Neutron Fluence at the Pressure Vessel of a Pressurized Water Reactor Determined by the MCNP Code-Reference-Cited by-同舟云学术

Neutron Fluence at the Pressure Vessel of a Pressurized Water Reactor Determined by the MCNP Code

Published:1995-12 Issue:3 Volume:121 Page:433-447
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Laky Peter G.¹,Tsoulfanidis Nicholas¹

Affiliation:

1. University of Missouri-Rolla, Nuclear Engineering Department, Rolla, Missouri 65401

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE95-A24145

Reference16 articles.

1. A Comparison of the BUGLE-80, SAILOR, and ELXSIR Neutron Cross-Section Libraries for PWR Pressure Vessel Surveillance Dosimetry and Shielding Applications

2. PDQ-7 REFERENCE MANUAL.

3. R. JUNG, R. S. DENNINGS, and M.P. MANAHAN, “The Development of Pre and Post Transport Analysis Codes: PINPOW, FMAT, and FLUX3DSYN,” Internal Report, Battelle Memorial Institute (Oct. 1983).

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