Published 1994 | Version v1
Report Open

Thermomechanical analysis of fast-burst reactors

Description

Fast-burst reactors are designed to provide intense, short-duration pulses of neutrons. The fission reaction also produces extreme time-dependent heating of the nuclear fuel. An existing transient-dynamic finite element code was modified specifically to compute the time-dependent stresses and displacements due to thermal shock loads of reactors. Thermomechanical analysis was then applied to determine structural feasibility of various concepts for an EDNA-type reactor and to optimize the mechanical design of the new SPR III-M reactor

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE94016563; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
SAND--94-0761C

Conference

Title
Physics, safety and applications of pulse reactors.
Dates
13-17 Nov 1994.
Place
Washington, DC (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
26033960
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; FINITE ELEMENT METHOD; MECHANICAL PROPERTIES; P CODES; PULSED REACTORS; REACTOR OPERATION; REACTOR SAFETY; THERMAL ANALYSIS; THERMAL SHOCK
Descriptors DEC
CALCULATION METHODS; COMPUTER CODES; NUMERICAL SOLUTION; OPERATION; REACTORS; SAFETY

Optional Information

Contract/Grant/Project number
Contract AC04-94AL85000
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-941141--3.