Influence of the position of the group of elements of the controlling and shielding system upon the integral neutron flux through the side surface of the jacket of the VV�R-440 (water-water power) reactor

1985 ◽  
Vol 59 (4) ◽  
pp. 867-869
Author(s):  
L. N. Bogachek ◽  
K. A. Gazaryan ◽  
A. M. Luzhnov ◽  
V. V. Lysenko ◽  
A. S. Makhon'kov ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Power Reactor ◽  
Side Surface ◽  
Water Power ◽  
Integral Neutron ◽  
Integral Neutron Flux ◽  
Shielding System

Rectifier emf and short-circuit current as functions of integral neutron flux for gallium arsenide p-n junctions

1973 ◽  
Vol 16 (2) ◽  
pp. 276-278
Author(s):  
V. I. Gaman ◽  
V. D. Okunev ◽  
A. P. Mamontov ◽  
B. A. Nichipurenko
Keyword(s):  
Gallium Arsenide ◽  
Neutron Flux ◽  
Short Circuit ◽  
Short Circuit Current ◽  
Integral Neutron ◽  
Integral Neutron Flux

Density effect of reactivity in a heavy-water power reactor operating in the 233U self-fueling regime

Atomic Energy ◽  
2008 ◽  
Vol 105 (5) ◽  
pp. 316-323
Author(s):  
B. R. Bergelson ◽  
A. S. Gerasimov ◽  
G. V. Tikhomirov
Keyword(s):  
Heavy Water ◽  
Power Reactor ◽  
Density Effect ◽  
Water Power ◽  
Reactor Operating

Rechner-Regelung der Neutronenflußverteilung in einem Leistungsreaktor / Computer control of the neutron flux distribution in a power reactor

1974 ◽  
Vol 22 (12) ◽  
Author(s):  
R. Grumbach
Keyword(s):  
Neutron Flux ◽  
Flux Distribution ◽  
Power Reactor ◽  
Computer Control ◽  
Neutron Flux Distribution

Die Neutronenflußverteilung in einem großen Kernreaktor unterliegt Störeinflüssen, deren Auswirkungen durch Regelung beherrscht werden müssen. Zu diesem Zweck wurde ein mit Hilfe eines Prozeßrechners anwendbares Verfahren entwickelt, das ein Regelungsgesetz aus einem Modell des vorhandenen Prozeßzustands errechnet; um zeitraubende physikalische Rechnungen zu vermeiden, werden die benötigten Modellparameter fortlaufend durch empirische Prozeßerkennung ermittelt. In Experimenten mit einem Leistungsreaktor wurde die Anwendbarkeit des Regelungsverfahrens bewiesen.

A gas-cooled heavy water power reactor

Atomic Energy ◽  
1956 ◽  
Vol 1 (1) ◽  
pp. 3-6 ◽  
Author(s):  
A. I. Alikhanov ◽  
V. V. Vladimirskii ◽  
P. A. Petrov ◽  
P. I. Khristenko
Keyword(s):  
Heavy Water ◽  
Power Reactor ◽  
Water Power

AMS Measurement of 237Np at CIAE

Radiocarbon ◽  
2013 ◽  
Vol 55 (2) ◽  
pp. 294-301 ◽  
Author(s):  
Xianggao Wang ◽  
Shan Jiang ◽  
Ming He ◽  
Kejun Dong ◽  
Hongtao Chen ◽  
...  
Keyword(s):  
Mass Spectrometry ◽  
Isotopic Ratio ◽  
Atomic Ratio ◽  
Molecular Ions ◽  
Nuclear Safeguards ◽  
Electrostatic Analyzer ◽  
Integral Neutron ◽  
Set Up ◽  
Oxide Sample ◽  
Integral Neutron Flux

237Np (≃2.14 × 106 yr half-life) is potentially applicable in studies on nuclear safeguards and radioactive waste migration. The atomic ratio of 237Np/U in nature is 10−12 or even lower, depending strongly on the integral neutron flux received by the material. As an ultra-sensitive technique, accelerator mass spectrometry (AMS) is the best for measuring ultratrace 237Np. By extracting negative molecular ions NpO– from the oxide sample using 238UO– and 208Pb16O2– pilot beams for the simulation of 237Np ion transport, identifying the interference isotopes by high-resolution dedicated injector, electrostatic analyzer, and time of flight (TOF) detector, a method for AMS measurement of 237Np was set up on the HI-13 accelerator at the China Institute of Atomic Energy (CIAE). A sensitivity of <10–11 has been achieved for the isotopic ratio 237Np/238U.

