Space-Time Neutronic Analysis of Postulated Loss-of-Coolant Accidents in CANDU Reactors-Reference-Cited by-同舟云学术

Space-Time Neutronic Analysis of Postulated Loss-of-Coolant Accidents in CANDU Reactors

Published:1979-12 Issue:3 Volume:46 Page:507-516
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Luxat J. C.¹,Frescura G. M.¹

Affiliation:

1. Ontario Hydro, Nuclear Studies and Safety Department, Design and Development Division, 700 University Avenue, Toronto, Ontario M5G 1X6 Canada

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT79-A32359

Reference6 articles.

1. Accuracy of the Quasistatic Treatment of Spatial Reactor Kinetics

2. CANDU Reactor Kinetics Benchmark Activity

3. L. K. VOLODKA, “PROGRAM MOVER: Point Kinetics Algorithm,” ANL-7310, Reactor Physics Division Annual Report, Argonne National Laboratory (1966-1967).

4. Application of the Natural Mode Approximation to Space-Time Reactor Problems

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