WorldCat Identities

Toppel, B. J.

Overview
Works: 21 works in 33 publications in 1 language and 149 library holdings
Roles: Author, Editor
Classifications: QC793.5.F32,
Publication Timeline
.
Most widely held works by B. J Toppel
Multigroup diffusion theory formulation of the calculation of the mean square slowing down distance in an infinite medium by B. J Toppel( )

2 editions published in 1960 in English and held by 27 WorldCat member libraries worldwide

Simple expressions for the mean square distance from a point fission source for slowing down past a given energy and for the mean square distance of neutrons that belong to a given energy group are derived within the framework of multigroup diffusion theory. The expressions may be applied to systems having arbitrary group transfer cross sections
The coupled aspects of a fast-thermal critical : ZPR-V by B. J Toppel( )

2 editions published in 1957 in English and held by 26 WorldCat member libraries worldwide

ZPR-V is a zero-power, coupled fast-thermal critical assembly involving a dilute fast core and a H/sub 2/O-moderated, enriched U thermal annulus. The two regions are coupled through a natural U isolation blanket. This facility is useful in studying some of the properties of dilute fast reactor systems as well as those of coupled fast-thermal power breeders. Recent emphasis has been on the latter aspect of the problem and an investigation of the coupled aspects of the system has been made. An important parameter in the coupling concept is the division of reactivity. This can be determined by means of fast fuel substitutions and 1/v poisoning of the thermal annulus in conjunction with theoretical calculations. Auxiliary information obtained in such a procedure is the fast fuel worth throughout the core and the prompt neutron lifetime of the whole system. A second important pnrameter, S/sub 1/S/sub 2/, is the relative number of neutrons emitted per unit time due to fast and slow fissions. Information regarding this quantity can be obtained with the aid of U/sup 235/ and U/sup 238/ fission distributions. Measurenments of thc above parameters were made for the case of a U/sup 238/:U/sup 235/ atomic ratio of 5:1 in the fast core and a 1-in. isolation blanket. The fractions of reactivity in the fast core, blanket, and annulus are, respectively, 24, 14, and 61%; the prompt lifetime is 39.0 plus or minus 3.0 mu sec; the ratio S/sub 1/S/sub 2/ is 0.43. (auth)
IBM-704 codes for reactivity step calculations (RE-126 and RE-135) by C. E Cohn( )

2 editions published in 1960 in English and held by 23 WorldCat member libraries worldwide

The code RE-128 assumes all delayed-neutron precursors in equilibrium at the time of the step, while the code RE-135 allows cases with non-equilibrium precursors to be handled. RE-126 can handle the case of zero final reactivity. Both codes are written in FORTRAN language
A high pressure proportional counter for fast neutron spectroscopy by S. D Bloom( )

2 editions published in 1955 in English and held by 19 WorldCat member libraries worldwide

Conceptual design of a coupled breeding superheating reactor, CBSR by R Avery( )

1 edition published in 1961 in English and held by 15 WorldCat member libraries worldwide

The conceptual design of the Coupled Breeding Superheating Reactor, CBSR, for achieving a positive breeding gain and for producing 65 Mw of electric power is presented. The design combines a steam-cooled fast region and a non-boiling pressurized light-water-cooled thermal region. The advantage offered by this arrangement as compared with that using a solid moderator in the thermal zone is that, if a power excursion occurs, the water will increase the void content and tend to limit the excursion. The total reactor power is 216 Mwt, of which 163 Mwt is used to superheat steam as it passes through the fast regions of the reactor and 53 Mwt is transferred to the pressurized water
The argonne-revised thermos code by B. J Toppel( )

2 editions published in 1965 in English and held by 8 WorldCat member libraries worldwide

The Argonne reactor computation (ARC) system( Book )

2 editions published in 1967 in English and held by 4 WorldCat member libraries worldwide

A user's guide for the REBUS-3 fuel cycle analysis capability by B. J Toppel( )

1 edition published in 1983 in English and held by 4 WorldCat member libraries worldwide

REBUS-3 is a system of programs designed for the fuel-cycle analysis of fast reactors. This new capability is an extension and refinement of the REBUS-3 code system and complies with the standard code practices and interface dataset specifications of the Committee on Computer Code Coordination (CCCC). The new code is hence divorced from the earlier ARC System. In addition, the coding has been designed to enhance code exportability
MC2, a code to calculate multigroup cross sections by B. J Toppel( Book )

2 editions published in 1967 in English and held by 3 WorldCat member libraries worldwide

The Argonne-revised thermos code by B. J Toppel( Book )

3 editions published in 1965 in English and held by 3 WorldCat member libraries worldwide

