14 MeV neutron yields from D-T operation of the MIT Cockcroft-Walton accelerator

As part of our fusion-product diagnostic development program, we have begun a series of experiments with 14 MeV neutrons generated in a Cockcroft-Walton accelerator. Two different detectors have been used to measure the neutron yield: a silicon SBD and a Cu foil. The energy of the emitted neutrons has been determined by using two spectrometers: the SBD and a³He proportional counter. The reaction rate is monitored, with about ±5% accuracy, by detecting the particles from D + T n +. The neutron yields obtained from the Si detector and the Cu activation had associated uncertainties of about ±15% and agreed well with the predicted values from measurements.     

Methods for preparing ions of short-lived isotopes

Conclusions A source with thermal ionization in a cavity is extremely convenient for obtaining ion beams with an ultralow quantity of the starting material. Its efficiency with ionization potentials of the starting atoms V_i<6 eV is equal to 100% and drops to 1% for V_i=8 eV [7]. This makes it possible to use it in the study or more than two-thirds of the periodic system of elements, including the actinides. Thus for 10¹² uranium and plutonium atoms ^*9% and 50%, respectively; for 10⁶ curium atoms ^*70%; and, for 10⁵ californium atoms ^*37% [13]. It was shown in [14] that this source can be successfully used in mass spectroscopy to analyze trace quantities of different elements in the solid phase. With its help yttrium isotopes with _1/2=0.4 sec were detected in [16].This source is now widely used in our country, where with its help tens of new isotopes have been discovered [15, 17], and abroad (for example, [16]). The source is effective for short-lived isotopes with _i/_1/2<10 and V_i<7 eV. To study isotopes with _i/_1/2<10 and V_i>7 eV but with _i/_1/2>10 it is desirable to develop sources with thermal and photoionization in the cavity. For elements whose atoms have a long residence time on the surface, these sources, just as the gas-discharge sources, are inefficient. Means must be developed for raising the rate of desorption of the indicated atoms from the surface within the framework of the techniques examined here.Translated from Atomnaya Énergiya, Vol. 60, No. 2, pp. 114–119, February, 1986.     

Study of the zirconium apex op the Zr-Ta-Nb phase diagram

Metallographical examination thermal analysis and electrical resistance measurements have been applied to a study of the zirconium apex, up to 82% zirconium and a temperature of 1200C, of the ternary system Zr-Ta-Nb, with limited solubility of tantalum and niobium in -zirconium ( phase), limited solubility and complete solubility of niobium in -zirconium, with eutectoid decomposition of the \ solid solution and three-phase eutectoid equilibrium + between - and-zirconium. In the investigated portion of the Zr-Ta-Nb phase diagram, the following phase regions were found: a) two one-phase regions and ; b) three two-phase regions + , + and + : c) one three-phase region + + ; the region contracts as the temperature falls below 1200 C.The solubility of tantalum and niobium in -zirconium in the system Zr—Ta—Nb is about 0.5%. On passing from Zr—Ta to Zr—Nb, the + and + regions are displaced toward lower temperature and high niobium concentrations; the boundaries of the + and + + regions are lowered from 790 for Zr—Ta to 612 C for Zr-Nb. Passing between the + and + regions is a binary eutectoid line which, from Zr-Ta to Zr-Nb is displaced toward lower temperatures and higher niobium concentrations. The solubility of niobium in ot zirconium in the Zr-Nb system is about 0.5%by weight. Eutectoid decomposition in the Zr-Ta system shifts the maximum of the martensitic-like transformation to the left and results in an increase in the stability of the phase at room temperature in quenched alloys.     

Distribution of the ratio of radiation capture and fission cross sections for Pu239 with respect to height in the BR-5 reactor

A study was made of the distribution of the ratio of radiation capture and fission cross sections for Pu²³⁹ with respect to height in the BR-5 reactor. The distribution of neutron capture reactions was measured by determining the concentration of Pu²⁴⁰ from the rate of spontaneous fissions in plutonium samples irradiated in the reactor with an integral flux of 10²¹ to 10²² neutrons/cm². As initial material for irradiation, almost isotopically pure Pu²³⁹ (Pu²⁴⁰ content 5·10^–3% was used. The values of obtained rose from 0.1 to 0.8 on moving away from the center of the reactor. The data corresponding to equilibrium neutron spectra in the active zone and the outer region of the reflector agree with the results of measuring and _f in monoenergetic neutrons.Translated from Atomnaya Énergiya, Vol. 16, No. 6, pp. 497–500, June, 1964     

