Nuclear Materials for Fission Reactors
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Published By Elsevier

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Development of the thermal behavior analysis code DIRAD and the fuel design procedure for LMFBR

Nuclear Materials for Fission Reactors ◽

10.1016/b978-0-444-89571-4.50052-9 ◽

1992 ◽

pp. 331-336

Author(s):

N. Nakae ◽

K. Tanaka ◽

H. Nakajima ◽

M. Matsumoto

Keyword(s):

Thermal Behavior ◽

Behavior Analysis ◽

Design Procedure ◽

Fuel Design

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Investigation of nuclear mixed oxide fuel–gas interaction by a solid electrolyte based coulometric technique

Nuclear Materials for Fission Reactors ◽

10.1016/b978-0-444-89571-4.50035-9 ◽

1992 ◽

pp. 226-231

Author(s):

K. Teske ◽

C. Nebelung ◽

H. Ullman ◽

I.I. Kapshukov ◽

L.V. Sudakov ◽

...

Keyword(s):

Solid Electrolyte ◽

Mixed Oxide ◽

Oxide Fuel ◽

Fuel Gas ◽

Mixed Oxide Fuel

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Failure behavior of plutonium–uranium mixed oxide fuel under reactivity-initiated accident condition

Nuclear Materials for Fission Reactors ◽

10.1016/b978-0-444-89571-4.50023-2 ◽

1992 ◽

pp. 154-161

Author(s):

T. Abe ◽

N. Nakae ◽

K. Kodato ◽

M. Matsumoto ◽

T. Inabe

Keyword(s):

Mixed Oxide ◽

Failure Behavior ◽

Oxide Fuel ◽

Mixed Oxide Fuel ◽

Accident Condition

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Fuel performance under normal PWR conditions: A review of relevant experimental results and models

Nuclear Materials for Fission Reactors ◽

10.1016/b978-0-444-89571-4.50018-9 ◽

1992 ◽

pp. 96-103

Author(s):

M. Charles ◽

C. Lemaignan

Keyword(s):

Experimental Results ◽

Fuel Performance

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Concerning the microstructure changes that occur at the surface of UO2 pellets on irradiation to high burnup

Nuclear Materials for Fission Reactors ◽

10.1016/b978-0-444-89571-4.50015-3 ◽

1992 ◽

pp. 73-79 ◽

Cited By ~ 1

Author(s):

C.T. Walker ◽

T. Kameyama ◽

S. Kitajima ◽

M. Kinoshita

Keyword(s):

Microstructure Changes ◽

High Burnup

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Irradiation of a 19 pin subassembly with mixed carbide fuel in KNK II

Nuclear Materials for Fission Reactors ◽

10.1016/b978-0-444-89571-4.50011-6 ◽

1992 ◽

pp. 43-48

Author(s):

D. Geithoff ◽

G. Mühling ◽

K. Richter

Keyword(s):

Carbide Fuel

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Mechanism and kinetics of the uranium–plutonium mononitride synthesis

Nuclear Materials for Fission Reactors ◽

10.1016/b978-0-444-89571-4.50010-4 ◽

1992 ◽

pp. 36-42

Author(s):

Philippe Bardelle ◽

Dominique Warin

Keyword(s):

Mechanism And Kinetics ◽

Uranium Plutonium ◽

Kinetics Of

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Supporting Organizations and Sponsors

Nuclear Materials for Fission Reactors ◽

10.1016/b978-0-444-89571-4.50005-0 ◽

1992 ◽

pp. viii

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Preface

Nuclear Materials for Fission Reactors ◽

10.1016/b978-0-444-89571-4.50004-9 ◽

1992 ◽

pp. vii

Author(s):

Hj. Matzke ◽

G. Schumacher

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Front Matter

Nuclear Materials for Fission Reactors ◽

10.1016/b978-0-444-89571-4.50002-5 ◽

1992 ◽

pp. iii

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