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Activities of the Shielding Subcommittee of the ENDF/B Cross Section Evaluation Working Group

Description: The Shielding Subcommittee of the Cross Section Evaluation Working Group (CSEWG) was established in 1967 to help ensure that the content of the ENDF/B cross section library was adequate for treating shielding problems. Early work of the subcommittee concentrated on devising formats for gamma-ray interaction and production data, as well as providing programs for testing the clerical and physics consistency of the files. The Radiation Shielding Information Center (RSIC) collaborated directly with evaluators on behalf of the National Neutron Cross Section Center (NNCSC) to begin testing and adding data sets to be fed into the official ENDF/B libraries. These efforts, which were sponsored by AEC-DRDT (now ERDA-DRDD), were augmented greatly through the Defense Nuclear Agency program of establishing a working cross section library in ENDF format. The effort concentrated on evaluation and testing of materials of interest to DNA programs and providing these for inclusion in the ENDF/B library. Shielding data testing efforts, as a part of the CSEWG Data Testing Program, are now also an integral part of the Shielding Subcommittee effort. Procedures for writing and approving the shielding benchmarks were devised by Shielding Subcommittee members. Data testing benchmark experiments have been documented and analyzed, and the most recent results for ENDF/B-IV are as reported as part of ENDF-230, ''Benchmark Testing of ENDF/B-IV.''
Date: January 1, 1977
Creator: Roussin, R. W.
Partner: UNT Libraries Government Documents Department

COVARIANCE WORKSHOP April 22-23, 1999 Brookhaven National Laboratory

Description: The NCSP is a comprehensive program established to help assure continued safe, efficient operations with fissile materials in the US. The major Tasks included in the NCSP are Critical Experiments, Benchmark Evaluations, Analytical Methods, Applicable Ranges of Bounding Curves and Data (AROBCAD), Information Preservation and Dissemination, Training and Qualification, and Nuclear Data. The Nuclear Data Task provides newly measured differential data and newly evaluated nuclear data for use in analyses of fissile material systems. One feature of the effort to improve the nuclear data for criticality applications is the inclusion of covariance data and sensitivity parameters that then allows the analyst to assess the uncertainty in calculated performance parameters due to uncertainties in the nuclear data. A characteristic of currently available nuclear data libraries is a lack of such covariance information. It was felt that gathering noted experts in the field would help assess the current status and offer guidance to the NCSP Nuclear Data Task on how to proceed in developing covariance information useful for criticality safety analysts. Since many of the experts in the field are in the international community, we scheduled the Workshop to be held just prior to a meeting of the OECD Nuclear Energy Agency Working Party on Evaluation Cooperation (WPEC). Hence, the Nuclear Data Covariance Workshop, held April 22-23, 1999 at Brookhaven National Laboratory, was able to attract 28 experts from 16 institutes in 8 countries to help assess the status of nuclear data covariance information. The presentations and discussions focused on practical technical matters associated with the generation of covariance matrices, formats for covariance matrices (particularly for evaluated files), mathematical issues related to the manipulation of covariances, and applications for covariance matrices. This publication provides a means of documenting the formal and informal presentations. The chairs of the four sessions also provided a ...
Date: January 11, 2001
Creator: Roussin, R.W.
Partner: UNT Libraries Government Documents Department

Cross Section Evaluation Group shielding benchmark compilation. Volume II

Description: At the time of the release of ENDF/B-IV in 1974, the Shielding Subcommittee had identified a series of 12 shielding data testing benchmarks (the SDT series). Most were used in the ENDF/B-IV data testing effort. A new concept and series was begun in the interim, the so-called Shielding Benchmark (SB) series. An effort was made to upgrade the SDT series as far as possible and to add new SB benchmarks. In order to be designated in the SB class, both an experiment and analysis must have been performed. The current recommended benchmark for Shielding Data Testing are listed. Until recently, the philosophy has been to include only citations to published references for shielding benchmarks. It is now our intention to provide adequate information in this volume for proper analysis of any new benchmarks added to the collection. These compilations appear in Section II, with the SB5 Fusion Reactor Shielding Benchmark as the first entry.
Date: December 1, 1983
Creator: Rose, P.F. & Roussin, R.W.
Partner: UNT Libraries Government Documents Department

