The specification of neutron flux and nuclear cross-sections in reactor calculations.

By:

Contributor(s):

Material type: Text

TextLanguage: en Publication details: Chalk River : AECL, 1955.Description: v. 2 p. 59-76ISSN:

Tags from this library: No tags from this library for this title. Log in to add tags.

Holdings
Item type	Home library	Call number	Status	Barcode
Books	Centro de Información Eduardo Savino	AECL-194 (Browse shelf(Opens below))	Available	44103

Total holds: 0

Browsing Centro de Información Eduardo Savino shelves Close shelf browser (Hides shelf browser)

Previous	No cover image available	No cover image available	No cover image available	No cover image available	No cover image available	No cover image available	No cover image available	Next
Previous	AECL-191 Reactor xenon poison simulator.	AECL-192 Nuclear Energy No. 3 of a series: Basic problems in the processing of nuclear fuels.	AECL-193 Prevention and treatment of radiation injury.	AECL-194 The specification of neutron flux and nuclear cross-sections in reactor calculations.	AECL-195 Out-reactor tests of the HTP loop.	AECL-196 The effect of zinc deficiency on the male genital system.	AECL-198 Progress report april 1, to june 30, 1955: Electronics Branch.	Next

There are no comments on this title.

to post a comment.