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The UK Department of the Environment (DOE), London, England, through the NEADB contributed this code system which provides an estimate of the subsequentradiological risk to man by simulating the ground water mediated movement ofradionuclides from underground facilities for the disposal of low and intermediatelevel wastes to the accessible environment. The simulated timescales are usuallywithin the range 103 to 107 years. SYVAC is capable of modelling both shallowdisposal facilities and deep disposal facilities. It includes both vault and geospheresubmodels.
Los Alamos National Laboratory, Los Alamos, New Mexico, contributed a newversion of this Monte Carlo N-particle transport code system. MCNP is ageneral-purpose, continuous-energy, generalized geometry, time-dependent, coupledneutron-photon-electron Monte Carlo transport code system. MCNP4C is the firstmajor release of MCNP since version 4B (February 4, 1997). The major new featuresinclude:
MCNP is operable on Cray computers under UNICOS, workstations under Unix or PCs under Linux, Windows NT/9xPCs, and Vax computers under VMS. Compilation requires both Fortran77 and ANSI C standard compilers. The sourcecan be compiled with g77 on PCs running Red Hat Linux. Executables are included only for PCs running Windows; allother systems require a Fortran compiler. The PC executables were created in a DOS window of Windows 98 withDigital Visual Fortran Professional Edition 6.0A Fortran 90 compiler on a Pentium II. RSICC tested this release onseveral Unix workstations (IBM RS/6000, Sun, HP, DEC, and SGI); on a Pentium III running Red Hat Linux Version 6.1;on a Pentium II in a DOS window of Windows 98 with Digital Visual Fortran Professional Edition 6.0A Fortran 90compiler with QuickWin plots; and on a Pentium II with Lahey/Fujitsu Fortran 95 Version 5.50 compiler withWinteracter Starter Kit.
The electronic documentation, source codes, test problems, executables, and installation scripts are distributed onCD-ROM and can be read under either Windows or UNIX operating systems. As a convenience to users, theDLC-200/MCNPDATA library is included on the distribution media. The cross sections are in ASCII mode in the Unixfile and in binary mode for PC Windows users. References: Readme.txt (April 2000) and LA-13709-M (April 2000).Fortran 77 or 90 and C; Unix workstations, Intel-based Pentium PC, Cray, and Vax. (C00700ALLCP00).
Gesellschaft f. Reaktorsicherheit (GRS) mbH, Garching, West Germany, through theNEA DB contributed this code system based on a non-linear theoretical modeldescribing the steady-state and transient behavior of a vertical natural-circulationU-tube steam generator together with its main steam system. The steam generatorconsists of a heat exchange section, a top plenum, a down-comer region and a mainsteam system (with a sequence of relief and/or safety valves, isolation, bypass,turbine-trip and turbine-control valves and a steam turbine). The theoretical modelconsists of a set of analytical state and nonlinear ordinary first-order differentialequations.
UTSG was tested at the NEA Data Bank on an IBM 3033 under MVS. With minor source changes, it was executed on anIBM RS/6000 at RSICC. A Fortran compiler is required. The package is transmitted on a DS/HD diskette which includesthe Fortran source and test case transmitted in both DOS and Unix compressed formats. Reference: GRS-A-426 (March1980). IBM 3033; Fortran IV (P00379I303300).
Through the NEA Data Bank, ORNL contributed this code system for analysis ofsteam turbine cycles supplied by light-water reactors. ORCENT-2 performs heat andmass balance calculations at valves-wide-open design conditions, maximumguaranteed rating conditions, and an approximation of part-load conditions for steamturbine cycles supplied with throttle steam, characteristic of contemporary light-waterreactors. The program handles both condensing and back-pressure turbine exhaustarrangements. Turbine performance calculations are based on the General ElectricCompany method for 1800-rpm large steam turbine-generators operating withlight-water-cooled nuclear reactors. Output includes all information normally shownon a turbine-cycle heat balance diagram.