Guide for licensing evaluations using CRAC2: A computer program for calculating reactor accident consequences

Description: A version of the CRAC2 computer code applicable for use in analyses of consequences and risks of reactor accidents in case work for environmental statements has been implemented for use on the Nuclear Regulatory Commission Data General MV/8000 computer system. Input preparation is facilitated through the use of an interactive computer program which operates on an IBM personal computer. The resulting CRAC2 input deck is transmitted to the MV/8000 by using an error-free file transfer mechanism. To facilitate the use of CRAC2 at NRC, relevant background material on input requirements and model descriptions has been extracted from four reports - ''Calculations of Reactor Accident Consequences,'' Version 2, NUREG/CR-2326 (SAND81-1994) and ''CRAC2 Model Descriptions,'' NUREG/CR-2552 (SAND82-0342), ''CRAC Calculations for Accident Sections of Environmental Statements, '' NUREG/CR-2901 (SAND82-1693), and ''Sensitivity and Uncertainty Studies of the CRAC2 Computer Code,'' NUREG/CR-4038 (ORNL-6114). When this background information is combined with instructions on the input processor, this report provides a self-contained guide for preparing CRAC2 input data with a specific orientation toward applications on the MV/8000. 8 refs., 11 figs., 10 tabs.
Date: December 1, 1988
Creator: White, J.E.; Roussin, R.W. & Gilpin, H.
Partner: UNT Libraries Government Documents Department

RSIC after 20 years: a look back and a look ahead

Description: On the occasion of RSIC's 20th anniversary year, this review includes highlights and lessons learned. In June 1963, the first RSIC Newsletter was published, and information analyses procedures and practices were initiated. Evidence indicates that RSIC served for 20 years as the focal point for the exchange and transfer of radiation transport technology and contributed to the advancement of the state of the art. The original concept is found to be sound: operate an information analysis center by collecting, organizing, evaluating, and analyzing all relevant information and making the information available in a form readily useful to scientists and engineers. Computing technology, a computer-based literature information system, and an advisory service remain important elements of the center. Continuing interaction between the center, developers, and users of information products and services has been a key to RSIC success. A look to the future reflects optimism.
Date: January 1, 1983
Creator: Maskewitz, B.F.; Roussin, R.W. & Trubev, D.K.
Partner: UNT Libraries Government Documents Department

RSIC (Radiation Shielding Information Center) after 25 years: Challenges and opportunities. [Radiation Shielding Information Center]

Description: The Radiation Shielding Information Center (RSIC) observed its 25th year in operation in 1987. During that time numerous changes have occurred in the government programs that sponsor RSIC and in the radiation transport community which it serves. The continued need for RSIC is evident from the steady volume of requests and interactions with the user community. It is a continual challenge to adjust and adapt our operation to respond to the demands placed on RSIC by sponsors and users. Cooperation between sponsors, users, and the RSIC staff is the key to keeping RSIC as the focus of activities in the international radiation transport community. 7 refs.
Date: January 1, 1988
Creator: Roussin, R.W.; Maskewitz, B.F. & Trubey, D.K.
Partner: UNT Libraries Government Documents Department

Deterministic methods in radiation transport. A compilation of papers presented February 4--5, 1992

Description: The Seminar on Deterministic Methods in Radiation Transport was held February 4--5, 1992, in Oak Ridge, Tennessee. Eleven presentations were made and the full papers are published in this report, along with three that were submitted but not given orally. These papers represent a good overview of the state of the art in the deterministic solution of radiation transport problems for a variety of applications of current interest to the Radiation Shielding Information Center user community.
Date: June 1, 1992
Creator: Rice, A. F. & Roussin, R. W.
Partner: UNT Libraries Government Documents Department

Computer codes for checking, plotting and processing of neutron cross-section covariance data and their application

