ML20138F795
| ML20138F795 | |
| Person / Time | |
|---|---|
| Issue date: | 11/27/1985 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20138F773 | List: |
| References | |
| FOIA-85-757 NUDOCS 8512160172 | |
| Download: ML20138F795 (76) | |
Text
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r APPENDIX B f
U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
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FOR NRC USE ONLY Program Office IIM Proposal No.
Topic No.
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TO BE COMPLETED BY PROPOSER Name and Adoress of Proposer
';UCLEAR STRUCTURES, INC.
i 4470 Chamblee Dunwoody Rd., Suite 150 l
At: anta GA 30335 Name ana Title of Principal Investigator John Robert Genser, Vice President & General Manager j
iitle of Project t
Feasibility of Conversion of Radwaste Computer Codes and Related Software Currently en Miniconcuters to Micrococcuters Tecnnology, Researen inrust and/or Potential Commercial Application (Limit to 10 words)
M:niccmouters Microconruters, Racwaste. NSASS. Criticality, Shieldine. Heat Transfer
~~ Technical Abstract (Limit to 200 woras)
A feasibility study is proposed to investigate the possible conversion of radwaste comDuter j
codes and related sof tware currently cn minicomputers to microcomputers.
The Nuc] car Safety Analysis Software System (NSASS) consistinF of 19 major nuclear encineering ccnruter codes,
.I 4 major nuclear crcss section libraries, 14 comouter interactive input generators, il intcr-active command file generators and 12 miscellaneous application conouter programs currently f
coerates on a PRIME 750 conouter system for radioactive waste managenedt.
A.prelininary
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c fort will be attempted to incl ement the 60 nodular NSASS programs on an IBM-AT micro-e
- ~ uter, and the feasibility for complete implementation of the USACS package to full
- --:' ' onal status will be ae"unsed.
1 ei Anticipatec Results/Imolication of tne Approacn (botn Phase I anc II/Potentiai Ctenercial ~~
Application of Research The prpcsed fully developed NSASS/nicrocomputer system would improve overall productivity in analysis and evaluation of nuclear systens from nuclear criticality safety, radiation snielding and heat trans ' ar considerations.
Potential cermercial users i,nclude:
gcvernment laboratorfes and reculatory bodies; nuclear vendors; architect /cngineers; i
utilities; consultants and military defense applications.
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PDR FOIA WILKINS85-57 PDR B-1 L
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(2) ImoJECT SUntARY F"
U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
- PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Decision Science Consortium, Inc.
7700 Leesburg Pike, Suite 421 Falls Church, Virginia 22043 Name and Title of Principal Investigator Dr. Jacob W. Ulvila, Vice President Title of Project DECISION ANALYSIS AS A FRAMEWORK FOR EVALUATING NEW RULES WITH PARTICULAR REFERENCE TO SAFETY GOALS t
Tecnnology, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
Decision analysis, integrated decision aiding Technical Abstract (Limit to 200 words)
We propose to develop decision-analytic techniques for evaluating proposed new rules with particular reference to safety goals.
First, we will review:
types of new rule decisions and procedures; existing methods for evaluation; and the status, form and content of safety goals.
Second, we will combine and develop decision analysis tech-niques to address particular problems in evaluating new rules. Techniques will include:
decision tree analysis, multiattribute utility analysis, personalist probability analy-sis, multiconstituency analysis, and efficiency analysis.
Third, we will illustrate the methods developed in case cxamples, including at least one that involves safety goals.
Fourth, we will begin to address organizational and other f acters ?nportant to the 1 plementation of the new t echniques in NRC's organizational and mar.ayer ial st ructure. In Phase II, these methods will be integrated into NRC, includiac ex t 'msive development of applications, guidance on the use of the techniques, and pessibl y computerized implementation of the methods.
e Anticipated Results/inglicction of the Approach (botn Phase I and II/ Potential Commercial Application of Research - Upon completion of the three phases of this proposal, a com-plete set of decision-analytic tools for evaluating new rules will be developed, tested, and i=plemented.
These methods will be integrated into NRC's organization in a way that they are readily accessible and usable by NAC's management. The methods will also include applications of safety goals in a manner that wi,11 contribute to NRC's ongoing study of this topic.
Probably the greatest benefit to be achieved from this project is the development of improved methods for evaluating new rules.
The NRC will benefit by having an improved, consistent framework for evaluating proposed new safety rules. The general public will benefit by having a consistent evaluation of new rules to improve safety. The electric utility industry will benefit by heving new rules evaluated in a way that is consistent and can reflect agreed safety goals.
l Users of electricity could benefit from cost-effective rulemaking, through its reflec-tion in electric rates.
Eventually, the method might be adapted to other NRC safety issues, which could yield additional benefits of a similar nature.,
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APPENDIX B p< <
U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS. INNOVATION RESEARCH PROGRAM (SBIR-35)
PHASE I - FY 1985 PROJECT
SUMMARY
l FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
i 10 BE COMPLE TED BY PROPOSER i
e Name and Address of Proposer NUCLEAR STRUCTURES, INC.