Synthesis of isotopes of element 102 with mass numbers 254, 253, and 252

In experiments on the irradiation of Pu²⁴² and Pu²³⁹ with O¹⁶ and O¹⁸ ions in the extracted beam of the 310-era cyclotron of the Joint Institute for Nuclear Research, isotopes of 102²⁵⁴, 102²⁵³ and 102²⁵² have been synthesized. Their properties are given below: Isotope T_1/2, sec E, meV 102²⁵⁴ 75±15 8.11±0.03 102²⁵³ 95±10 8.01±0.03 102²⁵² 4.5±1.5 8.41±0.03In order to identify the isotopes, the excitation functions are measured in crossover reaetions and the decay of the daughter nuclei is recorded.Translated from Atomnaya Énergiya, Vol. 22, No. 2, pp. 90–97, February, 1967.     

The dynamics of nuclear power stations

This paper makes a comparison of the results of eXperimental and theoretical studies that have been carried out on the properties of the engineering model of the Beloyarskii atomic electric station under construction in the USSR, which uses nuclear superheating of the steam. It is shown that a number of the simplifying assumptions are correct which are often used in discussing the dynamics of nuclear power stations.The results of the studies may be used to make a theoretical analysis of the dynamic properties of several types of nuclear power installations, as well as in analyzing and synthesizing the optimum control system.Notation q() specific heat load, referred to length of segment, kcal/hour · m - f(x) distribution function of specific heat load along the length of segment - () heat transfer coefficient, including the thermal resistence of the fuel element, kcal/m² · hour · degree - t_f.e. (x, ) the current value of fuel element temperature, averaged over the corss section, degrees C - t(x, t) current value of coolant temperature, degrees C - p perimeter of fuel element, bathed by coolant, m - m weight of metal per unit length of fuel element kg/m - C_M heat capacity of metal and fuel element, kcal/kg · degree - i(x, ) current value of heat content of coolant, kcal/kg - specific gravity of coolant, kg/m³ - S live cross section of fuel element, m² - D(x, ) current value of flow of steam phase, kg/hour - G(x, ) current value of the flow of water phase, kg/hour - (x, ) current value of the fraction of the cross section occupied by steam - , specific gravity of water and steam at saturation temperature, kg/m² - i, i heat content of water and steam at saturation temperature, kcal/kg - t_S() saturation temperature, degrees C - P_i() pressure in i-th segment, kg/m² - l height, determining the level pressure between segments, m - g acceleration of gravity, m/hour² - w_i() coolant velocity at the i-th segment, m/hour - D_i() steam flow at the i-th segment of the superheating circuit, kg/hour - V_i volume of i-th segment of the superheating circuit, m³ - mean steam temperature at the i-th segment for the superheating circuit, degrees C - k₁,k₂,k₃,k₄ constant coefficients - N/N₀ relative power change in the evaporating channels, % - P_I, P_II pressure change in the first and second loops, atm - t_sps, t_fw change in temperature of superheated steam and feed water, respectively, degrees C Translated from Atomnaya Énergiya, Vol. 15, No. 2, pp. 115–120, August, 1963     

Separation of the stable isotopes of boron

This article describes methods for separating the stable isotopes of boron. Three of them can be used to prepare concentrates of B¹⁰ isotope in industrial quantities. The method of chemical exchange has a comparatively high coefficient of separation ( = 1.03); however, the production rate of the apparatus is small due to the high molecular weight of the complex. The preparation of B¹⁰ by fractionating BF₃ offers possibilities ( = 1.0075); however this process must be carried out at a temperature of –l00 °C, and requires the use of large quantities of liquid air. The method of separation by fractionation of BCl₃ has a low value of (1.003), but can be carried out at atmospheric pressure and room temperature.     

Constraints on very-high-β, edge-stabilized tandem-mirror reactors

There are several tandem-mirror schemes which propose a very high and edge stabilization for the center-cell plasma ( being the ratio of the plasma pressure to the vacuum magnetic-field pressure). While the exact criteria for the edge stabilization are uncertain, it is possible to analyze the option space in which a very-high- mirror reactor would operate. The primary physics constraints on such a reactor are the energy balance at ignition, the buildup of He⁴ ash and the hot-particle( ^hot ), and the need for adiabatic conservation of the hot-particle gyro-orbits in the axial field gradients at the center-cell ends. There are also engineering constraints on the allowable wall loading and plant size. In this paper, a wall-stabilized tandem-mirror reactor is analyzed and is found to be an attractive device requiring low center-cell vacuum fields (of the order of 2 to 3 tesla). A primary requirement is that the plasma edge have a thermal conductivity near classical values.     

