Published 1995 | Version v1
Report Open

Issues related to criticality safety analysis for burnup credit applications

Creators

Description

Spent fuel transportation and storage cask designs based on a burnup credit approach must consider issues that are not relevant in casks designed under a fresh fuel loading assumption. Parametric analyses are required to characterize the importance of fuel assembly and fuel cycle parameters on spent fuel composition and reactivity. Numerical models are evaluated to determine the sensitivity of criticality safety calculations to modeling assumptions. This paper discusses the results of studies to determine the effect of two important modeling assumptions on the criticality analysis of pressurized-water reactor (PWR) spent fuel: (1) the effect of assumed burnup history (i.e., specific power during and time-dependent variations in operational power) during depletion calculations, and (2) the effect of axial burnup distributions on the neutron multiplication factor calculated for a three-dimensional (3-D) conceptual cask design

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE96003018; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
15 p.
Report number
CONF-9509100--35

Conference

Title
5. international conference on nuclear criticality safety.
Dates
17-22 Sep 1995.
Place
Albuquerque, NM (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27041451
Subject category
S42: ENGINEERING; S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; CRITICALITY; DESIGN; FUEL ASSEMBLIES; PWR TYPE REACTORS; REACTIVITY; SAFETY ANALYSIS; SPENT FUEL CASKS; SPENT FUELS
Descriptors DEC
CASKS; CONTAINERS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract AC05-84OR21400
Funding organization
USDOE, Washington, DC (United States).