4470 Chamblee Dunwoody Rd., Suite 150 i
Atlanta GA 30338 i
j Eihe and Title of Principal Investigator Jchn Robert Genser, Vice President & General Manager l
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Title of Proj.ect Development and Validation of TORUS Finite Element Model Simulator for Evaluation of Criticality Safety Systems Tecnnology, Researcn Tnrust and/or Potential Commercial Application (Limit to 10 worcs)
Criticality Safety, TORUS Finite Element Models, Simulation, Validation ietnnical ADstract (Limit to 200 words)
The development and validation of a TORUS finite element model simul ator is propcsed to evaluate nuclear criticality safety systems.
A matncmatical formulation of a finite element model technicue to simulate torej dal gecretries with skewed or centrifugal perturbation will be developed.
A computer program using this formulation will be develcped and verified on a PRIME minicomputer system.
The " TORUS Generator" program resul ts will be val: dated using critical experiments and the Monte Carlo criticality sa{cty cc:7 uter code, EENO.
All resul ts, analyses and conclusiens of tne e,
- ent, verif cation and validation along with a user instruction guide will 'm
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ad.
Anticipated hesultvixplication of the Approach (both Pnese I and ll/Fotentiai Comr.ercial Application of Research The prcposed development of a TORUS generator would permit the accurate
' representations of Loroidal geometries with rkewed or centrifugal pcrturba' ions in generalized geometry and the subsequent criticality safety analysis of the exact system.
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(2) PROJECT
SUMMARY
'U.S.
NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
" PHASE I - FY 1985 PP0 JECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Adcress of Proposer Decision Science Consortium, Inc.
7700 Leesburg Pike, Suite 421 Falls Church, Virginia 22043 Name and Title of Principal Investigator Dr. Rex V. Brown Title of Project
'c INFORMATION COMMLNICATION FOR REGULATORY DECISIONS: A COMPUTER-AIDED METHODOLOGY
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Tecnnology, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
Decision aids; information communication; interactive graphic software; regulatory analvsis Technical Abstract (Limit to 200 words)
Ef fective communication of PRA and other decision information is a high priority at NRC.
With help from DSC and others, NRC has made significant progress on how to present essen-tial information in a report. We will now address the communication of selective support-ing material to decision makers, who have different and often unpredictable needs for detail.
There is no substitute for an effective "information middleman," but his role could be greatly enhanced by a streamlined computer aid.
DSC will develop an interactive graphics technology for constructing such aids.
Their function will be to make the PRA
" black box" tranrparent; to trace arguments; to allow the user's judgment to override intermediate calculations; to merge findings from conflicting sources; to explore action icplications; and to clarify uncertainty.
DSC will build on innovative analytic and 4
display techniques (such as macro-models and plural analysis) and on earlier efforts to construct such aids.
In particular, a simple prototype designed to aid a backfit deci-sion (which has had encouraging feedback from NRC decision making and research staf f),
I would be developed as a demonstration case.
i Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commerciai i
Application of Research The communication technology developed through Phase II will foster more extensive and more productive use of risk and other formal analyses by the Commissioners, by NRC staf f tnd by industry.
It will be customized to specific regulatory activities, such as:
set-ting requirements, determining compliance, appraising baseline risk, prioritiling NRC activities, and designing facilities.
The methodology will be embodied in documents and software available to risk and decision analysts, policy makers and users in government and industry.
Commercial exploitation of software for the nuclear industry in planned for Phase III.
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U. S.
NUCt! AR REGULATORT CD:'?l S S 10N SMALL BUS]NE SS ]NWJV/d 10N RLSL ARCH Ph0GW PHASE I - FY 1985 PROJECT
SUMMARY
i FOR NRC USE ONLY
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Program Office TIM Propo.(al No.
~ Topic No.
10 BE COMPLflED BY PROPOSER Name and Address of Proposer Herman L. Crawford s
614 Garden Road Columbus, Ohio 43214 Name and litle of Principal Investigator
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Herman L. Crawford, Program Manager litle of Project Analytical Method of Representing Damping in the Inelastic Range for Nuclear Power" Plants Technology, Research Thrust and/or Potential Cormercial Application (Limit to 10 words)
_ Inelastic dad 2jna, dynamic eauipment aualification, equipment design too12' Technical Abstract (Limit to 200 words)
This study will develop numerical concepts of inelastic damping which can be osed to x
analytically qualify equipment to withstand earthquake conditions. A literature search
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will be performed to identify promising concepts and to identify the state-of-the-art methods of analysis.
Presently-used concepts in four widely used computer programs - '
will be s'.udied. During Phase 1 of this study, two concepts will be demonstrated by I
the use of a finite element computer program.
The results of the computer analyqis will be compared those experimentally obtained to assess the merits of tuis sBudy l
and the value of continuing the study to other concepts or refined concepts.
