SOME MEASUREMENTS OF PROMPT-NEUTRON FISSION YIELD (anti νp) IN THERMAL- NEUTRON FISSION OF ²³²U, ²³⁸Pu, ²⁴¹Pu, ²⁴¹Am, /sup 242m/Am, ²⁴³Cm, ²⁴⁵Cm, AND IN SPONTANEOUS FISSION OF ²⁴⁴Cm. [electronic resource]

Curium Isotopes Cm-243/neutron Fission Of, Prompt Neutron Yield From Thermal, (e); Americium Isotopes Am-241/neutron Fission Of, Prompt Neutron Yield From Thermal, (e); Uranium Isotopes U-232/neutron Fission Of, Prompt Neutron Yield From Thermal, (e); Curium Isotopes Cm-244/fission Of, Prompt Neutro...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Argonne National Laboratory (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C : Oak Ridge, Tenn. : United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1969.
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MARC

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245 0 0 |a SOME MEASUREMENTS OF PROMPT-NEUTRON FISSION YIELD (anti νp) IN THERMAL- NEUTRON FISSION OF ²³²U, ²³⁸Pu, ²⁴¹Pu, ²⁴¹Am, /sup 242m/Am, ²⁴³Cm, ²⁴⁵Cm, AND IN SPONTANEOUS FISSION OF ²⁴⁴Cm.  |h [electronic resource] 
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500 |a Jaffey, A.H.; Lerner, J.L. 
520 0 |a Curium Isotopes Cm-243/neutron Fission Of, Prompt Neutron Yield From Thermal, (e); Americium Isotopes Am-241/neutron Fission Of, Prompt Neutron Yield From Thermal, (e); Uranium Isotopes U-232/neutron Fission Of, Prompt Neutron Yield From Thermal, (e); Curium Isotopes Cm-244/fission Of, Prompt Neutron Yield From Spontaneous, (e); Curium Isotopes Cm-245/neutron Fission Of, Prompt Neutron Yield From Thermal, (e); Neutrons, Thermal/reactions (n,f) With A = 232 To 245 Nuclei, Prompt Neutron Yield From, (e); Americium Isotopes Am-242/ Neutron Fission Of Isomeric, Prompt Neutron Yield From Thermal, (e); Plutonium Isotopes Pu-241/neutron Fission Of, Prompt Neutron Yield From Thermal, (e); Plutonium Isotopes Pu-238/neutron Fission Of, Prompt Neutron Yield From Thermal, (e) 
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650 7 |a Americium 241-- Americium 242-- Curium 243-- Curium 245-- Fission-- Neutron Beams-- Plutonium 238- - Plutonium 241-- Thermal Neutrons-- Uranium 232.  |2 local. 
650 7 |a Fission Yield.  |2 local. 
650 7 |a Prompt Neutrons Curium 244-- Spontaneous Fission.  |2 local. 
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