Injection and storage of positrons

The authors describe the production of positrons and their injection into a storage ring. The positron beam is oblained by converting electrons in an external target and is shaped by means of special short-focus lenses. The particles are admitted into the storage ring below its medianplane: their capture is single-turn. The authors analyze the conditions required for maximum capture coefficient, which is equal to 1·10^–4 with vertical magnet aperture z = ±37 mm and horizontal aperture R= ±30 mm. They describe the method and results of their system for producing and injecting the positrons, and discuss the optimal conditions for capture and storage.Translated from Atomnaya Énergiya, Vol. 22, No. 3, pp. 206–210, March, 1967.     

Analysis of the composition of a mixture of249Bk+249Cf on the basis of x rays

Conclusion The results of the study enable us to conclude the following: the decay of²⁴⁹Bk is accompanied by an L series of x rays from the daughter product Cf. The yield of this radiation is low: (L+L+ L) 10^–4 ( disintegration)^–1, but because of the high specific activity of²⁴⁹Bk, 1 g of this isotope emits 3.7·10⁵ x-ray quanta per minute. This enables us to detect a fairly small amount of Bk (0.01 g) on the basis of x rays in a period of 5–10 min. The rapid accumulation of the daughter product²⁴⁹Cf does not interfere with the determination of the²⁴⁹Bk on the basis of x rays. Even when the mixture contains equal numbers of Bk and Cf nuclei, the ratio of the L lines corresponding to them is 0.46. Therefore the composition of a mixture of²⁴⁹Bk+²⁴⁹Cf can be determined on the basis of x rays over broad ranges of variation of the relative concentrations of Bk+Cf, roughly from 0.03 to 80. It is important to note that for relative measurements it is not necessary to prepare special specimens, since x rays with energies of 15–20 keV are not strongly absorbed in the solution and in the walls of the chemical vessel.Translated from Atomnaya Énergiya, Vol. 48, No. 2, pp. 106–108, February, 1980.     

Interaction of fast H1 + ions with metal surfaces in very high vacuum

The results of experiments on the interaction of fast hydrogen ions (H₁ ⁺) with metals forming weak chemical bonds (nickel, stainless steel) and metals forming strong chemical bonds (tantalum and titanium) with hydrogen are presented. The weighing method was used under very-high vacuum conditions to determine the sputtering coefficient of stainless steel bombarded by 35-keV H ₁ ⁺ ions and the penetration coefficient of H ₁ ⁺ ions entering the stainless steel (=9.10^–3, =0.5 for hydrogen concentrations greatly exceeding 10¹⁹ atoms/cm²). The variation of with the density of the hydrogen introduced and the temperature of the metals was determined by the pressure-variation method. The results indicate that metals of the titanium type are suitable for use in capturing fast hydrogen atoms in magnetic traps.Translated from Atomnaya Énergiya, Vol. 21, No. 5, pp. 339–345, November, 1966.     

Initial high beta operation of the HBT-EP Tokamak

HBT-EP is a new research tokamak designed and built to investigate passive and active feedback techniques to control MHD instabilities. In particular, HBT-EP will be able to test techniques to control fast MHD instabilities occurring at high Troyon-normalized beta, _N Ba/I_p [Tm/MA], since it is equipped with a thick, close-fitting, and adjustable conducting shell. The major goals of the initial operation of HBT-EP have been the achievement of high beta operation (_N 3) using only ohmic heating and the observation of MHD instabilities. By using a unique fast startup technique, we have successfully achieved these goals. A variety of MHD phenomena were observed during the high beta operation of HBT-EP. At modest beta (_N 2), discharges have been maintained for more than 10 msec, and these discharges exhibit saturated resistive instabilities. When _N approaches 3, major disruptions occur preceded by oscillating, growing precursors. During start-up, one or more minor disruptions are usually observed. A 1-D transport code has been used to simulate the evolution of the current profile, and these early minor instabilities are predicted to be double tearing modes. The simulation also reproduces the observed high beta operation when saturated neo-Alcator energy confinement scaling is assumed.     

