Monte Carlo Transport Calculations and Analysis for Reactor Pressure Vessel Neutron Fluence-Reference-Cited by-同舟云学术

Monte Carlo Transport Calculations and Analysis for Reactor Pressure Vessel Neutron Fluence

Published:1996-06 Issue:3 Volume:114 Page:373-398
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Wagner John C.¹,Haghighat Alireza¹,Petrovic Bojan G.¹

Affiliation:

1. The Pennsylvania State University Nuclear Engineering Department, 231 Sackett Building University Park, Pennsylvania 16802

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/NT96-A35241

Reference24 articles.

1. “MCNP-A General Monte Carlo N-Particle Transport Code, Version 4A,” LA-12625, J. F. BRIESMEISTER, Ed. Los Alamos National Laboratory (1993).

2. W. A. RHOADES and R. L. CHILDS, “The DORT Two-Dimensional Discrete Ordinates Transport Code System,” RSIC-CCC-484, Oak Ridge National Laboratory, Radiation Shielding Information Center (1989).

3. LEPRICON Analysis of Pressure Vessel Surveillance Dosimetry Inserted into H. B. Robinson-2 during Cycle 9

4. Calculation of neutron fluence in the region of the pressure vessel for the history of different reactors by using the Monte-Carlo-method

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