D.C. Kaul

Science Applications International Corporation (United States)

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Stephen D. Egbert

University of California, San Diego

F. Dolatshahi

Science Applications International Corporation (United States)

J.T. McGahan

University of Notre Dame

Harry M. Cullings

Radiation Effects Research Foundation

Ronald L. Weitz

Leidos (United States)

James A. Roberts

Baylor University

Robert W. Young

Aintree University Hospitals NHS Foundation Trust

J. Goetz

Masaharu Hoshi

Hiroshima University

J. Klemm

Deutsches Zentrum für Luft- und Raumfahrt e. V. (DLR)

Cooperative Institutions

United States Department of Energy

Leidos (United States)

Hiroshima University

Science Applications International Corporation (United States)

National Cancer Institute

Lawrence Livermore National Laboratory

Helmholtz Zentrum München

Radiation Effects Research Foundation

Ministry of Health Labour and Welfare

Medical Radiological Research Center

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Anthropomorphic phantom radiation dosimetry at 400 m from a fission source

Transactions of the American Nuclear Society (1988)

T. Cousins D.C. Kaul

Kerma

Nuclear data

Mockup

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The Dosimetry System 1986 (DS86) and the Tentative Dosimetry System 1965 (T65D): How Do They Compare, What is Left to Do?

Journal of Radiation Research (1991)

Jennifer Thiessen D.C. Kaul

Until 1987, the Radiation Effects Research Foundation (RERF) and its predecessor organization, the Atomic Bomb Casualty Commission (ABCC), utilized a dosimetry system developed in the sixties, the so-called Tentative Dosimetry System 1965 or T65D1,2), which later, after some revisions, became known as T65DR3). In the late seventies increasing doubt was raised (particularly in the Oak Ridge, Lawrence Livermore, and Los Alamos National Laboratories and at Science Applications International Corporation) on the correctness of the assumptions and the use of models underlying T65D, culminating in two symposia in 1981, one during the annual meeting of the Radiation Research Society in Minneapolis, Minnesota4), and the other one under the aegis of the U.S. Department of Energy in Germantown, Maryland5). Shortly thereafter, a major effort was initiated to evaluate the entire system of dosimetry then extant, and to design a new system if indicated. This undertaking, involving tens of investigators and millions of dollars and yen, resulted in the publication of a thousand-page, two-volume description of a new dosimetry system, christened Dosimetry System 19866). Following publication of these volumes, RERF received data bases and computer programs that form the core of the DS86 computational system currently in use at RERF.

10.1269/jrr.32.suppl_1.1

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Dose and Cell-Survival Calculations in Anthropomorphic Phantoms

Springer eBooks (1984)

D.C. Kaul William H. Scott

10.1007/978-94-009-6048-0_3

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NUCRAC: a code for the estimation of adversary-action consequences in the nuclear power fuel cycle

D.C. Kaul R.L. Ritzman Jerry A Roberts E.S. Sachs

A program sponsored by the Nuclear Regulatory Commission (NRC) and designed to estimate the potential consequences of adversary actions in the nuclear power fuel cycle has been completed. So that the results of this consequence analysis would be comparable to that of the reactor Safety Study (RSS), the methodology described in the RSS and implemented in the Calculation of Reactor Accident Consequences (CRAC) code served as the baseline for consequence evaluation in this study. Four portions of the RSS methodology were modified for use in this study: the atmospheric dispersion model, the inhalation dose factors, the criterion for early mortality from lung dose, and the model for chronic pathways to man. Implementation of these modifications to the CRAC code resulted in the preparation and application of a revised code termed NUCRAC. These modifications are described in detail. Detailed instructions for the operation of NUCRAC are presented in the form of a user-manual. Inputs and outputs for an example calculation are also presented.

RSS

Code (set theory)

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Study of radiation dosage to structural components in nuclear reactors

L.B. Miller R.E. Jarka D.C. Kaul

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Phantom dosimetry calculations for use in radiation-effects correlations. Technical report, 1 April 1983-30 July 1984

D.C. Kaul James A. Roberts Stephen D. Egbert

Models corresponding to an adult Rhesus Monkey and a simple analogue were created in combinatorial geometry for use in Monte Carlo radiation-transport calculations. The complex monkey phantom is based on anatomical measurements of a sectioned cadaver. Adjoint Monte Carlo calculations were performed to obtain the energy- and angle-differential adjoint fluence for the mid-head, mid-thorax locations in both phantoms and active marrow in the complex monkey phantom. The results were also convoluted with free-field spectra for two TRIGA reactor exposure room configurations at the Armed Forces Radiobiological Research Institute, using the VCS code system. Comparisons are made between calculated and measured KERMA values in the simple phantom. Good agreement is obtained. However, it is found that good agreement cannot be obtained using simple scalar coupling.