Influence of the structure and properties of uranium on its behavior during irradiation

Data are presented on the variations in dimensions and form of uranium specimens during irradiation. It is shown that by regulating the composition of the uranium and treatment conditions (degree of deformation in the-region and heat-treatment conditions), in consequence of variation in grain size and texture, it is possible to vary within wide limits the magnitude of surface distortion due to irradiation and the value of G_i.A study has been made of the dependence of the variation in grain size of quenched uranium, as well as hardness, tensile strength, and yield strength, on the iron, silicon, and aluminum content of uranium. The cooling rate and content of these impurities influence the critical point of the transformation on quenching; for example, for a cooling rate of 400C/ sec and a silicon content of 0.05%, the critical point of the transformation drops to 530C.Experimental results show a creep acceleration during irradiation (nv = 6·10¹² neutr/cm²·sec) of 50–100 times, i.e., by 1.5–2 orders for textured uranium and uranium with disoriented structure. The rate of creep of uranium with a disoriented structure is connected to the burnup rate.The results are given of tensile tests made on uranium directly in the reactor. Even after remaining a short time in the neutron field (up to 1 hour), the percentage elongation is diminished somewhat and the tensile strength is increased.The following assisted in the experimental work: A. G. Lanin, V. M. Teplinskaia, V. K. Zakharova, L. N. Protsenko, V. N. Golovanova and K. A. Borisov.     

Investigation of the Effect of Radiation and High-Temperature Treatment on the x-Ray Luminescence of Quartz Glasses

The x-ray luminescence of KI, KV, and KU-1 quartz glasses, irradiated with and n– radiation in the dose range 10²–10⁷ Gy and neutron fluence range 10¹⁵–10¹⁷ cm^–2 and subjected to high-temperature annealing in air at 450 and 900°C is investigated. It is shown that the spectra of the nonirradiated and the and n– irradiated glasses of the first two types are a superposition of bands with _max = 410 and 460 nm, which are due to an impurity center initially present in the glasses (_max = 410 nm) and the initial and radiation-generated with dose 10⁶ Gy and fluence 10¹⁶ cm^–2 E' centers (_max = 460 nm). X-Ray luminescence is not observed in nonirradiated KU-1 glasses; a band with _max = 460–470 nm, due to radiation-generated E' centers, appears in the spectra of and n– irradiated glasses. As the radiation dose and the neutron fluence increase, the number of impurity centers decreases and the number of E' centers increases. It is established that the 410 nm band is due to the component of the n– radiation. High-temperature annealing in air at 900°C induces in the spectra new bands with _max = 470 and 520–540 nm, which are believed to be due to interstitial defects of the type O^– and O₂ ^–, formed when oxygen from air diffuses into the glass and localizes in interstices. 6 figures, 7 references.     

Resonance scattering of γ-rays in Mg24

Resonance scattering of -rays With energies E₁=1.38 Mev, corresponding to the transition to the ground state in Mg²⁴. have been observed in metallic magnesium. The energy given off by the -ray (E₁=1.38 Mev) in emission and collision with the nucleus, is compensated for by the energy obtained due to recoil associated with the emission of the preceding -ray with an energy E₂ = 2.76 Mev. Using a fast coincidence method and amplitude discrimination, coincidences were recorded between the -rays with energies E₁=1.38 Mev and E₂=2.76 Mev. Scattercrs of magnesium and aluminum were alternately placed in the path of the 1.38 Mev -rays. The source was radioactive Na²⁴ in a water solution of NaOH. At an angle of 120 ° between the -rays a strong attenuatlon of the 1.38 Mev -rays was observed; this is attributed to resonance scattering. When the angle between the -rays was varied by 5 °. the strong attenuation of the flux disappeared. The width of the level at 1.38 Mev in Mg²⁴ has been estimated at > 1.6· in^–4 Mev.     

Drawbacks of the Classical Theory of the α-Rossi Method and Its Alternative

Certain contradictions and inaccuracies in the classical theory of the -Rossi stochastic neutron method are pointed out. An alternative theory which is almost free of contradictions and deficiencies of the classical theory is presented.A new implementation regime for the method is proposed to eliminate any influence of the prestart dip on the correlated amplitude in the -Rossi method using modern time-delay analyzers – the scaled start regime, consisting in triggerings of the time-delay analyzer scaled by two, three, or more signals from the starting neutron detector. It is shown that the correlated amplitude contains the ratio of the first and second moments of the number of prompt neutrons in a chain.A new expression is obtained for taking account of the spatial-energy effect in the -Rossi method. The effect differs from the well-known one not only by the energy component but also by a large range of possible values.The possibilities of the -Rossi method for determining the physical parameters of multiplying and nonmultiplying media are considered: , k _p, k, _eff, F, F _s, and D.     

