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

Maskewitz, B. F.

Roussin, R. W.

Trubey, D. K.

UNT Digital Library

AVAILABLE COMPUTER CODES AND DATAFOR RADIATION TRANSPORT ANALYSISD. K. Trubey, Betty F. Maskcwitz. R. \V. RoussinRadiation Shielding Information CenterOak Ridge National LaboratoryOak Ridge, Tennessee, USA 37830Symposium onVulnerability and Survivability ofSurface and Aerial TargetsOctober 21-23, 1975San Diego, California-NOTICE-Tha report uji pterwed 4* in dtvnunt ul wotkiponlored by Ihe United Slalei (rtivctntnenl Neithetthe United Suit* not ihr United SMTn tnrrnRernrch anj Detdopmrnl Ailmimilnitun, not jny ut(heii employets. nm any ot then contractuis.tubcunmclon. ttr Ihrir OT|>!i>)m. injkn inyvaitanty. e\pte» HI itnpbed. or juunwi any lc|ullubility tit t«p<iniibility Tot the actuuey. cumpletenewut uierulnes of any :tiri>tnutinn. appjtitui. prnduct ntpniceu IIIKKIKIJ. tit teptcscntt tlut Hi we wuukl notinfringe pnvately o«ned nitht)By acceptance of this article, thepublisher or recipient acknowledgesthe U.S. Government's right toretain a nonexclusive, royslty-froelicense in and to any copyrightcovering the article.* Research sponsored jointly by the L'.S. Energy Research and Development Administration and theDefense Nuclear Ayency utidur contract with Union f.'arbi.ie Corporation.NOF THU- OOCUMtNJ ISAbstractIhe Radiation Shielding Information Center (KSIC) [1-2]. sponsored andsupported by the linci-gy Research and Development Administration (FKDA)and the Defense Nuclear Agency (DNA). is a technical institute serving theradiation transport and shielding community. It acquires, selects, stores, retrieves,evaluates, analyzes, synthesizes, and disseminates information on shielding andioni/ing radiation transport. The major activities include: (I) operating acomputer-based inhumation system and answering inquiries on radiationanalysis. (2) collecting, checking out. packaging, and distributing large computercodes, and evaluated and processed data libraries. I he data packages includeinultigroup coupled neutron-gamma' ray cross sections and kerma coefficients,other nuclear data, and radiation transport benchmark problem results.As an integral pan of it's ii.formation collection and processing activities. RSIC collects, makesoperable, packages, and distributes computer code packages to nuclear scientists and engineersengaged in shielding research or design {3-5j. The \arious codes are designed for calculations relatedto radiation irom tission and fusion reactors, radioisotopes. weapons and accelerators and toradiation occurring in space. I lie Center uses the v-ord "package" to mean all the items needed toutilize a code el'lecli\ely. Ihe package normally includes documentation describing the theory andcode operation (contiibutor's report phis KSIC abstract and notes) and one or more reels of tape onwhich is written the source program, operating (binary or hex) program, input and output forasample problem, data libraries, and auxiliary routines.Most o! the codes are wiiiten in I-'ORTKAN IV. which makes them nearly machineindependent. Several of the packages actually represent coding systems. The;." are represented :.n thecollection, by proton pcs. which :ux not necessarily sisciti! in themsehes. but which achieve generalityin that tiuv are designed to be easily changed. Such code systems ate most useful to the researchworker who will invest a great deal of effort in learning to use the system. Other packages are groupsof interdependent codes which constitute a complete analysis system making use of a number oftechniques.The radiation treated by the majority of the codes is cither neutron or gamma radiation or both,inn M>me codes treat charged particles. Ihe types of geometry treated vary widely, with many codesallowing a general three-dimensional geometry.For convenience, the available codes arc grouped into two classes: (1) those which treatradiation transport and identified by Computer Code Collection (CCC) numbers, and (2) thoseperforming auxiliary data processing useful for other radiation analysis purposes and identified byPeripheral Shielding Routine (PSR) numbers. The numerical methods applied in the CCC codesarc primarily discrete ordinates (1- and 2-dimension). Monte Carlo (up to 3-dimension). and kernelintegration (generally ."