Published 2016 | Version v1
Miscellaneous Metadata-only

Modeling of excess reactivity transients in the SEALER lead-cooled reactor

Creators

  • 1. Canadian Nuclear Labs., Chalk River, ON (Canada)

Description

Modeling of the two hypothetical excess reactivity accidents was performed for the SEALER small lead-cooled reactor concept. The reactivity transient due to the leakage of steam from a steam generator to the core was analyzed using the SERPENT code. The ejection of the control rod assembly accident was modeled with the DONJON and DRAGON codes. The results of these two studies will be presented.

Part of:
Next generation small reactors and research reactors. 4. International Technical Meeting on Small Reactors (ITMSR-4)

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-25-4
Imprint Title
Next generation small reactors and research reactors. 4. International Technical Meeting on Small Reactors (ITSMR-4)
Imprint Pagination
50.1 Megabytes
Journal Page Range
[3 p.]

Conference

Title
4. International Technical Meeting on Small Reactors
Acronym
ITSMR-4
Dates
2-4 Nov 2016
Place
Ottawa, Ontario (Canada)

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
50005310
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
REACTIVITY COEFFICIENTS; REACTOR ACCIDENT SIMULATION; REACTOR OPERATION; REACTOR SAFETY; SMALL MODULAR REACTORS
Descriptors DEC
OPERATION; REACTOR LIFE CYCLE; REACTORS; SAFETY; SIMULATION

Optional Information

Notes
5 refs., 1 fig.