학술논문

ORNL cross-section sensitivity analysis applications for radiation shielding
Document Type
Conference
Author
Source
Conference: Meeting on advanced reactors; physics, design and economics, Atlanta, Georgia, USA, 8 Sep 1974; Other Information: Orig. Receipt Date: 31-DEC-74
Subject
N72400* --Physics (Radiation & Shielding)--Shielding Calculations & Experiments *IRON-- NEUTRON TRANSPORT
*NEUTRON REACTIONS-- CROSS SECTIONS
*SHIELDING-- CROSS SECTIONS
*SODIUM-- NEUTRON TRANSPORT
ONE-DIMENSIONAL CALCULATIONS
REACTOR VESSELS
SENSITIVITY
TWO-DIMENSIONAL CALCULATIONS
Language
English