Evaluation of Thermal Neutron Constants of 233 U, 235 U, 239 Pu and 241 Pu and the Fission Neutron Yield of 252 Cf

Evaluation of Thermal Neutron Constants of 233 U, 235 U, 239 Pu and 241 Pu and the Fission Neutron Yield of 252 Cf
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Evaluation of Thermal Neutron Constants of 233 U, 235 U, 239 Pu and 241 Pu and the Fission Neutron Yield of 252 Cf Related Books

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Type: BOOK - Published: 1982 - Publisher:

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A consistent set of best values of the 2200 meter/second neutron cross sections, Westcott g-factors, and fission neutron yields for 233U, 235U, 239Pu and 241Pu
Evaluation of Thermal Neutron Constants of 233U, 235U, 239Pu and 241Pu and the Fission Neutron Yield of 252Cf
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Evaluation of the Thermal Constants of 233U, 235U, 239Pu and 241Pu, and the Fission Neutron Yield of 252Cf
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Evaluation of the Thermal Constants of 233U, 235U, 239PU and 241PU and the Fission Neutron Yield of 252CF.
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