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Home / Publications / Journals / Nuclear Science and Engineering / Volume 97 / Number 1

Volume 97

Number 1

The Significance of Critical Experiments for Core Calculation and Design of High-Temperature Gas-Cooled Reactors Constructed on the Pebble-Bed Principle

R. Hecker, L. Wolf

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 1-8

Technical Paper / dx.doi.org/10.13182/NSE87-A23490

Treatment of the Upper Cavity in a Pebble-Bed High-Temperature Gas-Cooled Reactor by Diffusion Theory

H. Gerwin, W. Scherer

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 9-19

Technical Paper / dx.doi.org/10.13182/NSE87-A23491

Neutron Physical Investigations on the Shutdown Effect of Small Boronated Absorbing Spheres for Pebble-Bed High-Temperature Gas-Cooled Reactors

S. Sgouridis, F. Schürrer, Hj. Müller, W. Ninaus, K. Oswald, R. D. Neef, H. Schaal

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 20-29

Technical Paper / dx.doi.org/10.13182/NSE87-A23492

The Critical HTGR Test Facility KAHTER- An Experimental Program for Verification of Theoretical Models, Codes, and Nuclear Data Bases

V. Drüke, D. Filges

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 30-36

Technical Paper / dx.doi.org/10.13182/NSE87-A23493

Experiments on Inhömogeneous Fuel Loading at the Critical HTGR Test Facility KAHTER: A Study for the Future Loading Concept of Pebble-Bed Reactors

V. Drüke, D. Filges, R. D. Neef, N. Paul, H. Schaal

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 37-52

Technical Paper / dx.doi.org/10.13182/NSE87-A23494

Planning and Performance of Dynamic Experiments with the AVR Power Plant

M. Wimmers, P. Pohl

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 53-57

Technical Paper / dx.doi.org/10.13182/NSE87-A23495

Analysis of Reactivity and Temperature Transient Experiments at the AVR High-Temperature Reactor

W. Scherer, H. Gerwin, T. Kindt, W. Patscher

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 58-63

Technical Paper / dx.doi.org/10.13182/NSE87-A23496

Determination of the Hot- and Cold-Temperature Coefficient of Reactivity in the AVR Core

P. Pohl , M. Wimmers, T. Kindt, W. Feltes, U. Schmid, H. Jung

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 64-71

Technical Paper / dx.doi.org/10.13182/NSE87-A23497

Steady-State Neutrbnic Investigations to the Accident of Water Ingress in Systems with Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel

F. Schürrer, W. Ninaus, K. Oswald, R. Rabitsch, Hj. Müller, R. D. Neef

Nuclear Science and Engineering / Volume 97 / Number 1 / September 1987 / Pages 72-88

Technical Paper / dx.doi.org/10.13182/NSE87-A23498

 

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