HEAT TRANSFER FROM SPENT REACTOR FUELS DURING SHIPPING

HEAT TRANSFER FROM SPENT REACTOR FUELS DURING SHIPPING
Author:
Publisher:
Total Pages:
Release:
Genre:
ISBN:

A simple method is developed for calculating or predicting temperature distributions in spent reactor fuels in shipping casks. The method accounts for radiant heat transfer between all the individual pins in a square array. With the dimensions of the fuel bundle, the configuration factors for radiation between various tubes in the bundle can be obtained from the tabulated numerical calculations presented. The configuration factors, along with the heat generation rates, surface emissivity, and the temperature of the wall of the cask can be used to estimate the temperature distribution automatically with the computer code presented or possibly by hand calculations by the method outlined. Experimental measurements of temperature distribution in electrically heated tube arrays in steel shells that simulated shipping casks were made to test the proposed calculational procedure. Several heat generation rates and bundles containing up to 64 tubes were tested in 12-in.- and 6-in, -inner diameter shells. Tests were made with the casks in horizontal and vertical positions. The predicted temperatures were very near those observed experimentally under the conditions in which heat transfer is likely to be a problem in fuel shipment, that is, when the temperatures are near or above 200 c- C and the casks do not contain large empty spaces. These are the conditions where radiation should be expected to be the most important mechanism. The calculational method may also be adapted to nonsquare arrays. (auth).

An Experiment to Simulate the Heat Transfer Properties of a Dry, Horizontal Spent Nuclear Fuel Assembly

An Experiment to Simulate the Heat Transfer Properties of a Dry, Horizontal Spent Nuclear Fuel Assembly
Author: Phyllis Maria Lovett
Publisher:
Total Pages: 950
Release: 1991
Genre: Heat
ISBN:

Nuclear power reactors generate highly radioactive spent fuel assemblies. Initially, the spent fuel assemblies are stored for a period of several years in an on-site storage facility to allow the radioactivity levels of the assemblies to decay. As the radioactive fission product isotopes in the fuel decay, they generate significant amounts of thermal energy producing high temperatures in the spent fuel. The spent fuel from nuclear power plants will eventually have to be transferred to a federal geologic repository in a spent fuel transportation casks. The purpose of this research project is to characterize the relative importance of the heat transfer mechanisms of radiation, conduction, and convection in a dry horizontally-oriented nuclear spent fuel assembly, for eventual application in spent fuel transportation cask design. To determine the relative importance of each heat transfer mode, an experiment was designed and operated to characterize the heat transfer in an 8x8 square heater rod array (similar to a Boiling Water Reactor fuel assembly) in a horizontal orientation. The experimental apparatus was operated with the following variable parameters and their ranges: Power to Heater Rods (Controlling Temperatures from 40'C to 250'C); Heater Transfer Medium (Air, Nitrogen, Argon, and Helium); Pressure of the Heat Transfer Medium (15 psig, 0 psig, 24 inches of mercury); Power to Boundary Condition Box (not controlled). The experiment was designed, fabricated, and operated under the Sandia National Laboratories-approved MIT Nuclear Engineering Department Quality Assurance Program developed in this work specifically for this project. The test data obtained from the experimental apparatus was analyzed with the lumped keff/hedge model developed by R.D. Manteufel at MIT, in related work on this research project, and the Wooten-Epstein relationship developed at Battelle Memorial Institute. The test data was used to validate the lumped keff/hedge model. Good agreement was found between the lumped keff/hedge model and the test data in each Test Campaign with the exception of Below Atmospheric Pressure data. Both experimental and theoretical sources for the discrepancy are discussed. However, the full reason for the deviation is not know.

Going the Distance?

Going the Distance?
Author: National Research Council
Publisher: National Academies Press
Total Pages: 355
Release: 2006-06-21
Genre: Science
ISBN: 0309164826

This new report from the National Research Council's Nuclear and Radiation Studies Board (NRSB) and the Transportation Research Board reviews the risks and technical and societal concerns for the transport of spent nuclear fuel and high-level radioactive waste in the United States. Shipments are expected to increase as the U.S. Department of Energy opens a repository for spent fuel and high-level waste at Yucca Mountain, and the commercial nuclear industry considers constructing a facility in Utah for temporary storage of spent fuel from some of its nuclear waste plants. The report concludes that there are no fundamental technical barriers to the safe transport of spent nuclear fuel and high-level radioactive and the radiological risks of transport are well understood and generally low. However, there are a number of challenges that must be addressed before large-quantity shipping programs can be implemented successfully. Among these are managing "social" risks. The report does not provide an examination of the security of shipments against malevolent acts but recommends that such an examination be carried out.

Going the Distance?

Going the Distance?
Author: National Research Council
Publisher: National Academies Press
Total Pages: 355
Release: 2006-07-21
Genre: Science
ISBN: 0309100046

This new report from the National Research Council's Nuclear and Radiation Studies Board (NRSB) and the Transportation Research Board reviews the risks and technical and societal concerns for the transport of spent nuclear fuel and high-level radioactive waste in the United States. Shipments are expected to increase as the U.S. Department of Energy opens a repository for spent fuel and high-level waste at Yucca Mountain, and the commercial nuclear industry considers constructing a facility in Utah for temporary storage of spent fuel from some of its nuclear waste plants. The report concludes that there are no fundamental technical barriers to the safe transport of spent nuclear fuel and high-level radioactive and the radiological risks of transport are well understood and generally low. However, there are a number of challenges that must be addressed before large-quantity shipping programs can be implemented successfully. Among these are managing "social" risks. The report does not provide an examination of the security of shipments against malevolent acts but recommends that such an examination be carried out.