Calculations of thermal-reactor spent-fuel nuclide inventories and comparisons with measurements

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Comparisons with integral measurements have demonstrated the accuracy of CINDER codes and libraries in calculating aggregate fission-product properties, including neutron absorption, decay power, and decay spectra. CINDER calculations have, alternatively, been used to supplement measured integral data describing fission-product decay power and decay spectra. Because of the incorporation of the extensive actinide library and the use of ENDF/B-V data, it is desirable to compare the inventory of individual nuclides obtained from tandem EPRI-CELL/CINDER-2 calculations with those determined in documented benchmark inventory measurements of spent reactor fuel. The development of the popular /sup 148/Nd burnup measurement procedure is outlined, and areas ... continued below

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Pages: 28

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Wilson, W.B.; LaBauve, R.J. & England, T.R. January 1, 1982.

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Description

Comparisons with integral measurements have demonstrated the accuracy of CINDER codes and libraries in calculating aggregate fission-product properties, including neutron absorption, decay power, and decay spectra. CINDER calculations have, alternatively, been used to supplement measured integral data describing fission-product decay power and decay spectra. Because of the incorporation of the extensive actinide library and the use of ENDF/B-V data, it is desirable to compare the inventory of individual nuclides obtained from tandem EPRI-CELL/CINDER-2 calculations with those determined in documented benchmark inventory measurements of spent reactor fuel. The development of the popular /sup 148/Nd burnup measurement procedure is outlined, and areas of uncertainty in it and lack of clarity in its interpretation are indicated. Six inventory samples of varying quality and completeness are examined. The power histories used in the calculations have been listed for other users.

Physical Description

Pages: 28

Notes

NTIS, PC A03/MF A01.

Source

  • Thermal reactor benchmark calculations, techniques, results and applications seminar, Upton, NY, USA, 17 May 1982

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  • Other: DE82021772
  • Report No.: LA-UR-82-2341
  • Report No.: CONF-820566-7
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 5043554
  • Archival Resource Key: ark:/67531/metadc1056589

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • January 1, 1982

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  • Jan. 22, 2018, 7:23 a.m.

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  • Feb. 1, 2018, 7:01 p.m.

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Wilson, W.B.; LaBauve, R.J. & England, T.R. Calculations of thermal-reactor spent-fuel nuclide inventories and comparisons with measurements, article, January 1, 1982; New Mexico. (digital.library.unt.edu/ark:/67531/metadc1056589/: accessed July 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.