Neutron radiation yield of spent fuel of VV�R reactor

1980 ◽  
Vol 49 (5) ◽  
pp. 768-770
Author(s):  
N. S. Shimanskaya
Keyword(s):  
Neutron Radiation ◽  
Spent Fuel ◽  
Radiation Yield

Neutron radiation characteristics of the IVth generation reactor spent fuel

2018 ◽  
Author(s):  
Sergey Bedenko ◽  
Igor Shamanin ◽  
Victor Grachev ◽  
Vladimir Knyshev ◽  
Olesya Ukrainets ◽  
...  
Keyword(s):  
Neutron Radiation ◽  
Spent Fuel ◽  
Radiation Characteristics

Study on Periodic Shielding Performance Measurements of Spent Fuel Transportation Package

2017 ◽  
Author(s):  
Hongchao Sun ◽  
Guoqiang Li ◽  
Xuexin Wang ◽  
Dajie Zhuang ◽  
Renze Wang ◽  
...  
Keyword(s):  
Spent Nuclear Fuel ◽  
Measurement Instrument ◽  
Neutron Radiation ◽  
Radiation Shielding ◽  
Radioactive Material ◽  
Transportation Safety ◽  
Spent Fuel ◽  
Performance Measurements ◽  
Radiation Level ◽  
Neutron Measurement

The radioactive activity of spent nuclear fuel is high, and the transportation safety is concerned by public and specialist. The periodic radiation shielding performance measurements of spent fuels package is important content to ensure transportation safety of spent fuels. The radiation shielding performance of package must meet the requirements of “Regulations for the safe transport of radioactive material” (GB11806-2004). However, some of the problems and difficulties reflected in practice need to be solved, such as the measurements results of neutron radiation level of spent fuels package outer are not always reliable. In this paper, the periodic shielding performance measurements of one type of spent fuel transportation package are presented. The monitoring results of using both the neutron multi-sphere spectrometer and portable neutron measurement instrument are compared, and the Monte Carlo simulation is done to verify the measurements results. Some factors are discussed, and an optimized scheme is recommended.

scholarly journals Peculiarities of the radiation formation in dispersed microencapsulated nuclear fuel

2019 ◽  
Vol 5 (1) ◽  
pp. 23-29
Author(s):  
Sergey V. Bedenko ◽  
Vladimir V. Knyshev ◽  
Mariya Ye. Kuznetsova ◽  
Igor O. Lutsik ◽  
Igor V. Shamanin
Keyword(s):  
Nuclear Fuel ◽  
Computational Study ◽  
Reactor Core ◽  
Spectral Composition ◽  
Neutron Radiation ◽  
Photon Radiation ◽  
Structural Elements ◽  
Spent Fuel ◽  
Radiation Characteristics ◽  
Average Mass

A computational study has been performed for various options of the thorium reactor core loading. Neutronic studies of fuel have been conducted, its isotopic composition has been calculated, and the alpha emitters and the sources of neutron and photon radiation in the microencapsulated nuclear fuel have been analyzed. The studies had the purpose of developing the methodology used to estimate the radiation characteristics of nuclear fuel with a complex inner structure. Emphasis is placed on calculating the quantitative and spectral composition of the neutrons formed as the result of (a, n) reactions on small- and average-mass nuclei. The ratio of the quantity of the neutrons resulting from the (a, n) reactions to the quantity of the neutrons formed as the result of spontaneous fission has been calculated for fuel with heterogeneous and homogeneous arrangements of fissionable and structural elements. The developed tools will make it possible to estimate the neutron radiation dose, to revise the traditional fresh and spent fuel handling procedures, and to estimate, using the Rossi alpha method, the neutron multiplication factor in deeply subcritical systems. The neutron yield and spectrum were calculated using an analytical model and verified codes such as WIMS-D5B, ORIGEN-APP, SOURCES-4C and SRIM-2013.

scholarly journals Shelf life of plasma focus chambers with deuterium-tritium filling

2021 ◽  
Vol 9 (4) ◽  
pp. 347-358
Author(s):  
Dmitriy Yurkov ◽  
Victor Lavrenin ◽  
Boris Lemeshko ◽  
Yurii Mikhailov ◽  
Ilya Prokuratov ◽  
...  
Keyword(s):  
Shelf Life ◽  
Plasma Focus ◽  
Neutron Radiation ◽  
Bound State ◽  
Gas Generator ◽  
Radiation Yield ◽  
Initial Value ◽  
Duration Of Operation ◽  
Pulsed Neutron ◽  
Long Storage

