Dose calculation at the entrance of neutron source room using MCNPX (monte carlo - particle radiation transport computer code)

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Personal Author:

Publication Information:

Skudai : Universiti Teknologi Malaysia, 2006

Physical Description:

1v + 1 CD-ROM

General Note:

Also available in compact disc version : CP 4819 ra

Subject Term:

DSP_DISSERTATION:

Project Paper (Sarjana Muda Sains (Fizik Kesihatan)) - Universiti Teknologi Malaysia, 2006

Library	Item Barcode	Call Number	Material Type	Item Category 1	Status
Searching... FS Library	FS300000003401	QC795.32.R3 T43 2006	Closed Access Thesis	UTM Project Paper (Closed Access)	Searching... Unknown
Searching... Perpustakaan Raja Zarith Sofiah	30000010085635	QC795.32.R3 T43 2006	Closed Access Thesis	UTM Project Paper (Closed Access)	Searching... Unknown