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Anticipated Results/]rplication of the Approach (botn Phase I and II/ Potential Commercial 9
Application of Research The result will be to develop a methodology of accurately predicting the pekformance of equipment during earthquake conditions by the use of reliable inelastic damping theory.
The analytical methodology may be used' by equipment manufacturers and by rm;ulatory I
bodies to evaluate the equipment design to ensure safety at the san + tim 6, ensuring ecor.omical designs of equipment through optimization.
The concepts may be the basis g
for promulgating regulations or guidelines for the design of equipment.
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-(2)
PROJECT
SUMMARY
U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
}
PHASE I - FY 1985 PROJECT
SUMMARY
t FOR NRC USE ONLY j
Program Office ITM Proposal No.
Topic No.
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N 10 BE COMPLETED BY PROPOSER (s. Name and Address of Proposer Decision Science Consortium, Inc.
7710 Leesburg Pike. Suite 421 Fa'lls Church, Virginia 22043 hame Ad litle of Principal Investigato'r Dr. Jacmb W.-Ulvila, Vice President Title of Project 3
DECISION ANALYSIS FOR RESOURCE MANAGEMENT 4
Tecnnology, Research Tnrust and/or Potential Comercial Application (Limit to 10 words)
J Decision analysis, resource management, computer software Technical Abstract (Limit to 200 words)
We prepose to develop decision-analytic techniques to assist the NRC to rationally and g defensibly :::anage its resources. More specifically, we will develop aids to help NRC
' allocate staff effort toward resolution of severe accident safety issues. First, we a
willhview existing techniques for their appropriateness for resource management.
Secoyd,'we will develop new techniques based on decision analysis. Multiattribute utility th'eory and optimization theory will be used to address tradeoffs between direct and indirect costs and risks incurred or averted.
Bayesian probability theory will be used to take uhtertainty into account. Third, we will begin to address organizational and other fac. ors important to the integration of the new technigoes into NRC's organizational and managerial s t ru c tur e.
In Phase II, the techniques will be applied to an actual resource allocation tp the extent desirabic and will be integrated into NRC, including a cocputerized impleaen-t'aticn of the techniques in a form available to NRC's managers.
1 Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research Upon completion of the three phases of this proposal, improved methods will be developed, tested, and implemented for NRC to allocate its staff effort toward resolution of severe accident safety issues, and these methods will be integrated into NRC's organization in a way that they are readily accessible and usable by NRC's management.,Probably the t
greatest benefit to be achieved from this project is the economic balancing of costs and bene fi t.c.
The NRC will benefit by having an improved method for managing its resources to do the most good to the public and the electric utility industry. The electric utility industry will benefit by having severe accident safety issues evaluated in a way that is cost-effe'ctive considering both the cost to utilities and NRC.
Users of electricity will g
also benefit from this cost effectiveness, through its reflection in electric rates.
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general public will benefit from the assurance that NRC's attention is directed t'o the most
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important severe accident safety issues.
Eventually, the method might be adapted to other q
l NRC safety issues, which could yield additional benefits of a similar nature.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
/
PHA3E I - FY 1985' PROJECT
SUMMARY
a FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No, s
TO BE-COMPLETED BY PROPOSER
~ Name and Address of Proposer G2 CONSULTANTS Box 666 14976 La Cumbre Dr.
Pacific Palisades. CA 90272 O
Name and Title of Principal Investigator Thomas E. Pfenning Associate t
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TitleofProk'ect 1
An Op ical Fiber -Sensor System for the Continuous Monitoring i
of Strain on. Systems and Structures N coSpY t g ggji gyjgn y EbuYal0gypffdion c
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n Technical Abstract (Limit-to 200 words) a Preliminary research in progress by the company for the petroleum industry indicates that-for long pipelines, an effective means for-complete structural monitoring is feasible.'
This proposed research will begin at an advanced level, utilizing the known technology.
This will provide a higher return on the NRC's research dollar for Phase I and II work. We will determine the feasibility of optical fiber materials under severe radiation and thermal conditions.
- Improved, 4
electro-optical instrumentation will be evaluated and developed to-increase system resolution.
Systems and structures essential to the
.public safety and plant availability will be evaluated to determine application techniques and benefits.
With system criteria evolved.-
it will be possible to provide 'an extensive strain mapping of systems and structures with a single optical cable.
Static and dynamic conditions FMpDRs8 93iR8PM@ BM 189 ffErA8RWcoRnG8MifRelB6fRg leffmMe' "d
t Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Cognercial Application of Research Work sponsored by both the company and others indicate.s s
i a high potential for success in applying the electro optical fiber strain measuring system. If f easible for nuclear environments and.monit -
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.oring needs, nuclear plant diagnoltics will be significantly upgraded ;
with the potential for increasing plant availability andPhenc'e economic performance within the industry.
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N' CI.L Al liLGULA10RY CU M1 WON J
SMAl.L 1:USlil[SS INNOVA! JOH Pf 5l EU! PROGRAM
( Sl'II Ab )
PilASE 1 - I Y 19C5 j
l'ROJECT SUMMAi:Y IOR NRC tl5E ONLi Program Office llM Proposal Ho lopic No.
