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Title: Neutron fluxes in test reactors

Abstract

Communicate the fact that high-power water-cooled test reactors such as the Advanced Test Reactor (ATR), the High Flux Isotope Reactor (HFIR) or the Jules Horowitz Reactor (JHR) cannot provide fast flux levels as high as sodium-cooled fast test reactors. The memo first presents some basics physics considerations about neutron fluxes in test reactors and then uses ATR, HFIR and JHR as an illustration of the performance of modern high-power water-cooled test reactors.

Authors:
 [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1369358
Report Number(s):
INL/EXT-17-40962
TRN: US1701954
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HFIR REACTOR; NEUTRON FLUX; JULES HOROWITZ REACTOR; ATR REACTOR; neutron fluxes; test reactors

Citation Formats

Youinou, Gilles Jean-Michel. Neutron fluxes in test reactors. United States: N. p., 2017. Web. doi:10.2172/1369358.
Youinou, Gilles Jean-Michel. Neutron fluxes in test reactors. United States. doi:10.2172/1369358.
Youinou, Gilles Jean-Michel. Sun . "Neutron fluxes in test reactors". United States. doi:10.2172/1369358. https://www.osti.gov/servlets/purl/1369358.
@article{osti_1369358,
title = {Neutron fluxes in test reactors},
author = {Youinou, Gilles Jean-Michel},
abstractNote = {Communicate the fact that high-power water-cooled test reactors such as the Advanced Test Reactor (ATR), the High Flux Isotope Reactor (HFIR) or the Jules Horowitz Reactor (JHR) cannot provide fast flux levels as high as sodium-cooled fast test reactors. The memo first presents some basics physics considerations about neutron fluxes in test reactors and then uses ATR, HFIR and JHR as an illustration of the performance of modern high-power water-cooled test reactors.},
doi = {10.2172/1369358},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 2017},
month = {Sun Jan 01 00:00:00 EST 2017}
}

Technical Report:

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  • The highest thermal-neutron fluxes obtainable from fission reactors, if limits are placed on the power density or total power, are investigated. Two cases are studied: a homogeneous reactor and a flux trap'' reactor. The flux- trap reactor consists of a reactor with a moderator-filled cavity nt the center. Emphasis is placed on the fundamental principles and limitations rather than on engineering and design. (M.H.R.)
  • The results of a multi-group, diffusion type code computation for the fast neutron flux distribution in C, K, and N reactors are presented. Relative Ni activations in conjunction with the calculated neutron spectra are used to obtain values for the integrated fast flux per MWD/AT for C and K reactors. The relative, theoretical, integrated fast flux values at the same adjacent fuel powers in C, K, and N reactors in the mid-plane of the filler layers are: (1) C = 1.0; (2) K = 1.3; and (3) N = 2.6. For C reactor, the best estimate of the integrated fastmore » flux per MWD/AT is: 5.0 {times} 10{sup 16} nvt (> 1 MeV) = 1 MWD/AT.« less
  • Some of the results of reactor analyses on the Westinghouse Test Reactor are presented. A study to determine the optimum thimble material for WTR was performed. The study included a determination of thermal neutron flux within the thimble for various materials and various thimble contents. The analysis also included the effects of gamma heating and a study of thermal stresses resulting from gamma heating. (W.D.M.)
  • This report describes a series of neutron flux measurements made in order to obtain a relationship between the flux observed at the inner surface of the shield and local fringe tube power; this correlation would be expected to be more valid than that with total pile power level. The facility used for these measurements, the E test facility at the F Pile, is one which is very useful for pile irradiation of small samples provided temperature control does not have to be maintained. Both long and short term exposures may be made as samples may be charged and discharged frommore » the externally shielded facility during operation.« less