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Title: TEMPERATURES IN THE MSRE CORE DURING STEADY-STATE POWER OPERATION

Abstract

Over-all fuel and graphite temperature distributions were calculated for a detailed hydraulic and nuclear representation of the MSRE. These temperature distributions were weighted in various ways to obtain nuclear and bulk mean temperatures for both materials. At the design power level of 10 Mw, with the reactor inlet and outlet temperatures at 1175 deg F and 1225 deg F, respectively, the nuclear mean fuel temperature is 1213 deg F. The bulk average temperature of the fuel in the reactor vessel (excluding the volute) is 1198 deg F. For the same conditions and with no fuel permeation, the graphite nuclear and bulk mean temperatures are 1257 deg F and 1226 deg F, respectively. Fuel permeation of 2% of the graphite volume raises these values to 1264 deg F and 1231 deg F, respectively. The effects of power on the nuclear mean temperatures were combined with the temperature coefficients of reactivity of the fuel and graphite to estimate the power coefficient of reactivity of the reactor. if the reactor outlet temperature is held constant during power changes, the power coefficient is the reactor inlet and outlet temperatures is held constant, the power coefficient is --0.047% ( DELTA k/k)/Mw. (auth)

Authors:
;
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
US Atomic Energy Commission (AEC)
OSTI Identifier:
4749259
Report Number(s):
ORNL-TM-378
NSA Number:
NSA-17-015500
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Resource Relation:
Other Information: Orig. Receipt Date: 31-DEC-63
Country of Publication:
United States
Language:
English
Subject:
REACTOR TECHNOLOGY; DIFFERENTIAL EQUATIONS; DISTRIBUTION; FUSED SALT FUEL; GRAPHITE MODERATOR; HIGH TEMPERATURE; LIQUID FLOW; MSRE; POROSITY; REACTIVITY; REACTORS; TEMPERATURE; VARIATIONS

Citation Formats

Engel, J R, and Haubenreich, P N. TEMPERATURES IN THE MSRE CORE DURING STEADY-STATE POWER OPERATION. United States: N. p., 1962. Web. doi:10.2172/4749259.
Engel, J R, & Haubenreich, P N. TEMPERATURES IN THE MSRE CORE DURING STEADY-STATE POWER OPERATION. United States. https://doi.org/10.2172/4749259
Engel, J R, and Haubenreich, P N. 1962. "TEMPERATURES IN THE MSRE CORE DURING STEADY-STATE POWER OPERATION". United States. https://doi.org/10.2172/4749259. https://www.osti.gov/servlets/purl/4749259.
@article{osti_4749259,
title = {TEMPERATURES IN THE MSRE CORE DURING STEADY-STATE POWER OPERATION},
author = {Engel, J R and Haubenreich, P N},
abstractNote = {Over-all fuel and graphite temperature distributions were calculated for a detailed hydraulic and nuclear representation of the MSRE. These temperature distributions were weighted in various ways to obtain nuclear and bulk mean temperatures for both materials. At the design power level of 10 Mw, with the reactor inlet and outlet temperatures at 1175 deg F and 1225 deg F, respectively, the nuclear mean fuel temperature is 1213 deg F. The bulk average temperature of the fuel in the reactor vessel (excluding the volute) is 1198 deg F. For the same conditions and with no fuel permeation, the graphite nuclear and bulk mean temperatures are 1257 deg F and 1226 deg F, respectively. Fuel permeation of 2% of the graphite volume raises these values to 1264 deg F and 1231 deg F, respectively. The effects of power on the nuclear mean temperatures were combined with the temperature coefficients of reactivity of the fuel and graphite to estimate the power coefficient of reactivity of the reactor. if the reactor outlet temperature is held constant during power changes, the power coefficient is the reactor inlet and outlet temperatures is held constant, the power coefficient is --0.047% ( DELTA k/k)/Mw. (auth)},
doi = {10.2172/4749259},
url = {https://www.osti.gov/biblio/4749259}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Nov 01 00:00:00 EST 1962},
month = {Thu Nov 01 00:00:00 EST 1962}
}