^-dimension). The remaining include removal-diffusion (Spinney), moments,spherical harmonics, and invariant embedding transport theory codes and miscellaneous codes tocalculate fission product buildup, release and resulting dose, slopping power, optimization,sensitivity analvsis. and others.The PSR codes include multigroup cross section generation and handling, nuclear models,experimental energy spectra unfolding, optimization, plotting, coupling discrete ordinaie results toMonte Carlo, random number generation, and others.As an adjunct to the computer code exchange. RSIC is involved in many data activities, withmost emphr:iis being placed on nuclear cross section dataldj. Through cooperation with \ariousagencies, KSIC assists in improving the adequacy of basic evaluated cross section data and packagesand distributes various types of data libraries useful in radiation transport analysis. The emphasis ofthe effort is on the improvement ofcalcuiational tools available to the shielding analyst.This work involves collaboration with the National Neutron Cross Section Center (NNCSC)atBrookhaven National Laboratory, the Shielding Subcommittee of the Cross Section EvaluationWorking Group (CSEWG). ERDA Controlled Thermonuclear Research Division, the U. S.Nuclear Data Committee, especially the CTR subcommittee, and the Defense Nuclear Agency(DNA).The Center's role in the Evaluated Nuclear Data File (ENDF) development is to assist in theacquisition, checkout, and review of "shielding" cross sections in ENDF format which mayultimately be placed in the ENDF 15 file. In this context, "'shielding" cross sections are evaluationsperformed in the shielding, radiation effects, or weapons radiation transport communities which arelikely to have an emphasis on gamma-ray production cross sections, gamma-ray interaction crosssections, and neutron cross .section:, in the energy range of interest for shielding with detailed energy.•nd angular distribution resolution. RSIC maintains and distributes the Defense Nuclear Agency(DNA) evaluated cross-section library[7]. This is a working library in ENDF" format whose contentcan be modified and reused as oilen as the evaluator deems such changes to be necessary. 1 he keyto this approach is a selected evaluator. the person responsible for making the original evaluation fora particular nuclide or element. He is then responsible for authorizing changes in evaluations forthat nuclide. The evaluated data are for those materials of interest to DNA. uhose cross-sectionvalues were originally in a stale of rapid change, and with emphasis placed on neutron energies up to20 MeV and on secondary gamma-ray production. Evaluations which are not being modifiedfrequently ;<re found in the ENDF" B library, which is available in the ISA from NNC'SC atBrookhaven National Laboratory.For workaday problem solving, it has been found useful to generate and collect nuiltigroupcross section sets, and package, document, and distribute them in a format suitable as input to themost-used computer codes. Each data sei. packaged as a unit, carries a Data Library Collection(DLC) number. As with the code packages, a particular data package does not remain static but issubject to revision, updating, and expansion as required. Such changes are announced in the RSICNewsletter. Other data in the- collection include gamma-ray interaction cross sections, neutroninduced gamma-ray production spectra, fluence-to-kcrma coefficients, radioactive decay spectra anddecay schemes, and detailed output from fanspor: calculations.A continuing project, in cooperation with the American Nuclear Society, is to collect, edit, andpublish reference data in the form of "benchmark problems" [S]. The objective is to compile inconvenient form a limited number of well-documented problems in radiation transport which will beuseful in testing computational methods used in shielding analysis. The problem solutions, havingbeen determined by several methods, should be representative of the state of the art. I he problemdescription* are published in Innseleaf form so that revisions and additions can be easily made. Inconjunction with the benchmark work, data sets are packaged which allow the recalculation, with aparticular calculalional method, of already published results.Lists of selected codes ;md da!;s packaues arc given in the following (able. These are "ypical oftin; most used hat not necessarily the best for any particular application. I'urther information onthese or anv other codes or data arc available from KSIC upon