Description: This paper presents a brief review of computer codes concerned with checking, plotting, processing and using of covariances of neutron cross-section data. It concentrates on those available from the computer code information centers of the United States and the OECD/Nuclear Energy Agency. Emphasis will be placed also on codes using covariances for specific applications such as uncertainty analysis, data adjustment and data consistency analysis. Recent evaluations contain neutron cross section covariance information for all isotopes of major importance for technological applications of nuclear energy. It is therefore important that the available software tools needed for taking advantage of this information are widely known as hey permit the determination of better safety margins and allow the optimization of more economic, I designs of nuclear energy systems.
Date: December 31, 1992
Creator: Sartori, E. & Roussin, R. W.
Partner: UNT Libraries Government Documents Department

RSIC after 14 years: where do we go from here. [Brief history and list of suggested future activities]

Description: During the fourteen years since the Radiation Shielding Information Center (RSIC) started operations, many changes have taken place in the nuclear industry, both government and commercial, and in shielding technology. Military and space applications of radiation transport technology have waxed and waned, but computing applications and the need for elaborate computer codes and nuclear data for the commercial nuclear industry have increased manyfold. The rationale for RSIC operations has been the recognition of the need for government to promote the exchange and transfer of shielding technology to advance the state of the art. With the present need to meet energy demands through nuclear power, and yet to minimize radiation exposure to operating personnel and the public, there is great need to increase radiation analysis capabilities among the utilities and other segments of the industry. Yet, because of government cost-recovery restrictions and Electric Power Research Institute (EPRI) precedents, there is a widening gap between what is being done and what is needed. During 1975, RSIC had an Electric Power Research Institute contract to integrate the shielding and technology information exchange of the nuclear power industry with that of the government and its contractors. Included in work performed by RSIC on behalf of EPRI was a survey of the radiation protection, radiation transport, and shielding information needs of the nuclear power industry. Such needs include computing technology, nuclear data, special information needs, such as fission product and ''crud'' transport, and expansion more generally into radiation protection areas such as environmental radiological analysis.
Date: January 1, 1977
Creator: Trubey, D. K.; Maskewitz, B. F. & Roussin, R. W.
Partner: UNT Libraries Government Documents Department

Recent trends in radiation shielding: a RSIC perspective

Description: The subject of radiation transport and shielding in the nuclear power industry is reviewed, and advances in the state of the art are described. These fall into the areas of computational methods, nuclear cross sections, industry practices, and standards. Computer codes and data available from the Radiation Shielding Information Center (RSIC) representing recent advances are also described.
Date: January 1, 1979
Creator: Trubey, D.K.; Roussin, R.W. & Maskewitz, B.F.
Partner: UNT Libraries Government Documents Department

Sensitivity study of neutron transport through standard and rebar concrete

Description: An investigation is under way at ORNL to (1) develop a data base pertinent to the transport of neutrons through thick concrete shields, (2) use the data base in an energy group boundary selection and collapsing scheme, and (3) develop a simple methodology to access the data base to provide rapid solutions to practical shielding problems. This paper describes work carried out to fulfill objective (1), the work consisting of calculations of the transport of fission neutrons through 1- and 2-m-thick slabs of standard concrete and rebar (steel-reinforced) concrete, together with calculations of the sensitivities of the results to total, absorption, and elastic cross sections. The transport calculations were performed with the one-dimensional discrete ordinates code ANISN in both forward and adjoint modes. The DLC-41C/VITAMIN-C cross-section library (171 neutron, 36 gamma groups) was employed, with a P/sub 3/ cross-section expansion and an S/sub 16/ angular quadrature. In all cases the fission source was assumed to be distributed within the first 1-cm thickness of the slab and the detector was assumed to occupy the last 1-cm thickness of the slab. For the rebar concrete the slab constituents were homogenized, with the horizontal and vertical No. 11 reinforcing steel rods comprising 7.6 vol. % of the slab. The quantity calculated was the absorbed dose rate, and care was taken in the mesh interval selection and source description to ensure agreement between the forward and adjoint results to within 0.02%.
Date: January 1, 1982
Creator: Bhuiyan, S.I.; Roussin, R.W. & Lucius, J.L.
Partner: UNT Libraries Government Documents Department

