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Reactor Laboratory Experiments

Author: William J Sturm; Argonne National Laboratory.
Publisher: Argonne, Ill. : Argonne National Laboratory, International Institute Division, 1961.
Series: ANL (Series), 6410; Argonne National Laboratory., 6410.
Edition/Format:   Book : National government publication : EnglishView all editions and formats
Summary:
An exposition is presented comprising a basic set of experiments in reactor physics, engineering, and technology developed by the International Institute of Nuclear Science and Engineering. Twenty-three experiments are included in a program which may be divided into groups associated with the Argonaut Reactor, the AGN-201 Reactor, and with other reactors or auxiliary equipment.
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Additional Physical Format: Online version:
Reactor laboratory experiments.
Argonne, Ill. : Argonne National Laboratory, 1961
(OCoLC)603945888
Online version:
Reactor laboratory experiments.
Argonne, Ill. : Argonne National Laboratory, 1961
(OCoLC)609294283
Material Type: Government publication, National government publication
Document Type: Book
All Authors / Contributors: William J Sturm; Argonne National Laboratory.
OCLC Number: 757725999
Notes: "August 1961."
At head of title: Argonne National Laboratory.
"Operated by the University of Chicago under Contract W-31-109-eng-38."
Description: xvii, 430 p. : ill., tables ; 28 cm.
Contents: Preface. pp. iii. Experiment 1. Argonaut introduction and approach to critical. pp. 1. Experiment 2. An introduction to the AGN-201 reactor and an approach to critical. pp. 13. Experiment 3. Control and calibration. pp. 33. Experiment 4. Absorption cross section measurments by the danger coefficient method. pp. 57. Experiment 5. Temperature coefficient of reactivity. pp. 79. Experiment 6. Void coefficient of reactivity. pp. 101. Experiment 7. Reactivity importance function of neutron absorbers in a nuclear reactor. pp. 123. Experiment 8. Neutron flux measurement by induced activation methods. pp. 133. Experiment 9. Reactor power calibration. pp. 177. Experiment 10. Activation cross section. pp. 211. Experiment 11. Total neutron cross section. pp. 241. Experiment 12. Neutron temperature. pp. 280. Experiment 13. Measurement of the transfer function of the Argonaut. pp. 285. Experiment 14. Argonaut automatic flux controller. pp. 297. Experiment 15. Measurement of thermal neutron diffusion length in water. pp. 299. Experiment 16. Neutron age in water. pp. 317. Experiment 17. Resonance escape proabability. pp. 345. Experiment 18. Fast fission factor. pp. 359. Experiment 19. Determination of beta/l ratio for the Argonaut reactor by pile noise analysis. pp. 371. Experiment 20. Standard pile experiment. pp. 404. Experiment 21. Isotope production. pp. 411. Experiment 22. Analogue computer I. pp. 417. Experiment 23. Analogue computer II. pp. 423.
Series Title: ANL (Series), 6410; Argonne National Laboratory., 6410.
Responsibility: Edited by William J. Sturm.

Abstract:

An exposition is presented comprising a basic set of experiments in reactor physics, engineering, and technology developed by the International Institute of Nuclear Science and Engineering. Twenty-three experiments are included in a program which may be divided into groups associated with the Argonaut Reactor, the AGN-201 Reactor, and with other reactors or auxiliary equipment.

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schema:description"Experiment 12. Neutron temperature. pp. 280."
schema:description"Experiment 13. Measurement of the transfer function of the Argonaut. pp. 285."
schema:description"Experiment 14. Argonaut automatic flux controller. pp. 297."
schema:description"Experiment 16. Neutron age in water. pp. 317."
schema:description"Experiment 17. Resonance escape proabability. pp. 345."
schema:description"Experiment 19. Determination of beta/l ratio for the Argonaut reactor by pile noise analysis. pp. 371."
schema:description"Experiment 18. Fast fission factor. pp. 359."
schema:description"Experiment 4. Absorption cross section measurments by the danger coefficient method. pp. 57."
schema:description"Experiment 9. Reactor power calibration. pp. 177."
schema:description"Experiment 5. Temperature coefficient of reactivity. pp. 79."
schema:description"Experiment 1. Argonaut introduction and approach to critical. pp. 1."
schema:description"Experiment 20. Standard pile experiment. pp. 404."
schema:description"Experiment 15. Measurement of thermal neutron diffusion length in water. pp. 299."
schema:description"Experiment 7. Reactivity importance function of neutron absorbers in a nuclear reactor. pp. 123."
schema:description"Experiment 3. Control and calibration. pp. 33."
schema:description"Experiment 11. Total neutron cross section. pp. 241."
schema:description"Experiment 10. Activation cross section. pp. 211."
schema:description"Experiment 21. Isotope production. pp. 411."
schema:description"Experiment 8. Neutron flux measurement by induced activation methods. pp. 133."
schema:description"Experiment 6. Void coefficient of reactivity. pp. 101."
schema:description"Preface. pp. iii."
schema:description"Experiment 2. An introduction to the AGN-201 reactor and an approach to critical. pp. 13."
schema:description"Experiment 23. Analogue computer II. pp. 423."
schema:description"An exposition is presented comprising a basic set of experiments in reactor physics, engineering, and technology developed by the International Institute of Nuclear Science and Engineering. Twenty-three experiments are included in a program which may be divided into groups associated with the Argonaut Reactor, the AGN-201 Reactor, and with other reactors or auxiliary equipment."
schema:description"Experiment 22. Analogue computer I. pp. 417."
schema:inLanguage"en"
schema:name"Reactor Laboratory Experiments"
schema:numberOfPages"430"
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schema:name"Argonne National Laboratory, International Institute Division"
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