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Processing of evaluated neutron data files in endf format on personal computers.

Material type: Text

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TextPublication details: [s.l.] : [s.n.], 1991.

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Holdings
Item type	Home library	Call number	Status	Barcode
Books	Centro de Información Eduardo Savino	INDC[HUN]-030 (Browse shelf(Opens below))	Available	36660

Total holds: 0

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Previous	INDC[CPR]-024 Evaluation of cross-sections for dosimetry reactions.	INDC[CUB]-004 Analysis of experimental data on neutron-induced reactions and development of code pcross for the calculation of differential pre-equilibrium emission spectra with modelling of level density function.	INDC[EGY]-006 A low background pulsed neutron polyenergetic beam at the ET-RR-1 reactor.	INDC[HUN]-030 Processing of evaluated neutron data files in endf format on personal computers.	INDC[JPN]-162-U Progress report [July 1991 to June 1992 inclusive].	INDC[JPN]-172-U Progress report [july 1993 to june 1994 inclusive].	INDC[NDS]-281 Nuclear data for neutron multiplication in fusion-reactor first-wall and blanket materials.	Next

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