10 Ill COMPLEitb BY PkOPOSLR
'! w and Address ul Proposer Nuclear Consulting Services, Inc.
P O Box 29151 Columbus Ohio 43229 1
%me and litle ut Principal Investigator Dr. D. R. Sain, Senior Scientist lille of Project The Ef fect of Organic Impurities on Corrosion of Stainless Steels in BURS g
i xhnulogy.1:es:: arch ihrust cnd/or PotentiaFCoucercial Applica tion e l irn Ito ~10 Jords)
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nuclear reactor, coolant, organic impurities, corrosion, stainless steel technical Abstract ~(Limit to 200 v!ords)
The effect of organic impurities on corrosion of materials in SWR cooling system is virtually unknown. Many different organics are used in nucloar plants, compositions of which are of ten proprietary and thus unknown. Major organic impurities in the nuclear reactor coolant would bo identified during this research and their of fect on corrosion of stainless stools studied under the conditions simulating the BUR coolant c ond iti ens.
The organic impurities represent a significant group of impurities in a reactor ocu3 ant and, therefore, it is important to establish their of rect on corrosion of BUR materials.
The results of this study would contribute to bottor understanding of corrosion phenomena in BWRs.
Ant.it igated henolM/ Ir."lica tion of the Approach (bc! h Phase I and J J/ Potential Commercial Application of Fesearch This research work would identify corrosivo organic impurities in a BUR coolent and uvild illuminate their ef fect on corrosion and thus contribute to better understanding of the corrosion phenomena in BURS.
This would form a basis for a concentrated effort for the elimindti.on of these species from a nuclear ruactor coolant.
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could also lead to better selection of materials for nuclear reactor applications, which in turn, would Idad to significant cost reductions incurred by the nuclear plants due to the corrocion failures of materials.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office llM Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Name and Address of Proposer SHARODEN ENGINEERING CONS ULTANTS, P. A.
119 S. Trade Street, suite 1 01 P.O. Box 1336 it.atthews. North Carolina 28106 Name and Title of Principal Investigator Dennis K. Williams, President Title of Project N
Development of Localized Stresses in Attachments to 1 5D Elbows f
Technology, Research Thrust and/or Potential Commercial Application (Limit t Nuclear Piping Analysis: Attachments to 1 5D Elbows Technical Abstract (Limit to 200 words)
A finite element analysis of a trunnion and lug attachment to elbow support is proposed for the case of a long radius elbow subjected to various moment thermal, and internal pressure loadings.
The stress results will be categorized as average and linearly varying (through the thickness) stresses.
Pressure Vessel Code from which the primary and secondary (
- pressure, developed. thermal, and moment loading stress indices will be1'2 and C1'2'3) in order to determine empirical relationships for the stress indice function of dimensior.less ra tios.
a Application of ResearchAnticipated Results/ Implication of the Approach (both Phase I a ercial The anticipated results will allow the definition of stress indices to be formulated and guidelines to be established for attachments to elbows B-1
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U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVA 110N RESEARCH PROGRAM
( SB I P,-85 )
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office 1IM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Safety and Reliability Optimization Services, Inc.
62h Glen Willow Drive Knoxville, TN 37922 Name and Title of Principal Investigator' Stuart R. Lewis, Vice President Title of Project Develognent of a Procedure to Resolve Technical Conflicts in PRAs Technology, Research Thrust and/or Potential Comercial Application (Limit to 10 wordsl Resolving Conflicts in PRA Technical Abstract (Limit to 200 words)
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The further application of Probabilistic Risk Assessment (PRA) technology will require an efficient procedure for resolving technical conflicts that are inherent to the methodology. Due to the reliance on engineering judgment in nearly all aspects of PRA, technical differences routinely arise among project team members, reviewers and regulators.
This project will address that issue by establishing a procedure to assist in the resolution of technical conflict.
Phase I will concentrate on the development of a pre,lininar/- procedure that will be tested and refined in Fnase II.
Tne rescarch will include a review of appro iches to conflict resolution in other intastries and vill also draw on the applicable methods of decision amalysis.
Tne positive and negative attribut es of ad-hoc methods that have beca cr: ployed in past PRAs and other projects will also be revicwed.
The procedure is intended to be an engineering tool that will help those involved in a technical disagreement to syste: atically examine the issue and reach a resolution agreeable to all concerned.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research Phase,I will result in a draft procedure and a report describing the background of the methodology. Phase II will include tests of the nethod and a final procedure.
In addition to the procedure, long tem benefit will be derived from th'e collection precedents that will result from its application.
These precedents will then be useful in future cases.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (551R-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TTM Proposal No.
Icpic No.
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TO BE COMPLETED BY PROPOSER Name and Accress of Proposer American Research Corporation of Virginia 642 First Street, P.O.