Available computer codes and data for radiation transport analysis

Description: The Radiation Shielding Information Center (RSIC), sponsored and supported by the Energy Research and Development Administration (ERDA) and the Defense Nuclear Agency (DNA), is a technical institute serving the radiation transport and shielding community. It acquires, selects, stores, retrieves, evaluates, analyzes, synthesizes, and disseminates information on shielding and ionizing radiation transport. The major activities include: (1) operating a computer-based information system and answering inquiries on radiation analysis, (2) collecting, checking out, packaging, and distributing large computer codes, and evaluated and processed data libraries. The data packages include multigroup coupled neutron-gamma-ray cross sections and kerma coefficients, other nuclear data, and radiation transport benchmark problem results. (auth)
Date: January 1, 1975
Creator: Trubey, D.K.; Maskewitz, B.F. & Roussin, R.W.
Partner: UNT Libraries Government Documents Department

Nuclear Regulatory Commission programs are supported by the technology resources of the Engineering Physics Information Centers

Description: The Engineering Physics Information Centers (EPIC) at Oak Ridge National Laboratory have two activities which support NRC Programs, the Radiation Shielding Information Center (RSIC) and the Technical Data Management Center (TDMC). The older of the two, RSIC, was established in 1963 as an Information Analysis Center in the general field of radiation shielding, transport, and protection. It has multiple agency funding to acquire, evaluate, organize, and distribute information (including computing technology and numerical data) relevant to its field. The TDMC was established in 1978 to perform work for NRC in fields not related to RSIC's subject coverage and to perform tasks beyond the normal level of activity for RSIC. The two centers share administrative functions, physical premises, specialists skills, and computing resources. The NRC/ADM/TIDC monitors the cosponsorship of RSIC for coverage of agency-wide interests and plans, directs, and coordinates the work of the TDMC, including the establishment of TDMC as the agency-wide repository for packaged computer-related technical information products. The contract monitor is Myrna L. Steele.
Date: January 1, 1986
Creator: Hatmaker, N.A.; Roussin, R.W. & White, J.E.
Partner: UNT Libraries Government Documents Department

Status of multigroup cross-section data for shielding applications

Description: Multigroup cross-section libraries for shielding applications in formats for direct use in discrete ordinates or Monte Carlo codes have long been a part of the Data Library Collection (DLC) of the Radiation Shielding Information Center (RSIC). In recent years libraries in more flexible and comprehensive formats, which allow the user to derive his own problem-dependent sets, have been added to the collection. The current status of both types is described, as well as projections for adding data libraries based on ENDF/B-V.
Date: January 1, 1983
Creator: Roussin, R.W.; Maskewitz, B.F. & Trubey, D.K.
Partner: UNT Libraries Government Documents Department

BUGLE-96: A revised multigroup cross section library for LWR applications based on ENDF/B-VI Release 3

Description: A revised multigroup cross-section library based ON ENDF/B-VI Release 3 has been produced for light water reactor shielding and reactor pressure vessel dosimetry applications. This new broad-group library, which is designated BUGLE-96, represents an improvement over the BUGLE-93 library released in February 1994 and is expected to replace te BUGLE-93 data. The cross-section processing methodology is the same as that used for producing BUGLE-93 and is consistent with ANSI/ANS 6.1.2. As an added feature, cross-section sets having upscatter data for four thermal neutron groups are included in the BUGLE-96 package available from the Radiation Shielding Information Center. The upscattering data should improve the application of this library to the calculation of more accurate thermal fluences, although more computer time will be required. The incorporation of feedback from users has resulted in a data library that addresses a wider spectrum of user needs.
Date: May 1, 1996
Creator: White, J.E.; Ingersoll, D.T.; Slater, C.O. & Roussin, R.W.
Partner: UNT Libraries Government Documents Department

SINBAD: Shielding integral benchmark archive and database

Description: SINBAD is a new electronic database developed to store a variety of radiation shielding benchmark data so that users can easily retrieve and incorporate the data into their calculations. SINBAD is an excellent data source for users who require the quality assurance necessary in developing cross-section libraries or radiation transport codes. The future needs of the scientific community are best served by the electronic database format of SINBAD and its user-friendly interface, combined with its data accuracy and integrity.
Date: April 1, 1996
Creator: Hunter, H.T.; Ingersoll, D.T. & Roussin, R.W.
Partner: UNT Libraries Government Documents Department