TH-D-224C-03: Integral Test Phantom For Dosimetric and Geometric Assurance of IG-IMRT

2006 ◽  
Vol 33 (6Part22) ◽  
pp. 2283-2283
Author(s):  
D Letourneau ◽  
D Moseley ◽  
M Sharpe ◽  
D Jaffray
Keyword(s):  
Integral Test ◽  
Test Phantom

Integral test phantom for dosimetric quality assurance of image guided and intensity modulated stereotactic radiotherapy

2007 ◽  
Vol 34 (5) ◽  
pp. 1842-1849 ◽  
Author(s):  
Daniel Létourneau ◽  
Harald Keller ◽  
Michael B. Sharpe ◽  
David A. Jaffray
Keyword(s):  
Quality Assurance ◽  
Stereotactic Radiotherapy ◽  
Integral Test ◽  
Image Guided ◽  
Intensity Modulated ◽  
Test Phantom

Scaling analysis of core pressure drop in reduced height integral test facility

Kerntechnik ◽  
2018 ◽  
Vol 83 (3) ◽  
pp. 178-180
Author(s):  
P. Ju ◽  
B. Long ◽  
L. Li ◽  
Q. Su ◽  
X. Wu ◽  
...  
Keyword(s):  
Pressure Drop ◽  
Test Facility ◽  
Scaling Analysis ◽  
Integral Test ◽  
Reduced Height

Assessment of wall velocity gradient imaging using a test phantom

1996 ◽  
Vol 22 (9) ◽  
pp. 1255-1260 ◽  
Author(s):  
A. Nowicki ◽  
R. Olszewski ◽  
J. Etienne ◽  
P. Karłowicz ◽  
J. Adamus
Keyword(s):  
Velocity Gradient ◽  
Wall Velocity ◽  
Test Phantom

scholarly journals Technology Base 2004 Report on the Ultrasonic Calibration Test Phantom

2004 ◽  
Author(s):  
S Lehman ◽  
K Fisher ◽  
M Werve ◽  
D Chambers
Keyword(s):  
Calibration Test ◽  
Test Phantom

Integral Test of CENDL-3.1 with Shielding Benchmarks

2011 ◽  
Vol 59 (2(3)) ◽  
pp. 1166-1169
Author(s):  
H. Y. Zhang ◽  
H. C. Wu
Keyword(s):  
Integral Test

Integral measurement of spectrum-averaged cross sections of a few threshold reactions induced by fast neutrons of a TRIGA reactor: comparison with integrated data from excitation functions given in various data libraries

2020 ◽  
Vol 108 (7) ◽  
pp. 511-516
Author(s):  
Md. Shuza Uddin ◽  
K. A. Rafee ◽  
S. M. Hossain ◽  
R. Khan ◽  
S. M. Qaim
Keyword(s):  
Excitation Function ◽  
Cross Sections ◽  
Fast Neutrons ◽  
Integral Test ◽  
Triga Reactor ◽  
Fission Spectrum ◽  
Data Libraries ◽  
First Time ◽  
Prompt Fission ◽  
Fast Neutron Spectrum

AbstractIntegral cross sections of the reactions 24Mg(n,p)24Na, 27Al(n,p)27Mg, 27Al(n,α)24Na, 58Ni(n,d + np)57Co and 60Ni(n,p)60Co were measured for the first time using the fast neutron spectrum of a TRIGA reactor extending from 0.5 to 20 MeV. The values obtained in this work were comparable with the recommended values for a pure 235U prompt fission spectrum. The measured integral value was utilized for integral test of excitation function of each reaction given in some data libraries, namely ENDF/B-VIII.0, TENDL-2017, IRDFF-1.05 and ROSFOND-2010. The integral measurements are generally consistent with the integrated values within 5 %, except for a few cases, e. g. the reaction 60Ni(n,p)60Co, where the data libraries appear to need improvement.

scholarly journals Consistent Posttest Calculations for LOCA Scenarios in LOBI Integral Facility

2012 ◽  
Vol 2012 ◽  
pp. 1-16 ◽  
Author(s):  
F. Reventós ◽  
P. Pla ◽  
C. Matteoli ◽  
G. Nacci ◽  
M. Cherubini ◽  
...  
Keyword(s):  
Experimental Data ◽  
Mass Flow ◽  
Scaling Factor ◽  
Test Facility ◽  
Data Bases ◽  
Integral Test ◽  
The Core ◽  
Active Elements ◽  
Accuracy Data

Integral test facilities (ITFs) are one of the main tools for the validation of best estimate thermalhydraulic system codes. The experimental data are also of great value when compared to the experiment-scaled conditions in a full NPP. The LOBI was a single plus a triple-loop (simulated by one loop) test facility electrically heated to simulate a 1300 MWe PWR. The scaling factor was 712 for the core power, volume, and mass flow. Primary and secondary sides contained all main active elements. Tests were performed for the characterization of phenomenologies relevant to large and small break LOCAs and special transients in PWRs. The paper presents the results of three posttest calculations of LOBI experiments. The selected experiments are BL-30, BL-44, and A1-84. They are LOCA scenarios of different break sizes and with different availability of safety injection components. The goal of the analysis is to improve the knowledge of the phenomena occurred in the facility in order to use it in further studies related to qualifying nodalizations of actual plants or to establish accuracy data bases for uncertainty methodologies. An example of procedure of implementing changes in a common nodalization valid for simulating tests occurred in a specific ITF is presented along with its confirmation based on posttests results.

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