Effective cross sections for fission of U233, U235, Pu239 and Pu240 by neutrons with energies from 30 kev to 5 Mev

Measurements have been made of the absolute values of the effective fission cross sections in U²³³, U²³⁵, Pu²³⁹ and Pu²⁴⁰, using as photoneutron sources Sb + Be ( 30 kev), Na + D₂O ( 250 kev), Na + Be ( 900 kev), a source with a simulated fission-neutron spectrum and Po--Be. The fission cross sections for 30 kev-neutrons are 3.06 ± 0.16, 2.21 ± 0.12 and 1.79 ± 0.11 barns for U²³³, U²³⁵ and Pu²³⁹, respectively. As the neutron energy Is increased from 30 kev to 250 kev the cross sections in U²³³ and U²³⁵ fall off by approximately 35% and then remain almost constant while the cross section in Pu²³⁹ falls off by 12% and then increases. The effective cross sections for fission in Pu²⁴⁰ for 900-kev and 5-Mev neutrons is 1.4 barns and the threshold for fission in Pu²⁴⁰ lies within the limits 250 and 900 kev.In conclusion the authors wish to express their gratitude to P. E. Spivak for help in formulating the problem and a discussion of the results.     

Secondary nuclear reactions in the bombardment of tin by fast protons

A radiochemical method has been used to study the capture of products arising in disintegration of target nuclei.Using the measurements of yields of radioactive isotopes of tellurium (Z=52) and iodine (Z=53) obtained from tin (Z=50) irradiated by protons with energy from 170 to 660 Mev excitation curves are plotted for the secondary reactions which lead to the formation of products with charges 2 and 3 units greater than the charge of the original nucleus. The cross sections for these reactions increases with increasing energy of the incident protons: (, x n) and (Li, xn) are respectively 18.5 ± 5 and 0.17 ± 0.1 mbarns for E_p=170 Mev and 50 ± 6.5 and 1.6 ± 0.5 mbarns for E_p=660 Mev. The cross sections for lithium capture by tin in a comparable proton energy interval are in good agreement with the results of investigations of similar reactions in copper, tin and lead but are found to be 50 times smaller than the cross sections obtained by Marquez and Perlman.The observed cross sections for the secondary lithium capture can be explained only by assuming that these nuclei acquire energies greater than that which can be obtained In evaporation or fission of the target nuclei.Secondary reactions of the (, xn) type can be explained satisfactorily on the basis of an evaporation mechanism for the formation of the helium nuclei.The authors are indebted to B. V. Kurchatov, V. G. Solov'ev, and I. Iu. Levenberg for help in carrying out the present work and to V. P. Dzhelepov, M. G. Meshcheriakov and G. A. Leskin for a number of valuable critical remarks.     

Containment of plasma in a trap with combined magnetic field

The containing properties of an adiabatic trap with a magnetic field increasing in the longitudinal and radial directions are investigated. This field is obtained from a combination of the ordinary mirror field configuration (main field H0) and the field of a system of current-carrying conductors laid parallel to the axis of the trap (stabilizing field H). The conductors are placed uniformly in azimuth around the side walls. The trap is filled with plasma of density n10⁹–10¹⁰ cm^–3 and proton energy T_i5eV (T_e20 eV). The plasma lifetime is measured as a function of H. and the neutral gas pressure. From the results obtained, it is concluded that such combined fields ensure stable containment of the plasma, unbroken by magnetohydrodynamic instabilities [at any rate for = nI/(H²/8) 10^–4]. The stabilization of the instability is confirmed by analysis of the plasma oscillations for various values of H. The disintegration of the plasma is determined by the charge exchange of fast ions in the residual gas; the maximum containment time which can be achieved is 0.06 sec for p = 7.10^–9mmHg. A qualitative picture of the plasma density over the radius of the trap is obtained.Translated from Atomnaya Énergiya, Vol. 17, No. 5, pp. 366–375, November, 1964     

Characteristics of Liquid-Scintillation α Spectrometry

The energy calibration curve in the -particle energy range 4.01–8.77 MeV, suitable for solutions of a liquid scintillator with different light absorption, is constructed. The mechanisms of broadening and asymmetry of the peaks of various actinides are studied. Lists of isotopes, whose content can be measured quantitatively when they are present simultaneously in samples of different origin by liquid-scintillation spectrometry, are given.