Monte Carlo Simulation of the Massachusetts Institute of Technology Research Reactor-Reference-Cited by-同舟云学术

Monte Carlo Simulation of the Massachusetts Institute of Technology Research Reactor

Published:1994-04 Issue:1 Volume:106 Page:1-14
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Redmond Everett L.¹,Yanch Jacquelyn C.¹,Harling Otto K.¹

Affiliation:

1. Massachusetts Institute of Technology Nuclear Engineering Department and Nuclear Reactor Laboratory Cambridge, Massachusetts 02139

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/NT94-A34946

Reference11 articles.

1. T. B. FOWLER, D. R. VONDY, and G. W. CUNNINGHAM, “Nuclear Reactor Core Analysis Code: CITATION,” ORNL-TM-2496, Rev. 2, Oak Ridge National Laboratory (1971).

2. J. A. BERNARD, Jr. “MITR-II Fuel Management, Core Depletion, and Analysis: Codes Developed for the Diffusion Theory Program CITATION,” Master’s Thesis, Massachusetts Institute of Technology (1979).

3. “MCNP-A General Monte Carlo Code for Neutron and Photon Transport (Version 3A),” LA-7396-M, Rev. 2, J. F. BRIESMEISTER, Ed. Los Alamos National Laboratory (1986).

4. D. J. WHALEN, D. A. CARDON, J. L. UHLE, and J. S. HENDRICKS, “MCNP: Neutron Benchmark Problems,” LA-12212, Los Alamos National Laboratory (1991).

5. D. J. WHALEN, D. E. HOLLOWELL, and J. S. HENDRICKS, “MCNP: Photon Benchmark Problems,” LA-12196, Los Alamos National Laboratory (1991).

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