25 Matching Results

Search Results

Advanced search parameters have been applied.

in creator/contributor: "Lazareth, O.W."

open access

Effect of polarized fusion on the neutronics of a mirror fusion reactor

The conclusions of this study are that for the anisotropic neutron source: (1) the radiation damage in the first wall is reduced, and (2) both the fraction of energy (heat) deposited in the hot interior, and the tritium breeding ratio do not change significantly. These conclusions apply to this particular blanket design only. In order to increase the fractional heating and the breeding ratio, the blanket design must be modified.

Date: January 1, 1983

Creator: Takahashi, H. & Lazareth, O.W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Particle bed reactor propulsion vehicle performance and characteristics as an orbital transfer rocket

The particle bed reactor designed for 100 to 300 MW power output using hydrogen as a coolant is capable of specific impulses up to 1000 seconds as a nuclear rocket. A single space shuttle compatible vehicle can perform extensive missions from LEO to 3 times GEO and return with multi-ton payloads. The use of hydrogen to directly cool particulate reactor fuel results in a compact, lightweight rocket vehicle, whose duration of usefulness is dependent only upon hydrogen resupply availability. The L… more

Date: January 1, 1986

Creator: Horn, F. L.; Powell, J. R. & Lazareth, O. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

HYFIRE: a tokamak- high-temperature electrolysis system

Brookhaven National Laboratory is involved in a conceptual design study of a commercial nuclear power system which utilizes high-temperature electrolysis to produce synthetic fuels. The system is called HYFIRE. It includes a tokamak fusion power reactor supplying electrical and thermal energy to an array of electrolytes. The electrolytes produce hydrogen which can be used either directly as a fuel or in the production of hydrocarbons. The purpose of the study is to provide a mechanism for DOE t… more

Date: January 1, 1980

Creator: Lazareth, O.W.; Fillo, J.A. & Powell, J.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

One- and two-dimensional heating analyses of fusion synfuel blankets

Comparisons between one- and two-dimensional neutronics and heating analyses were performed on a Brookhaven designed fusion reactor blanket featuring synthetic fuel production. In this two temperature region blanket design, the structural shell is stainless steel. The interior of the module is a packed ball of high temperature ceramic material. The low temperature shell and the high temperature ceramic interior are separately cooled. Process steam (approx. 1500/sup 0/C) is then produced in the … more

Date: January 1, 1979

Creator: Tsang, J.S.K.; Lazareth, O.W. & Powell, J.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Two-dimensional heating analysis of fusion blankets for synfuel production

Fusion reactors could be used to generate electric power and produce synthetic fuels with relatively high efficiencies (about 60%). A two temperature zone blanket coupled to a high temperature electrolysis system would be used. An important parameter in this system is the ratio of the fusion neutron kerma energy absorbed by the hot interior (the higher temperature zone) to the total energy/fusion. This parameter is calculated as approximately .5 for both a one and two-dimensional model of the b… more

Date: January 1, 1978

Creator: Lazareth, O.W.; Tsang, J.S.K. & Powell, J.R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Calculation of radiation damage in insulators for fusion reactors

The MORSE neutron transport code has been used to characterize the neutron and gamma ray fluxes in a typical irradiation cave from a Li(d,n) neutron source. Recoil-atom damage and gas generation have been evaluated for Al/sub 2/O/sub 3/ and Si/sub 3/N/sub 4/ using the damage program DON.

Date: January 1, 1979

Creator: Dell, G.F.; Berry, H.C.; Goland, A.N. & Lazareth, O.W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Cosmogenic Neutron-Capture-Produced Nuclides in Stony Meteorites

The distribution of neutrons with energies below 15 MeV in spherical stony meteoroids is calculated using the ANISN neutron-transport code. The source distributions and intensities of neutrons are calculated using cross sections for the production of tritium. The meteoroid's radius and chemical composition strongly influence the total neutron flux and the neutron energy spectrum, while the location within a meteoroid only affects the relative neutron intensities. Meteoroids need to have radii o… more

Date: January 1, 1985

Creator: Spergel, M. S.; Reedy, R. C.; Lazareth, O. W. & Levy, P. W.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Determining temperature distributions inside a nuclear reactor

In a nuclear reactor, energetic particles are generated in the fuel region during the fission process. As these particles are slowed down and absorbed by material in the reactor, this material is heated. The material is cooled by convection of hydrogen flowing through coolant channels. The primary contributions to this heating process are neutrons and gamma rays. The neutrons have a short mean free-path. They travel a relatively short distance between collisions with nuclei of surrounding mater… more

