Criticality safety analysis using continuous energy libraries of MCNP code
by Jean A.D. Salomé; Claubia Pereira; Jonathan B.A. Assunção
International Journal of Nuclear Energy Science and Technology (IJNEST), Vol. 9, No. 4, 2015

Abstract: The study of subcritical and critical systems is useful to guide decisions about design, installation and operation of some devices, mainly nuclear reactors and power plants. The information generated by these systems guides the best decisions to be made in executive project, economic viability and the safety measures to be employed in a nuclear facility. Simulating some experiments from the International Handbook of Evaluated Criticality Safety Benchmark Experiments, the MCNP5 code has been validated as an important tool to make an analysis about nuclear criticality safety. Its continuous libraries have been used. The average values and the standard deviation (SD) are evaluated. The results are very close to the values obtained by the benchmark experiments and in agreement with the criticality safety limits required by the Brazilian authorities.

Online publication date: Thu, 24-Mar-2016

The full text of this article is only available to individual subscribers or to users at subscribing institutions.

 
Existing subscribers:
Go to Inderscience Online Journals to access the Full Text of this article.

Pay per view:
If you are not a subscriber and you just want to read the full contents of this article, buy online access here.

Complimentary Subscribers, Editors or Members of the Editorial Board of the International Journal of Nuclear Energy Science and Technology (IJNEST):
Login with your Inderscience username and password:

    Username:        Password:         

Forgotten your password?


Want to subscribe?
A subscription gives you complete access to all articles in the current issue, as well as to all articles in the previous three years (where applicable). See our Orders page to subscribe.

If you still need assistance, please email subs@inderscience.com