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Title: Deformation of the Sandia metallic ring seal test fixture. [LMFBR spent fuel casks]

Abstract

A fixture being used at Sandia Laboratories Albuquerque for testing a metallic ring-type seal is described and analyzed. Formulas for the deformation of the fixture are derived based on a simple mathematical model. Numerical results are presented for a set of parameters typical of an actual test. The seal is applicable to LMFBR spent fuel shipping casks.

Authors:
Publication Date:
Research Org.:
Sandia Labs., Albuquerque, NM (USA)
OSTI Identifier:
6513542
Report Number(s):
SAND-78-2191
TRN: 79-005588
DOE Contract Number:
EY-76-C-04-0789
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
42 ENGINEERING; SEALS; TEST FACILITIES; SPENT FUEL CASKS; DEFORMATION; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; BREEDER REACTORS; CASKS; CONTAINERS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTORS; 420204* - Engineering- Shipping Containers

Citation Formats

Sagartz, M.J. Deformation of the Sandia metallic ring seal test fixture. [LMFBR spent fuel casks]. United States: N. p., 1979. Web. doi:10.2172/6513542.
Sagartz, M.J. Deformation of the Sandia metallic ring seal test fixture. [LMFBR spent fuel casks]. United States. doi:10.2172/6513542.
Sagartz, M.J. Mon . "Deformation of the Sandia metallic ring seal test fixture. [LMFBR spent fuel casks]". United States. doi:10.2172/6513542. https://www.osti.gov/servlets/purl/6513542.
@article{osti_6513542,
title = {Deformation of the Sandia metallic ring seal test fixture. [LMFBR spent fuel casks]},
author = {Sagartz, M.J.},
abstractNote = {A fixture being used at Sandia Laboratories Albuquerque for testing a metallic ring-type seal is described and analyzed. Formulas for the deformation of the fixture are derived based on a simple mathematical model. Numerical results are presented for a set of parameters typical of an actual test. The seal is applicable to LMFBR spent fuel shipping casks.},
doi = {10.2172/6513542},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 1979},
month = {Mon Jan 01 00:00:00 EST 1979}
}

Technical Report:

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  • A spent-fuel shipping cask for use at both the Fast Flux Test Facility (FFTF) and the Clinch River Breeder Reactor Plant (CRBRP) is being developed. In compliance with milestones established for the Sandia Labs LMFBR spent-fuel shipping activity, conceptual designs of an LMFBR shipping cask are described. The detailed design based on one of the concepts will commence after review and comments have been received from the cognizant organizations. Conceptual designs described in this document comply with the shipping system requirements as defined in the LMFBR Spent-Fuel Shipping System Design Description. Additional considerations which have affected the conceptual designs currentlymore » being used are: (1) the rotating basket option has been excluded; (2) spent fuel must be adequately cooled during loading and unloading in a one-atmosphere argon environment; (3) passive cooling of the cask during shipment is required; (4) six-month cooled CRBRP fuel prescribes the radiation and thermal source; and (5) the shipping cask will be transported by rail. Heat transfer requirements during loading and unloading will substantially impact the shipping system. Spent-fuel assemblies may be placed in canisters containing a non-gaseous coolant prior to shipment or may be shipped bare subject to certain loading and cooling restrictions. The recommended option is to place a liquid metal in the canister and then insert the fuel assembly.« less
  • Three-dimensional Monte Carlo criticality calculations have been performed with KENO IV on two types of LMFBR subassemblies placed in configurations considered appropriate for shipping-cask applications. The report presents the effects of geometry, coolant, and loading changes--along with shield/structure material selection--on the self-multiplication of such systems. An example is shown which permits the determination of the maximum payload of CRBR fuel allowed under specified limits for k/sub eff/. Fuel enrichment, number of subassemblies, and type of coolant used are generally the most sensitive variables affecting self-multiplication. Of lesser importance are the type of gamma shield used and the pitch between subassemblies;more » the choice of neutron-shield material and outer case structure are of least importance. The correlations presented are expected to be useful in making decisions related to shipping-cask designs.« less
  • This report describes the analysis and experimental evaluation of a device to provide fire protection for a shipping cask used to transport liquid metal fast breeder reactor (LMFBR) fuel rods. Thermal analyses of various fire protection schemes were conducted by means of the finite difference code, CINDA. The choice of materials for the cask body was determined to be less important than the dimensions and number of cooling fins attached to the cask. Of several protection methods considered, radiation/convection shields between the cooling fins looked most attractive; these were tested on a quarter-scale cask model. The shields consisted of bimetallicmore » bands which expanded when heated, blocking the fire, and retracted when cooled. This automatic reversibility would allow the fins to dissipate internally generated heat of a full-size cask once the fire was out. Tests showed that, even in an asymmetric fire exposure, the bands expanded to provide protection to the cask. The directly exposed surface of the cask model, protected this way, reached a temperature of only 180/sup 0/C compared with 295/sup 0/C in the unprotected state, when subjected to a butane flame for 0.5 h at a distance of 15 cm. Greater relative effectiveness could be expected in an engulfing fire in which the bands would expand more symmetrically.« less
  • Possible designs of LMFBR spent fuel shipping cask energy mitigators (impact limiters) with reference to what has been done in previous large shipping casks subject to the requirement arising from LMFBR spent fuel are discussed. (TFD)
  • The Cask Standard Review Plan (CSRP) has been prepared as guidance to be used in the review of Cask Safety Analysis Reports (CSARs) for storage packages. The principal purpose of the CSRP is to assure the quality and uniformity of storage cask reviews and to present a well-defined base from which to evaluate proposed changes in the scope and requirements of reviews. The CSRP also sets forth solutions and approaches determined to be acceptable in the past by the NRC staff in dealing with a specific safety issue or safety-related design area. These solutions and approaches are presented in thismore » form so that reviewers can take consistent and well-understood positions as the same safety issues arise in future cases. An applicant submitting a CSAR does not have to follow the solutions or approaches presented in the CSRP. However, applicants should recognize that the NRC staff has spent substantial time and effort in reviewing and developing their positions for the issues. A corresponding amount of time and effort will probably be required to review and accept new or different solutions and approaches.« less