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Home / Publications / Journals / Nuclear Technology / Volume 116 / Number 1

Volume 116

Number 1

Pellet Power Ratio in a Pellet-Suspension Fission Core

D. R. Kingdon, A. A. Harms

Nuclear Technology / Volume 116 / Number 1 / October 1996 / Pages 1-8

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-A35307

Study on Reactivity Worth of Beryllium by (n,2n) and (γ,n) Reactions

Tsuyoshi Misawa, Seiji Shiroya, Keiji Kanda

Nuclear Technology / Volume 116 / Number 1 / October 1996 / Pages 9-18

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT96-A35308

Assessment of the Simulation Capability of RELAP5/MOD3 Compared with IIST Tests for Loss of the Residual Heat Removal System During Midloop Operation

Yuh-Ming Ferng, Chien-Hsiung Lee

Nuclear Technology / Volume 116 / Number 1 / October 1996 / Pages 19-33

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35309

A Model for Nonvolatile Fission Product Release During Reactor Accident Conditions

Brent J. Lewis, Bernard André, Gérard Ducros, Denis Maro

Nuclear Technology / Volume 116 / Number 1 / October 1996 / Pages 34-54

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35310

Passive Cooling System with Temperature Control for Reactor Containments

Charles W. Forsberg, James C. Conklin

Nuclear Technology / Volume 116 / Number 1 / October 1996 / Pages 55-65

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35311

RELAP5/MOD3 Simulation of the Station Blackout Experiment Conducted at the IIST Facility

Yuh-Ming Ferng, Tay-Jian Liu, Chien-Hsiung Lee

Nuclear Technology / Volume 116 / Number 1 / October 1996 / Pages 66-77

Technical Paper / Nuclear Reactor Safety / dx.doi.org/10.13182/NT96-A35312

Boron-Nitride-Coated Nuclear Fuels

Güngör Gündüz, İbrahım Uslu, Hasan H. Durmazuçar

Nuclear Technology / Volume 116 / Number 1 / October 1996 / Pages 78-90

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT96-A35313

Improvements in Boiling Water Reactor Uranium Utilization and Operating Experience with Burnup Increase

Takaaki Mochida, Katsumasa Haikawa, Jun-Ichi Yamashita, Akira Nishimura, Yutaka Iwata, Shiroh Arai

Nuclear Technology / Volume 116 / Number 1 / October 1996 / Pages 91-107

Technical Paper / Nuclear Fuel Cycle / dx.doi.org/10.13182/NT96-A35314

An Approach for Evaluating Equilibrium and Rate Constants for the Reaction of Np(V) with Nitric Acid in the Purex Process Using Process Data

Shunji Homma, Mitsuhiro Takanashi, Jiro Koga, Shiro Matsumoto, Masaki Ozawa

Nuclear Technology / Volume 116 / Number 1 / October 1996 / Pages 108-114

Technical Paper / Enrichment and Reprocessing System / dx.doi.org/10.13182/NT96-A35315

Preliminary Performance Assessment of the Engineered Barriers for a Low- and Intermediate-Level Radioactive Waste Repository

Won-Jin Cho, Jae-Owan Lee, Pil-Soo Hahn, Kwan-Sik Chun

Nuclear Technology / Volume 116 / Number 1 / October 1996 / Pages 115-126

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT96-A35316

Heat Removal Characteristics of a Primary Containment Vessel External Spray

Yoshiyuki Kataoka, Tadashi Fujii, Michio Murase

Nuclear Technology / Volume 116 / Number 1 / October 1996 / Pages 127-135

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT96-A35317

 

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