Published May 2020 | Version v1
Book Metadata-only

Management of the storage and transportation of PWR spent fuel cask in normal and accident condition

Creators

  • 1. Nuclear and Radiological Regulatory Authority, Cairo (Egypt)

Description

MCNPX computer code is used to model the general cask GBC-32 which contain 32 typical PWR spent fuel assemblies. For Safe storage and transportation of the cask, factors that affect the criticality were studied using the concept of burn up credit. Several parameters such as initial fuel enrichment, fuel burnup, cooling time, and axial burnup profile were analysed. The analysis was performed in two different steps, first burn the fuel assembly at different burnup and storage conditions, secondly, incorporate the details of the assemblies into the cask and perform a criticality calculations for the cask. Several cases of unnormal storage conditions are considered. The results are compared with similar GBC-32 benchmark. (author)

Part of:
Management of Spent Fuel from Nuclear Power Reactors: Learning from the Past, Enabling the Future. Proceedings of an International Conference

Additional details

Identifiers

URL
https://www.iaea.org/publications/14680/management-of-spent-fuel-from-nuclear-power-reactors?supplementary=82942; http://www.iaea.org/books;

Publishing Information

Publisher
IAEA
Imprint Place
Vienna (International Atomic Energy Agency (IAEA))
ISBN
978-92-0-108620-4
Imprint Title
Management of Spent Fuel from Nuclear Power Reactors: Learning from the Past, Enabling the Future. Proceedings of an International Conference
Imprint Pagination
[1 CD-ROM]
Series
Proceedings Series
Journal Page Range
9 p.
ISSN
0074-1884

Conference

Title
Learning from the past, enabling the future
Acronym
International conference on management of spent fuel from nuclear power reactors
Dates
24-28 Jun 2019
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
51073794
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCHMARKS; BURNUP; COMPUTER CODES; COOLING TIME; CRITICALITY; ENRICHMENT; FUEL ASSEMBLIES; MONTE CARLO METHOD; PWR TYPE REACTORS; SPENT FUEL CASKS; SPENT FUEL STORAGE; SPENT FUELS; WASTE TRANSPORTATION
Descriptors DEC
CALCULATION METHODS; CASKS; CONTAINERS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MANAGEMENT; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; STORAGE; THERMAL REACTORS; WASTE MANAGEMENT; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
9 refs., 7 figs., 8 tabs.
Secondary number(s)
IAEA-CN--272/67