The Hot Function Flow Characteristics of a Main Cooling Water System for the Nuclear Fuel Test Loop Installed in HANARO

2009 ◽  
Author(s):  
Young-Chul Park ◽  
Young-Seob Lee ◽  
Dae-Young Chi
Keyword(s):  
High Temperature ◽  
Power Reactor ◽  
Water System ◽  
Cooling Water ◽  
Flow Characteristics ◽  
Reaction Heat ◽  
Water Power ◽  
Test Loop ◽  
Air Pockets ◽  
High Temperature Operation

A nuclear fuel test loop (after below, FTL) is installed in IR1 of an irradiation hole in HANARO for testing neutron irradiation characteristics and thermo hydraulic characteristics of a fuel loaded in a light water power reactor or a heavy water power reactor. There is an in-pile section (IPS) and an out-pile section (OPS) in this test loop. When HANARO is normally operated, the fuel loaded in the IPS has a nuclear reaction heat generated by a neutron irradiation. To remove the generated heat and to maintain an operating conditions of the test fuel, a main cooling water system (MCWS) is installed in the OPS of the FTL. The MCWS is composed of a main cooler, a pressurizer, two circulation pumps, a main heater, interconnection pipe line and instruments. The interconnection pipeline is a closed loop which is connected respectively to an inlet and an outlet of the IPS. To absorb the nuclear reaction heat, there is a higher elevation pipeline with a reverse U letter type pipeline installed in upstream of the cooler. And there is another higher elevation pipeline for sucking a fluid by a vertically installed circulation pump with a top suction and a side discharge. Therefore, we predicted that it is difficult to continuously suck a fluid and pressurize the fluid due to air pockets in the two higher elevation pipelines under a high temperature operation. To verify the hot function flow characteristics of the MCWS including air pockets of the higher elevation pipelines, a flow net work analysis has been conducted under a high temperature operation. When the two higher elevation pipelines wholly filled with coolant, it was confirmed through the results that the pump pressurizes the coolant normally. And it was confirmed through the analysis results that the system hot function characteristics met the system design requirements.

scholarly journals Experimental confirmation of a new method for selective neutron separation

2020 ◽  
Vol 6 (4) ◽  
pp. 235-241
Author(s):  
Yuri V. Drobyshevsky ◽  
Ilya M. Anfimov ◽  
Valery A. Varlachev ◽  
Svetlana P. Kobeleva ◽  
Sergey A. Nekrasov ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Single Crystal ◽  
Thermal Neutron ◽  
Single Crystal Silicon ◽  
Hydrogen Uptake ◽  
Experimental Confirmation ◽  
Crystal Silicon ◽  
Neutron Reflection ◽  
Neutron Beams ◽  
Integral Neutron

The article presents an experimental confirmation of the operability of neutron concentrators in devices that form and use directed high-intensity thermal neutron beams with elliptical channels made as blocks of profiled graphite and aluminum plates. The effect of neutron reflection from the surface of materials is the basis of a device capable of selecting neutrons by their directions in space. The study experimentally confirmed the efficiency of a moderating-focusing structure (MFS) based on a pack of elliptical neutron mirrors, which makes it possible to form oriented thermal neutron beams from the outgoing neutron flux. To record the effects of selective thermal neutron separation, silicon single-crystal wafers were used, due to which it was possible to obtain portraits of integral neutron fluxes in the reactor. The experiments were carried out in a horizontal experimental channel (HEC-4) at the IRT-T reactor of the National Research Tomsk Polytechnic University. The integral neutron flux was (2.3–3.02)·1017 cm–2. The neutron flux was detected by the change in the specific electrical resistivity of the single-crystal silicon wafers. The effect of concentration of thermal neutrons was recorded both on the block of graphite neutron mirrors and on the block of aluminum thin-walled elliptical mirrors. In the near future, on this basis, it will be possible to solve such problems as extending the reactor life by reducing the hydrogen uptake in the inner walls. In addition, the experiments have proved the possibility of creating anisotropic structures that lie outside the formalism of Liouville’s theorem, in which the surfaces of thermal neutron sinks are formed with subsequent concentration in the areas separated by aluminum or graphite plates.

scholarly journals Structural assessment of radiation damage in light water power reactor concrete biological shield walls

2019 ◽  
Vol 350 ◽  
pp. 9-20 ◽  
Author(s):  
P.M. Bruck ◽  
T.C. Esselman ◽  
B.M. Elaidi ◽  
J.J. Wall ◽  
E.L. Wong
Keyword(s):  
Radiation Damage ◽  
Power Reactor ◽  
Structural Assessment ◽  
Light Water ◽  
Water Power
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