Date: August 1, 1992

Creator: Schmidt, E.; Mughabghab, S. F. & Lazareth, O. W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Determining temperature distributions inside a nuclear reactor

Date: August 1, 1992

Creator: Schmidt, E.; Mughabghab, S. F. & Lazareth, O. W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Results of parametric neutronic studies for high-temperature blankets with breeding

Previous conceptual studies have been extended to examine a wide range of possible blanket configurations. The overall goals of this study have been to achieve neutronically viable blanket combinations that obtain an average breeding ratio (BR) of at least 1.1 and a sufficiently high fraction of fusion energy, Q/sub FRAC//sup HI/ (20% HTE High Temperature Heat) in the HTE process steam. The present studies have converged on the most attractive blanket option. After a preliminary and a secondary… more

Date: January 1, 1981

Creator: Makowitz, H; Lazareth, O W; Powell, J R & Fillo, J A

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fusion blankets for high-efficiency power cycles

The efficiencies of blankets for fusion reactors are usually in the range of 30 to 40%, limited by the operating temperatures (500/sup 0/C) of conventional structural materials such as stainless steels. In this project two-zone blankets are proposed; these blankets consist of a low-temperature shell surrounding a high-temperature interior zone. A survey of nucleonics and thermal hydraulic parameters has led to a reference blanket design consisting of a water-cooled stainless steel shell around … more

Date: January 1, 1980

Creator: Usher, J L; Lazareth, O W; Fillo, J A; Horn, F L & Powell, J R

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Analysis of the start-up and control of a particle bed reactor

This study describes the modeling of start-up transients in Particle Bed Reactors (PBR) for burst electric power. Two computer programs have been developed to analyze the start-up process. The first program (named KINETIC) analyzes the entire fuel element, calculating time dependent solutions for power and the temperature distribution in the packed bed. The second program (named SPHEAT, for Spherical Heating) calculates time-dependent temperatures inside individual, cladded fuel particles. The … more

Date: January 1, 1987

Creator: Lazareth, O. W.; Araj, K. J.; Horn, F. L.; Ludewig, H. & Powell, J. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Human round trip to Mars: Six months and radiation safe. Revision

We describe a different type of round trip to Mars, using a combination of spacecraft. Compared to typical proposals, this flight is relatively fast and relatively safe from biological radiation dosage. Our study is concerned with the trip from Earth orbit to Mars orbit. Four spacecraft are required for the round trip. The crew spends most of their time on board a comparatively large, well shielded spacecraft (LC) which is in free (non-powered) orbit about the sun. The crew travels from Earth o… more

Date: December 31, 1991

Creator: Lazareth, O. W.; Schmidt, E.; Ludewig, H. & Powell, J. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Production rates of cosmogenic nuclides in stony meteorites

Monte Carlo calculations of /sup 26/Al and /sup 53/Mn production due to spallation induced by cosmogenic protons in model meteorite composition similar to L Chondrite has yielded predictions which are consistent with the observed decay rates in L Chondrite stony meteorites. The calculated /sup 26/Al production rate (54 dpm/kg) in a 1 m diameter meteorite is within 1/2 S.D. of the mean (49 +- 11 dpm/kg) taken from 100 bulk determinations in L Chondrite samples compiled in Nishiizumi (1987). Simi… more

Date: January 1, 1989

Creator: Divadeenam, M.; Gabriel, T.A.; Lazareth, O.W.; Spergel, M.S. & Ward, T.E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Low activity blankets for experimental power reactors

Results of current studies aimed at the development of low activity blankets for Tokamak experimental power reactors are presented. First wall loadings in the range of 0.5 to 1.0 MW(th)/m$sup 2$ have been assumed. Blanket designs are developed for both circular plasma reactors (R = 6.25m, a = 2.1m) and non-circular plasma reactors (R = 4.0m, a = 1.0m, b = 3.0m). For each of these two reactor choices, two blanket options are described. 1) In the first option, the blanket is thick graphite block … more

Date: January 1, 1975

Creator: Benenati, R.; Fillo, J.; Lazareth, O.W.; Majeski, S.; Powell, J.R. & Tichler, P.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Damage parameters for non-metals in a high energy neutron environment

