Kamil Szewczak

Evaluation of efficiency for in situ gamma spectrometer based upon cerium-doped lanthanum bromide detector dedicated for environmental radiation monitoring

Nuclear power plants that are planned to be constructed in various countries, including Poland, require to setup an environmental radiation monitoring system. Localization of the installation has to be preceded by the studies determining the level of natural background radiation. Presently the in situ gamma spectrometry is widely used for monitoring the natural as well as artificial radionuclides. An analysis and evaluation of parameters of the spectrometric system equipped with scintillation detector made of cerium-doped lanthanum bromide crystal are both the subject of the paper. The main question of the application of any gamma spectrometry system for the radiation monitoring purpose is how its efficiency looks like. Based on the numerical characteristics of the detector the absolute full energy peak efficiency was calculated. The three dimensions characteristics of gamma ray registration efficiency as the function of its energy and considered contaminated area diameter has been also performed. The study of numerical modeling based on MCNP code was performed by the ISOCS/LabSOCS software tool.

Calibration of the RSS-131 high efficiency ionization chamber for radiation dose monitoring during plasma experiments conducted on plasma focus device

Plasma research poses a radiation hazard. Due to the program of deuterium plasma research using the PF-1000 device, it is an intensive source of neutrons (up to 1011 n · pulse−1) with energy of 2,45 MeV and ionizing electromagnetic radiation with a broad energy spectrum. Both types of radiation are mostly emitted in ultra-short pulses (∼100 ns). The aim of this work was to test and calibrate the RSS-131 radiometer for its application in measurements of ultra-short electromagnetic radiation pulses with broad energy spectrum emitted during PF-1000 discharge. In addition, the results of raw measurements performed in the control room are presented.

Neutron activation of PF-1000 device parts during long-term fusion research

The neutron flux emitted from fusion devices induces many different nuclear reactions that can activate the vacuum chamber and irradiate operators. A γ-spectrometer was mounted inside the Plasma Focus (PF) PF-1000, the world’s largest plasma focus facility, after completing a campaign. Qualitative analysis was performed following a lengthy γ-spectrum acquisition period. Instrumental neutron activation analysis identified the elemental composition of the vacuum chamber for use by a Monte Carlo N-Particle simulation. In this way, the radioactivity accumulated inside the PF-1000 as the function of time was calculated.

A new concept of fusion neutron monitoring for PF-1000 device

Abstract The power output of plasma experiments and fusion reactors is a crucial parameter. It is determined by neutron yields that are proportional and directly related to the fusion yield. The number of emitted neutrons should be known for safety reasons and for neutron budget management. The PF-1000 is the large plasma facility based on the plasma focus phenomenon. PF-1000 is operating in the Institute of Plasma Physics and Laser Microfusion in Warsaw. Neutron yield changes during subsequent pulses, which is immanent part of this type device and so it must be monitored in terms of neutron emission. The reference diagnostic intended for this purpose is the silver activation counter (SAC) used for many years. Our previous studies demonstrated the applicability of radio-yttrium for neutron yield measurements during the deuterium campaign on the PF-1000 facility. The obtained results were compared with data from silver activation counter and shown linear dependence but with some protuberances in local scale. Correlation between results for both neutron monitors was maintained. But the yttrium monitor registered the fast energy neutron that reached measurement apparatus directly from the plasma pinch. Based on the preliminary experiences, the yttrium monitor was designed to automatically register neutron-induced yttrium activity. The MCNP geometrical model of PF-1000 and yttrium monitor were both used for calculation of the activation coefficient for yttrium. The yttrium monitor has been established as the permanent diagnostic for monitoring fusion reactions in the PF-1000 device.

Radioindium and determination of neutron radial asymmetry for the PF-1000 plasma focus device

Indium activation was used for radial neutron distribution measurements. The dense plasma focus device PF-1000 was used as the D–D neutron source. The geometry of the indium samples used to determine the neutron radial asymmetry (Ras) was beforehand optimized for sufficient γ–registration efficiency. The samples were placed on the vacuum vessel’s outer wall, activated, and measured by γ-ray spectrometry. The experiment was supported by Monte Carlo calculations of the activation factor, allowing Ras to be calculated. The parameters Ras and the shift of neutron emission center introduced here are useful for describing D–D neutron emission distributions.

Radiation hazards in PF-1000 plasma generator fusion research

Fusion research poses significant radiation hazards, including prompt as well as delayed exposures. Prompt radiation consists of deeply penetrating neutrons and gamma rays, whereas delayed exposure derives from nuclear decays that were previously activated by neutrons. The PF-1000 plasma focus device, a dense magnetized plasma generator, is a source of all of these radiation hazards. The aim here is to assess the delayed radiation hazard of the PF-1000 device to the operational crew and research scientists.

