Journal Search Engine
-
The Direct Dissolution of Ion-Exchange Resin by Fenton's Reagent
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.85-90
Open abstract -
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.91-99
Open abstract -
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.5 No.1 pp.100-102
Open abstract -
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.311-320
Open abstract -
Rock Weathering and Geochemical Characteristics in the KURT
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.321-328
Open abstract -
Spatial Distributions of 3H and 14C in the Shielding Concrete of KRR-2
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.329-334
Open abstract -
Development of a Simulation Program for the Li-Reduction Process of PWR Spent Fuel
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.335-344
Open abstract -
Measurement of the Radiolysis Gases Generated in Several Waste Forms by External Irradiation
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.345-352
Open abstract -
A Mathematical Model to Evaluate the Radiological Risks for the Reuse of Decommissioning Site
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.353-363
Open abstract -
Model for predicting the 137Cs contamination of an agricultural plant following a soil deposition)
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.365-372
Open abstract -
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.373-384
Open abstract -
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.385-391
Open abstract -
Analysis of the Disposal Tunnel and Disposal Pit Spacing for the Spent Fuel Repository Layout
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.393-400
Open abstract -
Consideration of Regulatory Systems for Decommissioning of Nuclear Power Plants
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.401-409
Open abstract -
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.4 pp.410-412
Open abstract -
A Study on the Wigner Energy Release Characteristics of Irradiated Graphite of KRR-2
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.209-216
Open abstract -
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.217-226
Open abstract -
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.227-234
Open abstract -
An Experimental Study on the Sorption of Uranium(VI) onto a Bentonite Colloid
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.235-243
Open abstract -
The Test for Verifying a Tip-Over Analysis of a Dry Storage Cask
Journal of Nuclear Fuel Cycle and Waste Technology :: Vol.4 No.3 pp.245-253
Open abstract
JNFCWT
Online Submission
Korean Radioactive
Waste Society (KRS)
Editorial Office
Contact Information
- Tel: +82-42-861-5851, 866-4157
- Fax: +82-42-861-5852
- E-mail: krs@krs.or.kr