Box 3406 Radford, Virginia 24143-3406 Name and Title of Principal investigator,
Dr. Russell J. Churchill, President Title of Project Laser-Fiber Optic Sensor for Use in Groundwater Analysis.
Tecnnology, Researcn inrust and/or Potential Commercial Application (Limit to 10 words)
- Groundwater contaminants, laser. fiber optic
- sensor, fluoresence, environmental pollution monitoring.
Tecnnical Abstract (Limit to 200 woros)
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The monitoring of groundwater for contamination by nuclear waste materials recuires the transport of subsurface materials to a surface laboratory for analysis in order to trace tne movement of wetting fronts containing contaminants.
This procecure is time consuming and subject to inaccuracy.
This proposal suggests the use of fiber optics to carry laser light to the subsurface sample location for the analysis of grounc,.ater contaminants.
The tarcet of opportunity is the combination of sensitive laser incated fluorescence with fiber optic remote sensing to achieve the technical cbjectives of determining sensitivity, calibrating kncwn
- samples, evaluating alternative designs, selecting and calibrating an optimal laser / fiber optic system, increasing signai-to-noise ratio and demonstrating the selected system at a suitable field site.
Successful completion nf the Phase I program objectives would result in the design of a prototype fiber optic remote sensor for engineering development and testing in Phase II of the program.
Anticipated Results/ implication of the Approaca (both Pnase I anc II/ Potential Ccmmercial Application of Research The anticipated result of the Phase I and Phase II program is the development of I
a laser / fiber optic system for monitoring groundwater contaminants in the subsurface environment.
Potential commercial applications include environmental control monitoring in the energy, chemical, and agricultural industries.
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U. S. NUCLE AR REGULATORY COMMISSION (SBIR-85)
SMALL BUSINESS INNOVA 110H RESEARCH PROGRAM e
PHASE I - FY 1985 PROJECT
SUMMARY
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FOR NRC USE ONLY TTM Proposal No.
Topic No.
Program Office 10 BE COMPLETED BY PROPOSER Name and Address of Proposer Applied Decision Analysis, Inc.
3000 Sand Hill Road Building 4, Suite 255 Menlo Park, CA 94025 Hame and Title of Principal Investigator Dr. Peter A. Morris, Principal Title of Project Aggregation of Opinions of Dependend Experts Technology, Research Thrust and/or Potential Commercial Application ([imit to 10 words)~~~
Methodology for resolving conflict in expert opinion in risk analyses Technical Abstract (Limit to 200 words)
All current models for combining in risk analyses insights and information obtained f rom different experts and infonnation sources are incomplete in their treatment of the judgments of dependent experts. The approaches are either not practical to implement or are theoretically unjusti fiable.
19 order to make effective use of risk analyses these difficulties must be overcome since dependence among experts is pervasive, particularly for problems where expert opinion is most important.
Unlike other approaches, the aggregation methods developed in this research will utilize the experts' conditional probabilities underlying the variable of concern, rather than their probability distributions on the variable itself. The methods will treat each conditional probability as a separate piece of inf onnation to be incorporated in the dggrtgated assessment.
Such an approach allows the formal inclusion of significantly more inf ormation into the aggregation process providing a basis for the eggregation lacking in other methods.
The information elicited f rom the experts will be structured using " influence di agrams."
Influence diagrams are powerful probabilistic modeling tools that display the dependencies (or influences) among variables and events. They are both a formal description of the problem and a representation easily understood by people of all degrees of technical proficiency.
Anticipated Results/ implication of the Approacn (both Pnase 1 and II/ Potential Comaercial~
Application of Research In much of the policy making of the MRC it is necessary to obtain and utilize espert judgments, because of the ability of experts to integrate into their' opinions and insights experiences and other hard information that are otherwise difficult to quantify.
But, in order to make effective use of experts in risk analyses dif ficulties in combining the judgments of dependent experts must be overcome.
Phase I of this research will develop methods for addressing this crucial 93p in risk analysis practice thereby advancing the state-of-the-art of risk analysis methodology and providing the NRC with insight into the use of experts.
The improve.nents in risk analysis techniques will thereby increase the NRC's effectiveness in its regulatory role and heighten the acceptance of risk analyses in the public forum.
In Phase 11, the methods developed in the first phase will be applied to an actual policy decision of the NRC and thc cethods' usef ulness end benefits in risk analysis demonstrated. The application will open the way for use of experts in all future risk analyses perf onned for the NRC,
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NUCLEAR REGULA10RY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85) y ',-
PHASE 1 - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Drogram Office TIM Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Nane and Address of Proposer Applied Decision Analysis, Inc.
3000 Sand Hill Road - Building 4 - Suite 255 Menlo Park, CA 94025 Name and litle of Principal Investigator Miley W. Merkhofer Research Program Manager, Principal Title of Project Research on the Use of Comparative Risk Information as an Aid to Communicating S
Risk and Related Information to Decision Makers Technology, Research Thrust and/or Potential Conmercial Application (Limit to 10 words) i Methods using risk comparisons to improve conmunication of risk analysis Technical Abstract (Limit to 200 words)
The numerical outputs of risk analyses are often difficult for decision makers to interpret.
