• Nuclear Engineering and Technology   1991  Volume.23  No.4 465 ~ 474

• Thermal Effects on the Physicochemical Properties of Domestic Bentonite as a Buffer Material of Spen...

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• Nuclear Engineering and Technology   1991  Volume.23  No.4 456 ~ 464

• A Numerical Model for Predicting the Radial Power Profile in CANDU-PHWR Fuel Pellet

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• Nuclear Engineering and Technology   1991  Volume.23  No.4 444 ~ 455

• a Study on He+ Ioon Beam Extraction in the Duoplasmatron Ion Source

• Nuclear Engineering and Technology   1991  Volume.23  No.4 438 ~ 443

• Ion Optical Study on the He++ Beam Transport System of the SNU 1.5-MV Tandem Van de Graaff Accelerat...

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• Nuclear Engineering and Technology   1991  Volume.23  No.4 426 ~ 437

• Construction of RB Charge Exchange Cell and Characteristic Experiment for He- Ion Production

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• Nuclear Engineering and Technology   1991  Volume.23  No.4 420 ~ 425

• Applicability of Domestic Bentonite as a Buffer Material of Spent Fuel Repository

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• Nuclear Engineering and Technology   1991  Volume.23  No.4 410 ~ 419

• Analytic Prediction of friction Factors for Turbulent Flow in Longitudinally Finned Rod Bundles

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• Nuclear Engineering and Technology   1991  Volume.23  No.4 401 ~ 409

• Modeling Study on Nuclide Transport in Ocean-an Ocean Compartment Model

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• Nuclear Engineering and Technology   1991  Volume.23  No.4 387 ~ 400

• An Experimental Study on Factors Affecting the Leachability of Cs-137 in Cement Matrix and Leaching ...

• Nuclear Engineering and Technology   1991  Volume.23  No.4 374 ~ 386

• Study on the Quantitative Rod Internal Pressure Design Criterion

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• Nuclear Engineering and Technology   1991  Volume.23  No.4 363 ~ 373