Eight computer programs make up a nine volume synthesis containing two design methods for nuclear rocket radiation shields. The first design method is appropriate for parametric and preliminary studies, while the second accomplishes the verification of a final nuclear rocket reactor design

Capo, M. A.

Disney, R. K.

Jordan, T. A.

Soltesz, R. G.

Woodsum, H. C.

English

NASA Technical Reports Server

rJune 1969
	
Brief 69-10158 
•	
. AEC-NASA TECH BRIEF 
AEC-NASA Tech Briefs describe innovations resulting from the research and development program 
of the U.S. AEC or from AEC-NASA interagency efforts. They are issued to encourage commercial 
application. Tech Briefs are published by NASA and may be purchased, at 15 cents each, from 
the Clearinghouse for Federal Scientific and Technical Information, Springfield, Virginia 22151. 
Synthesis of Calculational Methods for Design and Analysis

of Radiation Shields for Nuclear Rocket Systems 
The problem: 
To devise a computer prograni for the complete 
initial and final design of nuclear rocket radiation 
shields. 
The solution: 
Eight computer programs making up a nine volume 
synthesis containing two design methods. The "early 
design" method is appropriate for parametric and 
preliminary reactor design studies, while the "final 
design" method accomplishes the verification of a final 
nuclear rocket reactor design. 
How it's done: 
Both design niethocis begin with the initial program, 
POINT, which contains the basic microscopic cross 
section library. In addition to POINT, the early de-
sign method contains three programs. its important 
features are: flexibility in geometry and usage; con-
venience and usefulness of output; and nominal run-
ning time. The final design method, made up of five 
programs plus POINT, is highly accurate and has 
detailed output such as energy and angular distri-
butions. 
The eight programs used are: 
(I) POINT (Preparation of Input for Transport) 
Program. This program calculates macroscopic cross 
sections readily usable in the transport programs, 
TAPAT and ODD-K. This calculation is achieved by 
employing a built-in library of region independent 
neutron and gamma ray microscopic cross sections. 
The program also calculates response functions as 
punched card output for use in both the TAPAT and 
NAGS programs to calculate, for example, neutron 
and gamma ray energy deposition, fixed neutron 
sources, or prompt and secondary gamma ray sources.
(2) TA PA T (The Analysis Program and Trans-
port) Program System. This program system provides 
a complete, neutron and photon, one-dimensional ra-
diation analysis of a reactor system in a single com-
puter run. 
(3) KA P-V (Point Kernel Attenuation) Program. 
This program employs the point kernel method to 
calculate radiation levels at detector points located 
within or outside a complex radiation source geometry 
describable by a combination of quadratic surfaces. 
This program can be used, for example, to calculate 
gamma ray and/or fast neutron flux, dose, or heating 
rate. Three optional fast neutron attenuation func-
tions are included: ( I ) a modified Albert—Welton 
function; (2) a bivariant polynomial expression for 
computing neutron spectra using infinite media mo-
ments data; and (3) a monovariant polynomial ex-
pression for computing neutron spectra using infinite 
media moments data. The program . handles either 
cylindical, spherical, disk, line or point sources. 
(4) TIC-TOC-TOE (Temperature in the Coolant 
Tank and Other Calculations and for the Thermal 
Neutron Originating Energy) Program. This program 
performs rapid calculations of heating rate distribu-
tions in on-axis liquid hydrogen propellant tanks. 
Basic heating rate data are interpolated from curve-
fits of M. 0. Burrell's Monte Carlo data which are 
built into the program. 
(5) ODD-K (Two-Dimensional Transport) Pro-
gram. This program is the Westinghouse Astronuclear 
Laboratory modification of the Los Alamos Scientific 
Laboratory discrete ordinate transport program, DDK. 
The ODD-K program numerically solves the Boltz-
mann transport equation using a multigroup, discrete 
(continued Overleaf) 
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https://ntrs.nasa.gov/search.jsp?R=19690000158 2020-03-16T17:40:07+00:00Z
direction representation of the particle flux in a two-
dimension (R–Z, R–e, or X–Y) geometry description 
of a reactor. ODD-K performs photon, as well as 
neutron, transport analysis and, in conjunction with 
the NAGS and DAFT codes, it provides a method for 
obtaining neutron and photon spatial and energy dis-
tributions throughout the reactor system, and spatial, 
energy, and angular distributions of leakage fluxes at 
the surface of the reactor system. 
(6) NAGS (Calculations of Neutron and Gamma 
Ray Source. and Energy Deposition in Two-Dinien-
sional Geometries) Program. This program is a series 
of routines which process multigroup neutron and 
photon energy fluxes 'for two-dimensional (R, Z or R, 
o) geometry models. The NAGS program provides: provides: 
(1) neutron and photon energy sources and distribu-
tions for use in point kernel, Monte Carlo, and photon 
transport analyses, (2) neutron and gamiiia ray dose 
rates, and (3) energy deposition data for use in sub-
sequent thermal analyses. 
(7) DAFT (Preparation of ODD-K Angular Flux 
Tapes) Program. This program is the data processing 
routine which prepares angular, spatial, and energy 
distribution data for input to the FASTER Monte 
Carlo program from the surface angular leakage flux 
data of the two-dimensional transport program 
ODD-K. 
(8) Faster Monte Carlo (A Fortran Analytic Solu-
tion of the Transport Equation by Random Sampling) 
Program. This program calculates energy-dependent 
neutron or photon fluxes at points, surfaces, and
regions of complex geometries. FASTER contains all 
the data processing routines required for a wide variety 
of nuclear vehicle applications. FASTER deals with 
the entire spectrum of particle energies simultane-
ously. 
Notes: 
1. This program is written in FORTRAN IV and 
MAP for use on IBM 7094 computer. 
2. Although this set of programs has been designed 
primarily for use by personnel involved in the 
design and analysis of nuclear rocket radiation 
shields, some of the individual programs can be 
used by scientists involved in basic nuclear and 
nuclear reactor research. 
3. Inquiries concerning this program may be 
made to:
COSMIC 
Computer Center 
University of Georgia 
Athens, Georgia 30601 
Reference: B69-10158 
Patent status: 
No patent action is contemplated by NASA. 
Source: TA PAT R. K. Disney and R. G. Soltesz 
KAI R. K. Disney and M. A. Capo 
TIC-TOC-TOE—H. C. Woodsuni and T. A. Jordan of 
Westinghouse Astronuclear Laboratory 
under contract to 
Marshall Space Flight Center 
and AEC-NASA Space Nuclear Propulsion Office 
(MFS-14447andNUC-10192)
. 
. 
Brief 69-1,0158	 Category 06


Synthesis of calculational methods for design and analysis of radiation shields for nuclear rocket systems

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