Neutron Environment Characterization of the Central Cavity in the Annular Core Research Reactor *-Reference-Cited by-同舟云学术

Neutron Environment Characterization of the Central Cavity in the Annular Core Research Reactor *

Published:2016 Issue: Volume:106 Page:01003
ISSN:2100-014X
Container-title:EPJ Web of Conferences
language:
Short-container-title:EPJ Web of Conferences

Author:

Parma Edward J.,Naranjo Gerald E.,Lippert Lance L.,Vehar David W.

Publisher

EDP Sciences

Link

http://www.epj-conferences.org/10.1051/epjconf/201610601003/pdf

Reference9 articles.

1. MCNP-A General Monte Carlo N-Particle Transport Code, Version 5, Technical Report LA-UR-03-1987 (2003)

2. DePriest K. R., Cooper P. J., Edward Parma J., “MCNP/MCNPX Model of the Annular Core Research Reactor”, Technical Report SAND2006-3067 (2006)

3. Stallmann F. W., “LSL-M2: A Computer Program for Least-Squares Logarithmic Adjustment of Neutron Spectra”, Technical Report NUREG/CR-4349, ORNL/TM-9933 (1985)

4. ASTM E720-11, “Standard Guide for Selection and Use of Neutron Sensors for Determining Neutron Spectra Employed in Radiation-Hardness Testing of Electronics”, ASTM Int. (2011)

5. Griffin P. J., Luker M. S., Cooper P. J., Vehar D. W., DePriest K. R., Holm C. V., “Characterization of ACRR Reference Benchmark Field”, 11thInternational Symposium on Reactor Dosimetry (2002)

Cited by 3 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. SCALE modeling of foil irradiations at WSU’s TRIGA with sensitivity/uncertainty analysis;Journal of Radioanalytical and Nuclear Chemistry;2022-10-29

2. Evaluation of the 23Na(N,Gamma) Reaction Cross Section;Reactor Dosimetry: 16th International Symposium;2018-11-01

3. Neutron and Gamma-Ray Radiation Environments for the Annular Core Research Reactor;AM SOC TEST MATER;2018