Probabilities estimated for rare or unlikely events are particularly hard to appreciate, yet these are central to risk analyses of nuclear reactor safety.
Studies have shown that peo l and 10 gited capacity to distinguish small probabilities (e.g., the difference between 10 g e have li
) and to understand the significance of those differences.
A promising approach for improving the ability of decision makers and others to interpret the results of risk analyses is to provide them with a means for placing estimated risks in perspective.
If decision makers who review risk analyses have information on the level of risk associated with other more familiar risks, they possess a conceptual " ruler" that can help them to understand and interpret quantitative results.
However, risk comparisons must be used with care to avoid misinterpretation and to obtain maximum value.
Research is needed to identify ef fective and ef ficient means for presenting comoarative risk information to decision Takers.
This proposal describes a research plan designed to develop methodology for using risk comparisons as part of a comprehensive system for communicating risk and related inforn ation in rfarininn m kan Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Concercial Application of Research Phase I research will produce guidelines, a generalized strategy, and a set of specific techniques for using risk comparisons to communicate the results of risk analyses to decision makers.
The recommended methods will be illustrated in the context of an NRC decision problem.
Phase 11 will involve testing and refining the methodology and developing a comparative risk
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database.
The ultimate result will be a complete and self-contained system for comparative risk analysis designed for use by NRC decision makers.
Such a system is Tikely"to substantially -
improve the value derived from risk analyses. The concepts produced and some of the specific y
data and techniaues developed will have apolicability to other reaulatory acencies.
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APPENDIX B U.S. NtfCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Of fice 11M Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Hame and Address of Proposer SPIRE CORPOR ATION Patriots Park Bedford. M A 01730 Hame and Title of Principal Investigator Dr. Piran Sioshansi, Vice President / Surf ace Modification litle of Project lon Implantation of Zircaloy for Improved Reliability and Safety Technology, Research Thrust.and/or Potential Commercial Application (Limit to 10 words) lon Implantation of Zircaloy for improved wear and corrosion resistance Technical Abstract (Limit to 200 words)
Zircaloy, an alloy comprised largely of zirconium, is an ideal engineering material for nuclear r eactor environments. The reasons are its low cross-section for neutron capture, its excellent stability at high temperatures and its resistance to oxidation and corrosion. The one property that it fails to exhibit is,
resistance to wear. In contact with other materials within reactors it is quickly attacked by severe,
f retting wear. Ion implantation is an ideal surf ace treatment that can dramatically improve the wear resistance of Zircaloy compor,ents and at the same tirne enhance the corrosion resistaore of the alloy.
Spire has performed some preliminary research on ion, implanting nitrogen and chromium plus car bon into Zis caloy and has observed si nific. ant wear improvernent. The objective of this proposal is 10 inv est ica t e d
the effect of ion imolantation on the wear and corrosion characteristics of Zircaloy.
'A ' propose to implant Zircaloy test samples with various ions to optirnize the ion implantation paramc ter s and to investigate the wear and corrosion properties of these samples vs. unimplanted samples.
'A e will also analyze the near surface regions of the implanted samples to establish the chemical state and mechanism for improvement brought about by the ion implantation process.
Anticipated Results/Ix1 plication of the Approach (both Phasa I and ll/ Potential Comercial Application of Research This program will demonstrate a process by which Zircaloy's poor wear properties will be dramatically im pr oved. The desirable bulk properties of the alloy will remain unchanged and a significant improvement -
in corrosion resistance can be expected. These improvements will increase the lifetime of thousands of components inside nuclear reactor cores where Zircaloy is now used. Phase 11 will involve the ion implantation of actual parts (for example, fuel bundle grids) for installation in a reactor. -The long term performance of the implanted part wi!! be evaluated. Upon the suc cessful completion of Phase II, the third phase of this prograrn will be designing and building a customized ion implantation system for treatment of Zircaloy parts. The improved wear and corrosion resistance of ion implanted Zircaloy is
- expected to have a positive impact on availability and alleviate potential safety concerns.
/
..APPINDIX B U.S. NUCLEAR REGULATORY COMMISSION l
SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHAfE 1 - FY '1985 PROJECT-
SUMMARY
FOR NRC USE ONLY Program Office lTM Proposal 'No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer INTERMOUNTAIN TECHNOLOGIES, IN C.
P. O. Box 1604
?
Idaho Falls, Idaho 83403-1604 Name and litle of Principal. Investigator GLEN A. MORTENSEN, ' Manager - -Computer Sciences
{
Title of-Project l
DEVELOPMENT OF A COMiUTER GRAPHICS DATA BASE USING DATATRAN
.l Technology, Research Thrust and/or Potentiil Commercial Application (Limit to 10 words)~
{
Computer Graphics Data Base-
['
-Technical Abstract (Limit to-200 words)
The computer progra=s developed for the NRC produce expensive and detailed predictions of a
'l cultitude of system variables. The graphics output from these calculations is limited in scope and kind.
