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Title: NEUTRONIC REACTORS

Abstract

A method is presented for loading and unloading rod type fuel elements of a neutronic reactor of the heterogeneous, solld moderator, liquid cooled type. In the embodiment illustrated, the fuel rods are disposed in vertical coolant channels in the reactor core. The fuel rods are loaded and unloaded through the upper openings of the channels which are immersed in the coolant liquid, such as water. Unloading is accomplished by means of a coffer dam assembly having an outer sleeve which is placed in sealing relation around the upper opening. A radiation shield sleeve is disposed in and reciprocable through the coffer dam sleeve. A fuel rod engaging member operates through the axial bore in the radiation shield sleeve to withdraw the fuel rod from its position in the reactor coolant channel into the shield, the shield snd rod then being removed. Loading is accomplished in the reverse procedure.

Inventors:
;
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4296371
Patent Number(s):
US 2856339
Assignee:
U.S. Atomic Energy Commission
NSA Number:
NSA-13-008364
Resource Type:
Patent
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-59
Country of Publication:
United States
Language:
English
Subject:
PATENTS; CONFIGURATION; COOLANT LOOPS; COOLANTS; FUEL ELEMENTS; LIQUIDS; MACHINE PARTS; MODERATORS; RADIATION PROTECTION; REACTOR CORE; REACTOR FUELING; REACTORS; RODS; SEALS; SHIELDING; SOLIDS; VESSELS; WATER; WATER COOLANT

Citation Formats

Wigner, E P, and Young, G J. NEUTRONIC REACTORS. United States: N. p., 1958. Web.
Wigner, E P, & Young, G J. NEUTRONIC REACTORS. United States.
Wigner, E P, and Young, G J. 1958. "NEUTRONIC REACTORS". United States.
@article{osti_4296371,
title = {NEUTRONIC REACTORS},
author = {Wigner, E P and Young, G J},
abstractNote = {A method is presented for loading and unloading rod type fuel elements of a neutronic reactor of the heterogeneous, solld moderator, liquid cooled type. In the embodiment illustrated, the fuel rods are disposed in vertical coolant channels in the reactor core. The fuel rods are loaded and unloaded through the upper openings of the channels which are immersed in the coolant liquid, such as water. Unloading is accomplished by means of a coffer dam assembly having an outer sleeve which is placed in sealing relation around the upper opening. A radiation shield sleeve is disposed in and reciprocable through the coffer dam sleeve. A fuel rod engaging member operates through the axial bore in the radiation shield sleeve to withdraw the fuel rod from its position in the reactor coolant channel into the shield, the shield snd rod then being removed. Loading is accomplished in the reverse procedure.},
doi = {},
url = {https://www.osti.gov/biblio/4296371}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Oct 14 00:00:00 EDT 1958},
month = {Tue Oct 14 00:00:00 EDT 1958}
}