Delay effects of the interactions between neutrons emitted during plasma experiments performed on the DPF-1000 U facility and construction materials

The Institute of Plasma Physics and Laser Microfusion operates the biggest plasma focus device built so far in the world. It is identified as DPF-1000 U (Dense Plasma Focus Upgrade). The plasma produced by the described device constitutes a pulse of highly effective neutron source with the neutron yield ranging up to 1012 n per impulse. The precise composition of the stainless steel from which the vacuum chamber of the plasma focus device is made, was determined by neutron activation analysis. It was found that nuclear reactions that occur inside the stainless steel are mainly (n, γ), (n, p) and (n, α) reactions. Taking into consideration the neutron energy spectrum and the material composition, 63 nuclear reactions leading to vacuum chamber material activation were identified in total. It was observed that in the first hour after shut-down, the main activity comes from 59Fe and 59Ni isotopes. One year after the shut-down, the main contribution to the observed radioactivity of the experimental chamber material was related to the presence of 54Mn isotope, while after 10 years the only significant contribution to the activity will be made by molybdenum isotopes such as 93mMo and 99Mo.

Occupational exposure to Am-Be neutron calibration source mounted in OB26 shielding container

Abstract Laboratory for Dosimetric and Radon Instruments Calibration which is a part of Central Laboratory for Radiological Protection (CLRP) in Warsaw is equipped with 241Am-Be neutron calibration source with activity of 185 GBq since 1999. The capsule was mounted in the OB26 type shielding container. The control room is separated from the above source by a concrete wall of 0.5 m in thickness. The calibration hall is adjacent to one side of the offi ce room. To comply with the requirements of the radiological protection system, the occupational exposure of persons that are working both in the offi ce and control room needs to be assessed. Two methods were involved for ambient dose equivalent rate determination. The active instrument measurements (AIMs) performed with the Berthold LB6411 neutron probe and the Monte Carlo simulation method (MCS) based on MCNP5 code. These estimations were completed for fi ve reference points. Additionally the γ radiation component was measured by RSS131 ionisation chamber. An increased value of the ambient dose equivalent rate from neutrons was observed in two reference positions. The fi rst observation was done in the control room while the second one in the offi ce room. Expected individual dose equivalents were evaluated based on the results of the AIM and on the expected working time in particular reference points. The annual individual dose equivalent associated with calibration activities using mentioned neutron source was estimated at maximum 0.8 mSv.

Individual dose monitoring of the nuclear medicine departments staff controlled by Central Laboratory for Radiological Protection

Presented paper describes the results of the individual doses measurements for ionizing radiation, carried out by the Laboratory of Individual and Environmental Doses Monitoring (PDIS) of the Central Laboratory for Radiological Protection in Warsaw (CLOR) for the medical staff employees in several nuclear medicine (NM) departments across Poland. In total there are48 NM departments in operation in Poland [1] (consultation in Nuclear Atomic Agency). Presented results were collected over the period from January 2011 to December 2011 at eight NM departments located in Krakow, Warszawa (two departments), Rzeszow (two departments), Opole, Przemysl and Gorzow Wielkopolski. For radiation monitoring three kinds of thermo luminescence dosimeters (TLD) were used. The first TLD h collected information about whole body (C) effective dose, the second dosimeter was mounted in the ring (P) meanwhile the third on the wrist (N) of the tested person. Reading of TLDs was performed in quarterly periods. As a good approximation of effective and equivalent dose assessment of operational quantities both the individual dose equivalent Hp(10) and the Hp(0.07) were used. The analysis of the data was performed using two methods The first method was based on quarterly estimations of Hp(10)q and Hp(0.07)q while the second measured cumulative annual doses Hp(10)a and Hp(0.07)a. The highest recorded value of the radiation dose for quarterly assessments reached 24.4 mSv and was recorded by the wrist type dosimeter worn by a worker involved in source preparation procedure. The mean values of Hp(10)q(C type dosimeter) and Hp(0.07)q (P and N type dosimeter) for all monitored departments were respectively 0.46 mSv and 3.29 mSv. There was a strong correlation between the performed job and the value of the received dose. The highest doses always were absorbed by those staff members who were involved in sources preparation. The highest annual cumulative dose for a particular worker in the considered time period was 4.22 mSv for Hp(10)a and 67.7 mSv for Hp(0.07)a. In 2011 no case of exceeding the allowed dose limits was noted.

Radiation hazards in PF-1000 plasma generator fusion research (part 3)

Plasma experiments conducted on the PF-1000 device generate the release of neutrons and ionizing radiation that are the source of immediate exposure to personnel. Neutron activation of materials in the research device and the surroundings is a source of ongoing radiation exposure to the same personnel. Having reported on personnel exposure from ionizing radiation and neutron activation, we now aim to characterize exposure from direct neutron emission generated by the device, and describe the process of ensuring measurement accuracy.