Deuterium-Tritium Fuel Self-Sufficiency in Fusion Reactors

MCNP-A general Monte Carlo code for neutron and photon transport

J.F. Briesmeister · CERN Document Server (European Organization for Nuclear Research) · 1986 · 710 citations

Engineering, Nuclear Engineering, Physics +14

ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6

V. McLane · 2001 · 203 citations

Natural Sciences, Nuclear Engineering, Physics +14

Uncertainties in Prediction of Tritium Breeding in Candidate Blanket Designs Due to Present Uncertainties in Nuclear Data Base

M.Z. Youssef, Mohamed Abdou · Fusion Technology · 1986 · 34 citations

Engineering, Nuclear Engineering, Nuclear Materials +16

Calculational Methods for Nuclear Heating—Part II: Applications to Fusion-Reactor Blankets and Shields

Mohamed Abdou, C.W. Maynard · Nuclear Science and Engineering · 1975 · 23 citations

Engineering, Nuclear Engineering, Physics +8

Assessments of Tritium Breeding Requirements and Breeding Potential for the STARFIRE/Demo Design

Jiyoung Jung, M. Abdou · Nuclear Technology - Fusion · 1983 · 23 citations · Full text

Engineering, Materials Engineering, Nuclear Engineering +16