The paper presents the results of an experimental study of the shelf life of sealed plasma focus chambers with deuterium-tritium and deuterium fillings. Shelf life is defined as maintaining the level of neutron yield during operation of PF chambers as part of pulsed neutron generators after long storage intervals. The release of impurities from the inner surfaces of the PF chamber and the accumulation of he-lium He3 due to the decay of tritium in the volume of the sealed-off PF chambers leads to a significant decrease in the neutron radiation yield several years after the chamber is filled with the working mixture. The paper shows that the shelf life of the chambers is significantly increased when using a gas generator, in which hy-drogen isotopes are contained in a bound state, and are released into the inner volume of the chamber only for the duration of operation as part of neutron gen-erators. It has been shown experimentally that spherical chambers of the PF9 type provide a level of neutron radiation yield Y, close to the initial value in the manu-facture of chambers, after more than 10 years of storage.

scholarly journals DEVELOPMENT OF A MODELING APPROACH TO ESTIMATE RADIATION FROM A SPENT FUEL ROD QUIVER

2021 ◽  
Vol 247 ◽  
pp. 16006
Author(s):  
Zs. Elter ◽  
V. Mishra ◽  
S. Grape ◽  
E. Branger ◽  
P. Jansson ◽  
...  
Keyword(s):  
Gamma Radiation ◽  
Spent Nuclear Fuel ◽  
Radiation Transport ◽  
Neutron Radiation ◽  
Nuclear Safeguards ◽  
Monte Carlo Code ◽  
Spent Fuel ◽  
Fuel Rods ◽  
History Of ◽  
New Type

Before encapsulation of spent nuclear fuel in a geological repository, the fuels need to be verified for safeguards purposes. This requirement applies to all spent fuel assemblies, including those with properties or designs that are especially challenging to verify. One such example are quivers, a new type of containers used to hold damaged spent fuel rods. After placing damaged rods inside the quivers, they are sealed with a thick lid and the water is removed. The lid is thick enough to significantly reduce the amount of the gamma radiation penetrating through it, which can make safeguards verification from the top using gamma techniques difficult. Considering that the number of quivers at storage facilities is foreseen to increase in near future, studying the feasibility of verification is timely. In this paper we make a feasibility study related to safeguards verification of quivers, aimed at investigating the gamma and neutron radiation field around a quiver designed by Westinghouse AB and filled with PWR fuel rods irradiated at the Swedish Ringhals site. A simplified geometry of the quiver and the detailed operational history of each rod are provided by Westinghouse and the reactor operator, respectively. The nuclide inventory of the rods placed in the quiver and the emission source terms are calculated with ORIGEN-ARP. The radiation transport is modeled with the Serpent2 Monte Carlo code. The first objective is to assess the capability of the spent fuel attribute tester (SFAT) to verify the content for nuclear safeguards purposes. The results show that the thick quiver lid attenuates the gamma radiation, thereby making gamma radiation based verification from above the quiver difficult.

Fuel-burnup monitoring based on the characteristic neutron radiation of spent fuel assemblies

Atomic Energy ◽  
1993 ◽  
Vol 74 (5) ◽  
pp. 399-401
Author(s):  
G. N. Vlaskin ◽  
E. V. Chvankin ◽  
O. G. Darenskikh ◽  
E. G. Dzekun ◽  
E. G. Markin ◽  
...  
Keyword(s):  
Neutron Radiation ◽  
Fuel Burnup ◽  
Spent Fuel ◽  
Fuel Assemblies

A new type of defect structure in 124-superconducting oxide revealed by HREM

1991 ◽  
Vol 49 ◽  
pp. 1092-1093
Author(s):  
R. Sharma ◽  
B.L. Ramakrishna ◽  
N.N. Thadhani ◽  
D. Hianes ◽  
Z. Iqbal
Keyword(s):  
Shock Wave ◽  
Defect Structure ◽  
Neutron Radiation ◽  
Weak Links ◽  
Defect Structures ◽  
New Materials ◽  
New Type ◽  
Current Densities ◽  
Processing Techniques ◽  
Microstructural Studies

After materials with superconducting temperatures higher than liquid nitrogen have been prepared, more emphasis has been on increasing the current densities (Jc) of high Tc superconductors than finding new materials with higher transition temperatures. Different processing techniques i.e thin films, shock wave processing, neutron radiation etc. have been applied in order to increase Jc. Microstructural studies of compounds thus prepared have shown either a decrease in gram boundaries that act as weak-links or increase in defect structure that act as flux-pinning centers. We have studied shock wave synthesized Tl-Ba-Cu-O and shock wave processed Y-123 superconductors with somewhat different properties compared to those prepared by solid-state reaction. Here we report the defect structures observed in the shock-processed Y-124 superconductors.

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