scholarly journals Comparisons of calculated and measured spectral distributions of neutrons from a 14-MeV neutron source inside the Tokamak Fusion Test Reactor

1985 ◽  
Author(s):  
R. T. Santoro ◽  
J. M. Barnes ◽  
R. G. Alsmiller, Jr. ◽  
M. B. Emmett ◽  
J. D. Drischler
Keyword(s):  
Neutron Source ◽  
Spectral Distributions ◽  
Test Reactor

scholarly journals Comparisons of Calculated and Measured Spectral Distributions of Neutrons from a 14-MeV Neutron Source inside the Tokamak Fusion Test Reactor

1987 ◽  
Vol 11 (2) ◽  
pp. 420-428 ◽  
Author(s):  
R. T. Santoro ◽  
J. M. Barnes ◽  
R. G. Alsmiller ◽  
Margaret B. Emmett ◽  
James D. Drischler
Keyword(s):  
Neutron Source ◽  
Spectral Distributions ◽  
Test Reactor

Evaluation and validation of external neutron source strength of operating Fast Breeder Test Reactor

2021 ◽  
Vol 372 ◽  
pp. 110992
Author(s):  
Neethu Hanna Stephen ◽  
C.P. Reddy ◽  
G. Raghukumar ◽  
K. Dinesh ◽  
K.V. Suresh Kumar
Keyword(s):  
Neutron Source ◽  
Source Strength ◽  
Fast Breeder Test Reactor ◽  
Test Reactor

Improvement of Exchanging Method of Neutron Startup Source of High Temperature Engineering Test Reactor

2016 ◽  
Author(s):  
Hiroaki Sawahata ◽  
Yosuke Shimazaki ◽  
Etsuo Ishitsuka ◽  
Kazunori Yamazaki ◽  
Yoshinori Yanagida ◽  
...  
Keyword(s):  
High Temperature ◽  
Radiation Dose ◽  
Neutron Source ◽  
Reactor Core ◽  
Handling Performance ◽  
Technical Issues ◽  
Neutron Leakage ◽  
Poly Ethylene ◽  
Test Reactor ◽  
Transportation Container

In the HTTR, 252Cf is loaded in the reactor core as a neutron startup source and changed at the frequency. In this exchange work, there were two technical issues; slightly higher radiation exposure of workers by neutron leakage and reliability of neutron source transportation container in handling. To reduce the radiation dose by the neutron leakage, detailed numerical evaluations using PHITS code were carried out, the effective shielding method for fuel handling machine was proposed. Easily removable poly-ethylene blocks and particles were used as the neutron shieling, and installed in the cooling paths of the fuel handling machine. As a result, the collective effective dose by neutron was reduced from about 700man-μSv to about 300man-μSv. As to the neutron source transportation container, the handling performance was improved and the handling work was safely accomplished by downsizing.

Collimated ZnS (Ag)‐detector array for Tokamak Fusion Test Reactor neutron source strength radial profile measurements

1985 ◽  
Vol 56 (5) ◽  
pp. 1081-1083 ◽  
Author(s):  
H. W. Hendel ◽  
L. P. Ku ◽  
D. C. Long ◽  
E. B. Nieschmidt ◽  
J. D. Strachan
Keyword(s):  
Neutron Source ◽  
Radial Profile ◽  
Detector Array ◽  
Reactor Neutron ◽  
Source Strength ◽  
Test Reactor

Design of a Neutron Source for Calibration

2002 ◽  
Author(s):  
Aureliano Carrillo-Nuñez
Keyword(s):  
Neutron Source

Closed loop auto control system software for Miniature Neutron Source Reactors (MNSRs)

Kerntechnik ◽  
2009 ◽  
Vol 74 (5-6) ◽  
pp. 280-285
Author(s):  
M. Iqbal ◽  
J. Qadir ◽  
T. K. Bhatti ◽  
Q. Abbas ◽  
S. M. Mirza
Keyword(s):  
Control System ◽  
Neutron Source ◽  
Closed Loop ◽  
System Software

Slurry Bioremediation of Petrochemical Waste Sludges

1992 ◽  
Vol 25 (3) ◽  
pp. 207-212 ◽  
Author(s):  
F. J. Castaldi ◽  
D. L. Ford
Keyword(s):  
Aqueous Phase ◽  
Petrochemical Production ◽  
Waste Sludge ◽  
Petrochemical Waste ◽  
Test Reactor

Slurry bioremediation testing was conducted on waste sludges from petrochemical production. The study concludes that the apparent mechanism for remediation of the waste involves an initial dissolution of the waste constituents into the aqueous phase followed by actual biodegradation. The test reactor most successful in the solubilization and dispersal of waste constituents and possibly most effective in reducing waste sludge mass during treatment is the reactor with the lowest waste sludge-to-microorganism ratio.

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