the potential for integrated values over a thermal spectrum to differ from single energy values. Specific assumptions regarding the nature of cross sections are also questioned.

Who May Find This Useful

This discussion may be useful for researchers and students interested in nuclear physics, particularly those focusing on neutron interactions, cross section data, and the application of Thorium in nuclear reactors.

henxan
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I'm writing a paper on Thorium utilization in nuclear reactors.
In this connection I'm looking for figures which describe the neutron capture and neutron fission cross sections over a wide energy range (not only thermal). There are probably some online resources unbeknown to me, any hints?
 
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I think ENDF VII came out recently, you can check that.

http://www.nndc.bnl.gov/exfor7/endf00.htm

I looked up Th-232 quickly, and I found a small part that gave cross sections for 1 eV to 4 keV range. I couldn't find info on higher energies than that in th file though.
 
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Click on the sigma retrival in canydmans link or go straight here
http://www.nndc.bnl.gov/sigma/index.jsp

there you can find plots of capture and fission cross section and many other cross sections.
 
Superb! This was really helpful!

Thanks a lot people! :D
 
Difficutulties in interpreting data

I'm having some difficulties in interpreting the data on NNDC database. I'm trying to figure out how to use the database.
Ive got a table from IAEA's tecdoc 1450 attached to this message.

Specifically: Table gives data for 233U at 0.05eV:
sigma(f)=332
alfa=sigma(c)/sigma(f)=0.096

Straight forward calculation gives sigma(c)=32, which quite elegantly corresponds to the Sigma Plot of sigma(n,gamma) on NNDC.

But this is not the case in the table, which gives the sigma(c)=54

The second anomaly occurs for when I look at the data for sigma(n, total fission) at NNDC's site, which gives the value 377. In the table this value is 332 as earlier described.

Anyone got a hunch what errors I may be making?
 

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henxan said:
I'm having some difficulties in interpreting the data on NNDC database. I'm trying to figure out how to use the database.
Ive got a table from IAEA's tecdoc 1450 attached to this message.

Specifically: Table gives data for 233U at 0.05eV:
sigma(f)=332
alfa=sigma(c)/sigma(f)=0.096

Straight forward calculation gives sigma(c)=32, which quite elegantly corresponds to the Sigma Plot of sigma(n,gamma) on NNDC.

I don't see your problem: the absorption is 364, of which there is 332 fission, so there is 32 capture in the table, no ?

Also, these values are INTEGRATED values over a thermal SPECTRUM at 300 degrees (corresponding to about 0.05 eV average), but 32 is actually pretty close to the cross section in the table at 0.05 eV if you check, while 54 is the value at one single energy (0.0253 eV).
2200 m/s corresponds to 0.0253 eV.

But this is not the case in the table, which gives the sigma(c)=54
The second anomaly occurs for when I look at the data for sigma(n, total fission) at NNDC's site, which gives the value 377. In the table this value is 332 as earlier described.

Anyone got a hunch what errors I may be making?

I've checked this, and I don't know either why this is so. Maybe the cross section is not strictly 1/nu and the maxwell integral doesn't give the same as the value at the average energy...
 
i like to solve more problem in chapter 5(lamarsh),please tell me how find new problem?
 

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