! )
The objective of this proposal'is to develop a general computer graphics methodology which can be used with any of the major NRC computer progra=s.
Specifically, the cethodology would utilize the DATATRAN data base canagement system in conjunction with restart-plot files produced bf the computer programs to generate computer graphic data bases. - Existing DATATRAN plotting modules would then be used to produce graphic representations of computer results.
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- A new DATATRAN odule to produce noding diagrams from cceputer prcgram input will be developed.
i Anticipated Results/Imolication of the Approach (both Phase I and II/ Potential Commercial Application of Research 2e anticipated result of. Phase I of the prop ad wcrk is a cost-effective method of producirg sqhic
/
repremntations of cccputer code input ~and output, demonstrated for REI.APS. De cethod will be based on the DATATRAN systems and will ecploy both existing and new DATATRAN codules.
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Rese DATATRAN codules woul'd ccepiccent the Nuclear Plant Data Bank (NPDB) currently under develepwnt
)
by the NRC, and wculd interface with cceputer program output in a manrry nimilar to the (mtmt irierface 1etween the._NFIB nnd wer"+ evcgrr irp"t.
l Ccepletion of Phase II would expand the capability to other cceputer programs such as TRAC, SIMMER, g
SCDAP, etc., and would add capabil$ ty of producing system roding diagra=s frve pregram ir,put.
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J AP?LNDIX B Page 2
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U.S. NUCLEAR RECULATORY COMMISSION
-1 SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE 1 - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office 1TM Froposal No.
Topic No.
10 BE COMPLETED BY PROPOSEN a
Name and Address of Proposer KTA-TATOR, INC.
115 Technology Drive Pittsburgh, PA 15275-1085 Name and Title of Principal lovest1 gator a
Kenneth A. Trimber Title of Project Field Design Basis Accident Test Chamber for Assecting the Integrity of Aged Coating Systems Tecnnoiogy, Research Thrust and/or Potential Lorinercial Application (Limit to 107ords)
~
1 Determine need for equipment to assess integrity of aged coating.
Technical Abstract (Limit to 200 words)
Protective coatings are applied within primary containment to facilitate decontamination and for corrosion protection.
The applied coatings must also be of sufficient integrity j
{
to withstand the rigors of a Loss of Coolant Accident (LOCA), should it occur.
This
{
ability is assessed on fresh coatings applied to test panels which are then subjected to a laboratory Design Basis Accident (DBA) test.
However, the coatings are not re-assessed after the plant has been in service to determine if aging has any effect on perfor ance.
It is felt that the development of a field DBA test chamber will al}ow for the routine monitoring of in-situ coatings to assure that a potential safety prob}en does not exist, and wi'.1 be of value in verifying the quality of repairs.
The Phase I research will assess tne current methods for verifying the quality of aged coatings (if any), will determine if there is a need for such a field device, will investigate the previous use of any such apparat 11, and will culminate in the con-ceptual designs for developing the equipment.
}
Anticipateo Results/iglication of the Aoproacn (both Phase I and II/ Potential Commercial Apolication of Research It is anticipated that the Phase I research will show an overwhelming positive response to the development and use of such equipment.
It is likely that the equipment will eventually be used as a part of routine assessments of_the coating during outages. This will help in determining if repairs are necessary and if the repairs to the aged coating are natisfactory.
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APPENDIX B U. 5.
NUCLEAR REGULATORY C0f;M15510N SMALL BUSINESS INNOVA 110N RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office llM Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Name and Address of Proposer Fracture Proof Design Corporation 77 Maryland Plaza St. Louis, MO 63108 Name and litle of Principal Investigator Dr. Hiroshi Tada litle of Project Energy Absorbtion Characteristics of Cracked Pipe Technology, Research Thrust and/or Potential Connercial Application (Limit to 10 wordsf Demonstrate safety of cracked pipes during seismic / water har:ner events Technical Abstract (Limit to 200 words)
Structural ductility methods (SDM) for evaluating the integrity of piping rely on th e energy absorption characteristics of cracled sections.
The emphasis of the program will be to extend (SDff) to the analysis of water hacmer problems. The original SDM formuistion was limit ed to the analysis of bending loads and was based on an elastic perfectly plastic formulation. Hus, the analysis of axial loads and axial plus bending must be included.
The formulation will also be extended to incInde estimates of J,pp based on hardening asst =ptions.
Methods will be developed for bounding the stored energy of various elesses of water harmer events such as the steam bubble collapse and valve sinm.
The effects of discontinuities on energy absortion ebcrasteristics will be included.
As the SDM zelies en tearing stability, this proj e ct will also include the develerment of simplified mettods for the corpct ation of T,pp.
This approach will permit ce=putation of T,pp, by bend analyses without having to resort to the use of finite element methods, c
Anticipated Results/Im?lication of the Approach (both Phase I and II/ Potential Commercial Application of Research It is expected that a criteria for the analysis of cracled piping under mater hancer loading (and ccmbined with other loads) would be developed.