Los Alamos National Laboratory, Los Alamos, New Mexico, contributed thesecross-section libraries for use with Version 4C and later of the MCNP transport code.These data provide a comprehensive set of cross sections for a wide range of radiationtransport applications using the Monte Carlo code package CCC-700/MCNP4C.Documentation is available at:
A wide variety of continuous-energy, discrete, multigroup, thermal and dosimetryneutron data libraries are available in this release. The continuous-energy neutron data libraries available include:ENDF60, RMCCS, RMCCSA, ENDF5U, ENDF5P, NEWXS, ENDF5MT, MISC5XS, ENDL85, KIDMAN, 100XS,URES, ENDF6DN, ENDF62MT, and ENDL92. The discrete neutron data libraries include: NEWXSD, DRMCCS, andDRE5. The multigroup neutron data library is MGXSNP, and the thermal S(alpha, beta) libraries are TMCCS andTHERXS. The neutron dosimetry libraries are 531DOS, 532DOS, and LLLDOS. The photon transport libraries areMCPLIB and MCPLIB02, and the electron libraries are EL and EL03. The photon and electron data libraries contain datafor elements having Z
The data library ENDF5MT contains data previously available in the library EPRIXS, along with the U600K data library.The data library MISC5XS contains corrected data for ENDF/B-V based Zr as described below, and the librariespreviously known as IRNAT, MISCXS, ARKRC, TM169, GDT2GP, and T2DDC. The ENDF/B-V Zr data has beencorrected for five ZAID's from the libraries RMCCS, DRMCCS, ENDF5P, DRE5, and EPRIXS. These five data libraries(URES, ENDF6DN, ENDF62MT, ENDL92, and EL03) are newly released. Please consult the README file and themore detailed documentation provided for descriptions of these libraries.
Dr. Walter H. Zinn , 93, died at a hospital in Clearwater, Florida, February 14, 2000. He was born December 10, 1906,in Kitchner, Ontario, Canada. He received BA and MA Degrees from Queens University, Kingston, Ontario, and a Ph.Din Physics from Columbia University, New York City. Dr. Zinn was internationally known for his contributions inphysics and reactor engineering. In the mid 30s he collaborated with Leo Szilard on an experiment crucial to proving thefeasibility of the fission chain reaction, the measurement of the number of prompt neutrons emitted per uranium fission.He was a leader in Enrico Fermi's wartime team which constructed the world's first nuclear reactor. He headed one of theteams in charge of the construction of the CP-1 reactor and was subsequently responsible for the design and constructionof the world's first heavy-water moderated reactor--CP-3--which was placed in operation in 1944.
Dr. Zinn was named the first director of the Argonne National Laboratory in 1946 and served in that capacity for tenyears. He made significant contributions to the design and development of a number of nuclear reactors, including theExperimental Breeder Reactor No. 1 (nicknamed ZIP for Zinn's Infernal Pile), which produced the first electricity fromnuclear energy in 1951 and first demonstrated the breeding of nuclear fuel; the Submarine Thermal Reactor, the prototypefor the power plant of Nautilus, the first nuclear-powered submarine; the Savannah River Reactors for plutoniumproduction; the Argonne Heavy Water Research Reactor, or CP-5; the Borax Nuclear Power Plant, the first boiling waterreactor; the Experimental Boiling Water Reactor; and the Experimental Breeder Reactor No. 2.
In 1956 he founded the General Nuclear Engineering Corporation and served as president of that company until it mergedwith Combustion Engineering, Inc. (now ABB). He then served as vice president of the Nuclear Division and on theBoard of Directors and Consultant until he retired in 1970. He served on the President's Science Advisory Committee forPresidents Eisenhower, Kennedy, Johnson and Nixon. He was a co-recipient of the Ford Foundation Atoms-for-PeaceAward in 1960. In 1969 he received the U.S. Atomic Energy Commission's Enrico Fermi Award "For his pioneeringwork in atomic energy, including the world's first reactors and the fast breeder reactor, and for his distinguished record ofleadership and contributions to the development of atomic reactors for research, production, and electric power."
He was a charter member of the American Nuclear Society and served as its president in 1955-56. The Power Division ofthe American Nuclear Society created the Walter H. Zinn Award in 1978, making him the first recipient.
Maj. Gen. Kenneth D. Nichols, 92, died February 21 in Bethesda, Maryland. Nichols helped establish early military andcivilian nuclear policies. He worked on the Manhattan Project in 1942 and oversaw the construction of the Oak Ridge,Tennessee, and Hanford, Washington, projects. In 1953 he became general manager of the Atomic Energy Commissionand promoted the construction of nuclear power plants.
In "My Work In Oak Ridge," the chapter he wrote for These Are Our Voices (January 1987, Childrens Museum of OakRidge; ISBN: 0960683240) he had this to say about the making of a community in which both scientists and "hillbillies"would live.
"The town of Oak Ridge itself required approximately $100 million for construction, or about one-tenth of the overallcost of the Clinton Engineer Works. More headaches for me, however, were generated per dollar spent in the constructionand operation of the town than for any of the production plants. Handling personnel on a construction job was one thing,but being responsible for the men, women and children in a government-owned town of which the best that can be saidfor the form of government is that it was a benevolent dictatorship, was another matter ...
"After spending three exciting years of my life planning, constructing and living in Oak Ridge, I am pleasedthat this once temporary town has fixed its place, permanently, in the history and future of those other townsthat make up Tennessee."He returned to Oak Ridge in 1998 for the Special Engineer Detachment reunion.
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