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Title: Core design and safety studies for a small modular fast reactor.


No abstract prepared.

; ; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
OSTI Identifier:
Report Number(s):
TRN: US0805981
DOE Contract Number:
Resource Type:
Resource Relation:
Conference: PHYSOR 2006 - American Nuclear Society Topical Meeting on Reactor Physics; Sep. 10, 2006 - Sep. 14, 2006; Vancouver, Canada
Country of Publication:
United States

Citation Formats

Yang, W.-S., Cahalan, J. E., Dunn, F. E., and Nuclear Engineering Division. Core design and safety studies for a small modular fast reactor.. United States: N. p., 2006. Web.
Yang, W.-S., Cahalan, J. E., Dunn, F. E., & Nuclear Engineering Division. Core design and safety studies for a small modular fast reactor.. United States.
Yang, W.-S., Cahalan, J. E., Dunn, F. E., and Nuclear Engineering Division. Sun . "Core design and safety studies for a small modular fast reactor.". United States. doi:.
title = {Core design and safety studies for a small modular fast reactor.},
author = {Yang, W.-S. and Cahalan, J. E. and Dunn, F. E. and Nuclear Engineering Division},
abstractNote = {No abstract prepared.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 2006},
month = {Sun Jan 01 00:00:00 EST 2006}

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  • The paper describes the core design and performance characteristics and the safety analysis results for a 50 MWe small modular fast reactor design that was developed jointly by ANL, CEA, and JNC as an international collaborative effort. The main goal in the core design was to achieve a 30-year lifetime with no refueling. In order to minimize the burnup reactivity swing, metal fuel with a high heavy metal volume fraction was selected. To enhance the proliferation resistance and actinide transmutation, all the transuranic (TRU) elements recovered from light water reactor spent fuel were used in a ternary alloy form ofmore » U-TRU-10Zr. A 125 MWt core design was developed, for which the burnup reactivity swing was only 1.6$ over the 30-year core lifetime. The average discharge burnup was 87 MWd/kg, and the maximum sodium void worth was 4.65$. The evaluated reactivity coefficients provided sufficient negative feedbacks. Shutdown margins of control systems were confirmed. Steady-state thermal-hydraulic analysis results showed that peak 2{sigma} cladding inner-wall and fuel centerline temperatures were less than design limits with sufficient margins. Detailed transient analyses for the total loss of power to reactor and intermediate coolant pumps showed that no fuel damage or cladding failure would occur, even when multiple safety systems were assumed to malfunction. (authors)« less
  • No abstract prepared.
  • The safety of the demonstration fast breeder reactor is being pursued, two independent reactor shutdown systems are installed. A passive system for rapid insertion of negative reactivity especially against Unprotected Loss of Flow events, the Gas Expansion Module (GEM), has been studied as one of means for a further enhancement of safety. 4 refs., 6 figs.
  • In certain fast-reactor designs, the core is an assemblage of a large number of containers of long, hexagonal, hollow cylinders mounted vertically. These so-called hex-cans sit individually on coolant nozzles held down by their own weight, and are held as a group laterally at two levels by two constraint rings. In the analysis, it is observed that the large number of hex-cans and the distribution of the temperature field are such that the cross section of the reactor core can be treated as in a locally uniform dilatational field. An approximate equation was developed relating the plane deformation of amore » hollow hex cylinder to the global lateral pressure. The cylinder constitutive equation is then used to determine an equivalent stiffness for a solid hex cylinder that is to have the same deformation as the given hex-can. The entire planar core region is then analyzed as a homogeneous medium of the equivalent stiffness. The method was applied to the core confinement design for a fast reactor. The thermoelastic solution was then applied to a relatively simpler configuration than the actual case to give a measure of the lateral pressure.« less