Kerma

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Transport of initial radiations in air over ground

George D. Kerr J.V. Pace Edgar Mendelsohn W.E. Loewe D.C. Kaul

A time-dependent system of classification is normally used to divide the ionizing radiation from a nuclear explosion into two groups: initial and residual. The initial radiation is the ionizing radiation emitted within the first minute following the detonation of the weapon, and the residual radiation is the ionizing radiation emitted later. Transport calculations for the prompt and delayed radiations were performed separately and then combined at fixed ground locations to obtain the total neutron and gamma-ray fluence, together with their energy and angular distributions. Modeling of the air-over-ground transport for the delayed radiation is a more difficult task. For example, such complex effects as the rapid early-time decay of the fission products, the rise of the fireball, and the blast-enhanced transport of the delayed radiation must be considered. The blast wave from the explosion enhances the transport of the delayed radiations by removing most of the air between the fireball and the shock front. This work uses transport modeling procedures and source term data developed in studies by Science Applications International Corporation (SAIC). In their studies, the delayed neutron and gamma-ray fluences were estimated by means of a one-dimensional ANISN calculation that takes into account the air density profile at a fixed location on the ground at discrete time intervals after the explosion. The effects of ground scattering were then computed separately by means of the VCS code. These transport modeling procedures were verified by applying them to weapon tests where time dependent gamma-ray measurements were made as a function of ground range. Many of the calculations and comparisons of this work involve the use of dosimetric parameter called kerma. Kerma equals the total kinetic energy of all the charged particles liberated by neutrons and gamma rays in a small volume of a given material divided by the mass of the material in that volume element.

Radiation transport

Neutron Transport

Blast wave

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The Air Transport of Radiation (ATR) Code: Development and Testing of ATR5

F. Dolatshahi D.C. Kaul John R. Phillips James A. Roberts

Abstract : The Air Transport of Radiation (ATR) code is the standard model for initial radiation dose (kerma free-in-air) from nuclear weapons in uniform air and air-over ground geometries. ATR predicts free field dose from neutron, gamma rays, from a parameterized data base. This report describes modifications made to the code to provide for improved uniform air and air-over-ground dose distributions. Effects of atmospheric moisture are now accounted for. The fission product radiation model has been modified to include contributions from individual fissile isotopes and has been provided with empirical corrections to allow it to better replicate observed dose values. The resulting version of the code is ATR5. Keywords: Radiation transport; Nuclear weapons; Dose; Kerma; Neutrons; Gamma rays; Fission products.

Kerma

Fissile material

Nuclear fission product

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Delfic fallout prediction code radiation physics package upgrade. Technical report, 26 July 1888-13 March 1992

James A. Roberts D.C. Kaul F. Dolatshahi J.T. McGahan

The DEfense Land Fallout Interpretive Code (DELFIC) is the Defense Nuclear Agency standard phenomenology code for computing fallout environments from nuclear weapons detonations. This report describes the results of a program to update the DELFIC radiation physics package, that portion of the code which calculates the radioactive decay of initial fission product inventories and their contribution to radiation exposure rate. Updates include corrections to errors in following multi-path decay chains, the inclusion of ENDF/B-6 decay constant data and the expansion of the number of radionuclides which contribute to direct exposure to irradiation from surface contamination.

Nuclear fission product

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FIIDOS - a computer code for the computation of Fallout Inhalation and Ingestion Dose to Organs: computer user's guide. Technical report, 1 November 1983-15 April 1985

Stephen D. Egbert D.C. Kaul J Klemm J. C. Phillips

The computer code Fallout Inhalation and Ingestion Dose to Organs (FIIDOS) calculates the 50-year radiation-dose commitment to 20 body organs that would result from the inhalation or ingestion of nuclear weapon fallout. FIIDOS considers the production and radioactive decay of the radionuclides present in the nuclear fallout (including fission products, activation products, and actinides) and accommodates radionuclide-specific fractionation data. Several types of radiation intensity and activity measurements, with selectable sets of dose-conversion factors, form the basis for dose calculations. Sample problems and the FORTRAN program listing are included.

Fortran

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