request.I. Neutron Gamma-Ray Transport I-Dimension CCC-42 DTI- IVDiscrete OrdinatesMuhijiroiipMonte Carlo2. Multigroup Cross SectionProcessors3. Kernel Integration4. Spectra5. fission Product Imentorv6. Multiuroup Data Libraries7. l^ieiiiy Point I ibrariesCCC-S2,ANLSNCCC-126, ASOP (opiimi/ation)CCC-130 DTI-69 (X-ray)CCC-204 SWANLAKE (sensitivityanalysis)CCC-204 LNAP (activation)2-Dimensions CCC-222 TWO! RAN IICCC-209 DOT IIICCC-230 TRIPLET (triangular mesh)3-Dimensions CCC-230 MORS1Z-CG (muhigroup)CCC-187 SAM-CT:CCC-262 VCS (\chicle shielding)Neutron PSR-13 SUPERTOGPSR-52 MACK (kenna factors)Gamma Ray PSR-51 SNH'GCoupled PSR-63 AMPX3-Dimensions CCC-4X QADCCC-94 KAP VIPS R-l 7 11- R DO R-COOLCPSR-41 MAZHCCC-li: SAND IICCC-233 CRYSTAL HALLOX-217 ORIGLNCCC-225 RI:STCCC-237 Bl RP 2Ncution Dl.C-2 H)0G (100-group from I:\DK »)DLC-33 MONTAGI: HOO-gioup actuation)Coupled Dl.C-23 CASK (22-n.2l-7)DLC-27 ANiPXOl (104-11.22--/)1)1 V-M )):\M,\ (37-11.21--..)Gamma Ray DI.C-31 Gl-D'l 1 (SAM-C1 format)Neutron DI.C-31 NT DTI (SAM-CL format)n.r prodiuli.inDl.C-31 Cil'DTl (SAM-C1-: formal)A recent review published by the Center [')] should be of interest to tlnv:. stiirting work in thearea of weapons radiation shielding. More detailed information is presented m the Defense NuclearAgency Weapons Radiation Shielding Handbook published by the Oak Ridge NationalLaboratory [10-16].References1. D. K. Trubey. "'I he Kadiation Shielding Information Center A Technical Information Servicefor Nuclear Engineers." Sucl. l.ng. l)cs. 9 (1969) 392-5.2. B. F. Maskewit/. D. K. Trubey. K. W. Koussin, F. II. Clark. The Radiation ShieldingInformation Center: A Citifying I'one in the International Shiehtiitg Coitimunity, i-'ourihInternational Conference on Reactor Shield ing. Paris. France (Oct. 1972). CONF-72101S. Vol.I. pp. 215-225.3. D. K. Trubey and Hetty F. Maskewit/. "Computer Codes for Shielding Calculations-1969."Aucl. Dig. Iks. 10 (1969)505-17.4. Hetty F. Maskewit/ and D. K. Truhey. "Computer Codes for Shielding Calculations- 1970.".Ym7. Dig. Ih-s. 13 il9~0)44K-9.5. Betty F. Maskeuit/. Frauds H. Clark, and D. K. i m k y . "Comptiler Codes lor Shielding andRelated Calculations 1972." \uel. Dig. Dcs. 22 (19^2) 334 341.6. R. W. Roiissin. I). K. Trubey. and Betty F. Maskev.it/. I lain Activities of the tiailiatioi:Shielding Information Center, Fourth International Conteienee on Reactor Shielding. !'ari\.Fiance (October IV72). CONF-~2I01N. Vol. 4. pp. 1191- 12!l!.7. R. \V. Rotissin. lie!en\e Snelear Agency H'ordini: Cross Set lion l.ihinrv: Description andContents. OKM.-RSIC-34 (!972) Oak Ridire Nai;;mal 1 abor.iton.S. A. V,. IVolui. Kditor. Sitieldini: Henchnnuk Problems. ORM.-RS1C-2? (ANS-SD-9) (Sup. I.1970. Sup. 2. 1974) Oak Ridge National 1 aboiatory.9. Lorraine S. -\bbott. Shielding A'iiiir,\i Initial Radiation lrom Suclcur Wea/tuns.ORNL-RSIC-36 i.lnlv IT3). OA Ridge National I alv.;.'toi>.10 I*. N. Si rens and H. C. Claibome. "Masic Concepts ot Radiation Shielding AnaKsis." Chapter2 ot fi'ea/>on\ Iv.hliiitiun SliieUiw; Handbook. I . S. A h b o t t II. C . C l a i b o r n e . a iui C . ! .Clifford, l-iiimrs. Defense Nucleai Ageno'. DASA-I.S92-5 (I9"O).11. P. N. Skicns ;u<d D. K. Irubey. "Methods for Calculating Neutron and liamma-Ra>Attenuatiuii". Chapter .-.. DNA-1S92-3. Rev. I (loisneilv DASA-I.VJ2-3) (March 1972).12. Wade F. Sclph. "Neutron and Ciamma-R.iv Albedos". C'hapter 4. ORNI.-RSIC-21(DASA-IW2-2) (I9(..S) Oak Ridge National Labmahm.13. Wade L. Selph and II. C. Cl.iiborne. "Meibods !oi Calculating Iliects of Duets. Access Ways.and Holes in Radiation Shields." Chapter 5. OKM.-R.SK.-20. (DASA-KS92-I) (I96X) OakRidge National Laborators.14. W. F. St-lpli and M. B. Well.s. "Methods lor Predicting Radiation lields Produced by NuclearWeapons." Chapter 6. DASA-IS92-4 (1969)(SR1)I.15. L. Ci. Mooney. M. li. Wells. ,.nd II C. Claiborne. "L'tigineering Method for Designing InitialRadiation Shields loi Blast-Hardened I'lKierground Structures." Chapter 7. JMSA-IN92-6(1972) (SRI)).16. I.. Ci. Mooney and M. \i. Wells, '"iingineering Method loi Designing Initial Radiation Shieldsfor Artoufinumd Smictmes." Chaptci S. lo be issued as one of the DN A-1X92 series (SRI)).

Available computer codes and data for radiation transport analysis

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Available computer codes and data for radiation transport analysis

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