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Title: Encapsulated nuclear reactor heat source module

Abstract

Motivated by a goal to develop an encapsulated nuclear heat source (ENHS) that could be delivered and retrieved unopened after a long core lifetime, a novel reactor concept was postulated by the authors in summer 1998. The ENHS would be inserted into, and later removed from, an in-place power plant. The ENHS would, in fact, constitute a totally new refueling concept. The single most unique feature of the ENHS is that the fission-generated heat is transferred from the primary coolant to the secondary coolant through the reactor vessel wall. This enables the reactor module to have a very simple design and to be free of any mechanical connections to the power plant components. The ENHS coolant must have a low vapor pressure at operating temperatures. Lead or Pb-Bi eutectic appears to be among the most promising. Here, the authors briefly describe the ENHS concept and present results of a very preliminary assessment of its feasibility.

Authors:
 [1];  [2]
  1. Univ. of California, Berkeley, CA (United States)
  2. Argonne National Lab., IL (United States)
Publication Date:
OSTI Identifier:
678150
Report Number(s):
CONF-990605-
Journal ID: TANSAO; ISSN 0003-018X; TRN: 99:009135
Resource Type:
Journal Article
Journal Name:
Transactions of the American Nuclear Society
Additional Journal Information:
Journal Volume: 80; Conference: 1999 annual meeting of the American Nuclear Society (ANS), Boston, MA (United States), 6-10 Jun 1999; Other Information: PBD: 1999
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; TRANSPORTABLE REACTORS; DESIGN; NUCLEAR POWER PLANTS; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; FEASIBILITY STUDIES

Citation Formats

Greenspan, E., and Wade, D.C. Encapsulated nuclear reactor heat source module. United States: N. p., 1999. Web.
Greenspan, E., & Wade, D.C. Encapsulated nuclear reactor heat source module. United States.
Greenspan, E., and Wade, D.C. Wed . "Encapsulated nuclear reactor heat source module". United States.
@article{osti_678150,
title = {Encapsulated nuclear reactor heat source module},
author = {Greenspan, E. and Wade, D.C.},
abstractNote = {Motivated by a goal to develop an encapsulated nuclear heat source (ENHS) that could be delivered and retrieved unopened after a long core lifetime, a novel reactor concept was postulated by the authors in summer 1998. The ENHS would be inserted into, and later removed from, an in-place power plant. The ENHS would, in fact, constitute a totally new refueling concept. The single most unique feature of the ENHS is that the fission-generated heat is transferred from the primary coolant to the secondary coolant through the reactor vessel wall. This enables the reactor module to have a very simple design and to be free of any mechanical connections to the power plant components. The ENHS coolant must have a low vapor pressure at operating temperatures. Lead or Pb-Bi eutectic appears to be among the most promising. Here, the authors briefly describe the ENHS concept and present results of a very preliminary assessment of its feasibility.},
doi = {},
journal = {Transactions of the American Nuclear Society},
number = ,
volume = 80,
place = {United States},
year = {1999},
month = {9}
}