Simulation of radiation damage induced in monatomic and binary non-metals by FMIT and fusion neutrons is described. Damage produced by elastic scattering of recoil atoms and by ionization-assisted processes has been evaluated using the damage program DON. Displacement damage from gamma rays has been evaluated by using the technique of Oen and Holmes. A comparison of damage for an anticipated FMIT radiation environment generated by a coupled n-..gamma.. transport calculations and a fusion spectr… more

Date: January 1, 1980

Creator: Dell, G F; Berry, H C; Lazareth, O W & Goland, A N

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

A particle bed reactor based NTP in the 112,500 N thrust class

This paper discusses the application of a Particle bed Reactor (PBR) to a 112,500 N thrust Nuclear Thermal Propulsion (NTP) Engine. The method of analysis is described, followed by a presentation of the results. It is concluded that the PBR would result in a very competitive NTP engine. In addition, due to the high power densities possible with a PBR, high thrust/weight ratios are possible. This conclusion can be used to satisfy a variety of mission goals.

Date: April 1, 1993

Creator: Ludewig, H.; Powell, J. R.; Lazareth, O. W. Jr. & Todosow, M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Neutronics and mass transport in a chemical reactor associated with controlled thermonuclear fusion reactor

The formation of ozone from oxygen and the dissociation carbon dioxide to carbon monoxide and oxygen is studied in a gamma-neutron chemical process blanket associated with a controlled thermonuclear reactor. Materials used for reactor tube wall will affect the efficiency of the energy absorption by the reactants and consequently the yield of reaction products. Three kinds of materials, aluminum, stainless steel and fiber (Al/sub 2/O/sub 3/)-aluminium are investigated for the tube wall material … more

Date: November 28, 1976

Creator: Dang, V D; Steinberg, M; Lazareth, O W & Powell, J R

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Comparison of preliminary D-T and ''catalyzed'' D-D system studies

The purpose of the research currently underway is to provide technological and eventual economic comparison of a reference D-T reactor to a ''catalyzed'' D-D reactor. Two separate reactor designs are delineated and examined for this purpose. These systems include plasma parameters, blanket and shield configurations, magnetic coil configurations, and power conversion systems, including a divertor-direct convertor system for the D-D design. The initial conclusions reached are … more

Date: January 1, 1976

Creator: Usher, J L; Powell, J R; Fillo, J A & Lazareth, O W

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fusion blanket for high-efficiency power cycles

The efficiencies of blankets for fusion reactors are usually in the range of 30 to 40%, limited by the operating temperature (500/sup 0/C) of conventional structural materials such as stainless steels. In this project two-zone blankets are proposed; these blankets consist of a low-temperature shell surrounding a high-temperature interior zone. A survey of nucleonics and thermal hydraulic parameters has led to a reference blanket design consisting of a water-cooled stainless steel shell around a… more

Date: January 1, 1980

Creator: Usher, J. L.; Powell, J. R.; Fillo, J. A.; Horn, F. L.; Lazareth, O. W. & Taussig, R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Fusion blankets for high efficiency power cycles

Definitions are given of 10 generic blanket types and the specific blanket chosen to be analyzed in detail from each of the 10 types. Dimensions, compositions, energy depositions and breeding ratios (where applicable) are presented for each of the 10 designs. Ultimately, based largely on neutronics and thermal hyraulics results, breeding an nonbreeding blanket options are selected for further design analysis and integration with a suitable power conversion subsystem.

Date: April 1, 1980

Creator: Powell, J R; Fillo, J A; Horn, F L; Lazareth, O W & Usher, J L

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Blanket options for high-efficiency fusion power

Date: January 1, 1980

Creator: Usher, J L; Lazareth, O W; Fillo, J A; Horn, F L & Powell, J R

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

HYFIRE: a tokamak-high-temperature electrolysis system

Brookhaven National Laboratory (BNL) is carrying out a comprehensive conceptual design study called HYFIRE of a commercial fusion Tokamak reactor, high-temperature electrolysis system. The study is placing particular emphasis on the adaptability of the STARFIRE power reactor to a synfuel application. The HYFIRE blanket must perform three functions: (a) provide high-temperature (approx. 1400/sup 0/C) process steam at moderate pressures (in the range of 10 to 30 atm) to the high-temperature elect… more

Date: January 1, 1980

Creator: Fillo, J A; Powell, J R; Steinberg, M; Benenati, R; Horn, F; Isaacs, H et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

HYFIRE: a tokamak-high-temperature electrolysis system

Date: January 1, 1980

Creator: Fillo, J.A.; Powell, J.R.; Steinberg, M.; Benenati, R.; Horn, F.; Isaacs, H. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department