Published 1990 | Version v1
Book

MELCOR adaptation and validation for modeling of N reactor core phenomena

  • 1. Sandia National Labs., Albuquerque, NM (United States). Reactor Systems Test and Analysis Dept.

Description

MELCOR has been adapted for use in modeling the N Reactor core as a part of the recently completed N Reactor probabilistic risk assessment. Significant adaptation of MELCOR was required because of the horizontal, water cooled, graphite-moderated nature of the N Reactor core. The generation and verification of the revised N Reactor core model are described in this paper. A hydrogen production and core damage benchmark calculation is presented in which all significant parameters calculated by MELCOR agreed with those in the reference calculation to within approximately 10%. The reference calculation required many CRAY CPU hours, while the MELCOR calculation was completed in less than 20 CPU minutes on a VAX 8700

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (United States)
Imprint Title
The safety, status and future of non-commercial reactors and irradiation facilities
Imprint Pagination
830 p.
Journal Page Range
p. 120-130.

Conference

Title
American Nuclear Society (ANS) topical meeting on the safety, status and future of non-commercial reactors and irradiation facilities.
Dates
30 Sep - 4 Oct 1990.
Place
Boise, ID (United States).

Optional Information

Secondary number(s)
CONF-900917--.