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Re-evaluations for SINBAD Experiments Using ENDF/B-VII, JEFF-3.1, and JENDL-3.3

Title
Re-evaluations for SINBAD Experiments Using ENDF/B-VII, JEFF-3.1, and JENDL-3.3
Other Titles
B-VII, JEFF-3.1, and JENDL-3.3
Author
김종경
Keywords
Reactor shielding; Fusion neutronics; Accelerator shielding; MCNPX; ENDF/B-VII; JEFF-3.1; JENDL-3.3
Issue Date
2011-08
Publisher
Korean Physical SOC
Citation
Journal of the Korean Physical Society, 2011, 59(2), P.1187-1190
Abstract
SINBAD (Shielding Integral Benchmark Archive Database) started in 1996 as a joint project of the OECD/NEA Data Bank (Organization for Economic Cooperation and Development, Nuclear Energy Agency Data Bank) and ORNL/RSICC (Oak Ridge National Laboratory, Radiation Safety Information Computational Center). It contains a variety of experiments concerning reactor shielding, fusion blanket neutronics, and accelerator shielding that are useful to verify and validate radiation shielding codes as well as nuclear data libraries. In this work, re-evaluation of SINBAD experiments has been conducted by using the MCNPX code with recently released nuclear data libraries, ENDF/B-VII, JEFF-3.1, and JENDL-3.3. The MCNPX calculations for several typical problems of SINBAD reactor shielding, fusion neutronics, and accelerator shielding were carried out and validated through comparing with available experimental data. It is found that there was reasonable agreement between the calculational and experimental results. Hence, ENDF/B-VII, JEFF-3.1, and JENDL-3.3 are strongly recommended to be used for validating the new developed radiation shielding methods and codes.
URI
http://www.jkps.or.kr/journal/view.html?volume=59&number=2(3)&spage=1187&year=2011http://hdl.handle.net/20.500.11754/66689
ISSN
0374-4884; 1976-8524
DOI
10.3938/jkps.59.1187
Appears in Collections:
COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
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