The speed and two-bank memory capacity of the CDC-3600 computer at Argonne has prompted a reprogramming effort to relax some of the original restrictions on dimensions of variables, and to provided a much more elaborate output edit. In connection with the revised output edit, the associated cross-section library preparation code, LIBP, was modified. The revised codes to be described here are written entirely in 3600 FORTRAN
Coupled fast-thermal power breeder critical experiment by R Avery( Book )

1 edition published in 1958 in English and held by 3 WorldCat member libraries worldwide

Some physics aspects of the plutonium experiment in EBWR by B. J Toppel( Book )

1 edition published in 1965 in English and held by 2 WorldCat member libraries worldwide

The potential advantages of plutonium recycle have long been recognized. In the fast-reactor area, these advantages are primarily, if not exclusively, related to the possibility of achieving a fuel cycle with a substantial breeding gain
MC exp 2-2 : a code to calculate fast neutron spectra and multigroup cross sections by H Henryson( Book )

2 editions published in 1976 in English and held by 2 WorldCat member libraries worldwide

The Argonne Reactor Computation (ARC) System by B. J Toppel( Book )

2 editions published in 1967 in English and held by 2 WorldCat member libraries worldwide

The reactor physicist is primarily concerned with solving the Boltzmann equation for a particular physical configuration. In addition, the reactor designer is involved with numerous adjunct problems to further define the interaction of the reactor with its environment. In this area, for example, the problem will be influenced by the engineering realities of the physical system
MC²: A code to calculate multigroup cross sections by B. J Toppel( Book )

2 editions published in 1967 in English and held by 2 WorldCat member libraries worldwide

Cross sections in the resolved resonance region are calculated using Doppler-broadened line shapes with an equivalence relation to account for heterogeneities. The interference between resonance and potential scattering and the interference with overlapping resonances in other isotopes are allowed
Some physics aspects of the plutonium experiments in EBWR by B. J Toppel( Book )

1 edition published in 1965 in English and held by 1 WorldCat member library worldwide

The coupled aspects of a fast-thermal critical: ZPR-V by B. J Toppel( Book )

1 edition published in 1957 in English and held by 1 WorldCat member library worldwide

ZPR-V is a zero-power, coupled fast-thermal critical assembly involving a dilute fast core and a H2O-moderated, enriched U thermal annulus. The two regions are coupled through a natural U isolation blanket. This facility is useful in studying some of the properties of dilute fast reactor systems as well as those of coupled fast-thermal power breeders. Recent emphasis has been on the latter aspect of the problem and an investigation of the coupled aspects of the system has been made. An important parameter in the coupling concept is the division of reactivity. This can be determined by means of fast fuel substitutions and 1/v poisoning of the thermal annulus in conjunction with theoretical calculations. Auxiliary information obtained in such a procedure is the fast fuel worth throughout the core and the prompt neutron lifetime of the whole system. A second important parameter, S₁/S₂ is the relative number of neutrons emitted per unit time due to fast and slow fissions. Information regarding this quantity can be obtained with the aid of U-235 and U-238 fission distributions. Measurements of the above parameters were made for the case of a U-235:U-238 atomic ratio of 5:1 in the fast core and a 1-in. isolation blanket. The fractions of reactivity in the fast core, blanket, and annulus are, respectively, 24, 14, and 61%; the prompt lifetime is 39.0 plus or minus 3.0 mu sec; the ratio S₁/S₂ is 0.43
Engineering physics production code implementation on the Cray X-MP by C. H Adams( Book )

1 edition published in 1989 in English and held by 1 WorldCat member library worldwide

Improved algorithms for the calculation of resolved resonance cross sections with applications to the structural Doppler effect in fast reactors [microform] by R. N Hwang( Book )

1 edition published in 1980 in English and held by 1 WorldCat member library worldwide

To illustrate the accuracy and efficiency of the improved RABANL algorithms and resonance screening techniques, calculations have been performed for two systems, the first with a composition typical of the STF converter region and the second typical of an LMFBR core composition
Safety analysis associated with the plutonium recycle experiment in EBWR by B. J Toppel( Book )

1 edition published in 1966 in English and held by 1 WorldCat member library worldwide

The Experimental Boiling Water Reactor (EBWR) was originally constructed to demonstrate the feasibility of a direct-cycle, natural-circulation, boiling-water reactor integrated power plant. The reactor was designed to produce 20,000 kW of heat in the form of 600-psig saturated steam which was fed directly to a turbogenerator, generating about 5,000 kW of electricity. This power level was considered as a minimum value for producing useful information which could be extrapolated and used in the design of large, central-station power plants. The reactor achieved criticality during December 1956, and began full-power operation at 20 MWt on December 29, 1956
 
moreShow More Titles
fewerShow Fewer Titles
Audience Level
0
Audience Level
1
  Kids General Special  
Audience level: 0.76 (from 0.66 for Coupled fa ... to 0.87 for MC2, a cod ...)

Languages
English (32)