In conjunction with this, simplified methods for computing T,
would be prepared.
Finally alternate design
- methods, such as criteria for thec[pzmination of snubbers and other restraints, could be C
assessed. The results wonid provide a basis for eliminating the requirement to postulate breals for pipe-whip protection in systems prone to water hammer events.
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B-1
APPENDIX B U. S. NUCLEAR REGULATORY CCMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985
' PROJECT
SUMMARY
FOR NRC USE ONLY Program Office 1IM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Adcress of Proposer SWAKE SIVEK ScF7TVARQ.[NC,
- 2. IO O Sc=LMcwr AveuvC 10483 Ru s, zD 6340/
Name and Title of Principal Investigator 5Ame5 2.
/* Jut 7x V}CK hlDEN7~
Title of Project EnsC.in/csetur,- laseec.S74 riori kwLoi ocar c
~
0
' SMZ P 19 WctCSTdTid foc. AWMy.st.5_CCTechnoToay, Researcn Th ietnnical Abstract (Limit to 200 woras) 2egna 3//wwu ncyf/ 0 RQW.W _
The proposed project addresses the development of a mi crocomput er bawd engineering workstation to be used in the analysis of nuclear reactor transient simulations produced by mainframe thermal-hydraulic simulation codes. Phase I consists of the investigation of the feasibility of development of a microcomputer based work station, investigation of the attributes it should have, estimation of the cost and schedule f or developing the system, and devel opment of a pr nt otype system for evaluation and demonstration purposes. Phase II would develcp a full-featured working version of the workst ation f or a single icactor code. Phase III would generalize this workst ati on f or a variety of codes and mainfrema ccmputers.
i 4
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Cornercial Application of h search As a r esult of this project in the analysis of computer, calculated reactor transientthe NRC could provide engineers involved si mul ati ons with tools to improve and simpli f y their analyses. This would reduce the cost and duration of such analyses and improve the productivity of the involved engineers.
E-1 1
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U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINEftS INNOVA 110N RESEARCH PROGRAM (SBIR-85)
PHASE 1 - FY 1985 PROJECT
SUMMARY
~
FOR NRC USE ONLY llM Proposal No.
Topic No.
Program Office 10 BE COMPLETED BY PROPOSER Name and Address of Proposer Expert-EASE Systems, Inc.
932 Santa Cruz Avenue Menlo Park, CA 94025 Name and Title of Principal Investigator Joseph M. Holzer, Manager o f Applicatinns Development litle of Project Expert Syste= Aided QA ofSystem T-H Models Utilizing Automated Schamatic Generation
~ Technology, Research Thrust and/or Potential Conmercial Application {Ma~it to iObr~dsl
~
Thermal Hydraulics, Quality Assurance, Expert Systems, ?!ork st a tion c,__ 7. r, i Technical Abstract (Limit to 200 words)
Computer Gr whicc The research described in this proposal will make a major contribution to the Quality Assurance (QA) of thermal-hydraulic models by introducing an expert system approach. The expert system symbolic CRT schematic technology will be used to both generate a display of a model and input data tables to enable easy data validation.
A work-station environment will be developed which ut ili zes previously generated models to interactively display on graphical component tdt's thc calcu}ated nsults is numeric or
- spleve.
Phase ! will result in the development of a demons ation i o lo t ;e
,1 s em o r.
a,icro-::mputer for PEhiPS (or TRAC) and will anc x ;, e r t systcas.
A full-scale prot otype will be developed during Phase II on a mini-computer work-station with the emphasis on the expert system, the e n g i n e e r - c o ir. p u t e r interface, and colorgraphics.
Anticipated cesults/ Implication of the Approach (taotn Phase I and II/Fctential Ca ercial
,$pplication of Research As a result of this RSD project, software will be developed that will aid the engineer in Quality Assur:ng his models.
The expert srstem rule Sate and associated tables deseloped in this pro. ject can specifically be used for RELAP5; howeser, the analyst will also be able to modify these to enable usage with other codes and models.
In Phase II, development will result in a workstation that will enable the interactive display of results in color on schematics or graphs, thereby assistine the analyst in the i n t e r r; r e t a t i o n and evaluation of results.
inis system extends the concept of human engineering to the design engineer or analyst.
2
U.S. AUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Prcgram Office TTM Proposal No.
Topic No.
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TO BE COMPLETED BY PROPOSER H me and Address of Proposer Science and Engineering Associates, Incorporated 76 Lafayette Street Salem, MA 01970 Name and Title of Principal Investigator Dr. John G. Eoll, Senior Scientist Title of Project Condensation Heat Transfer Model Development Technology, Research Thrust and/or Potential Connercial Application (Limit to 10 words)
Steam condensation model algorithm development Technical Abstract (Limit to 200 words)
A model of condensation heat transfer widely used in meteorology will be evaluated for possible installation in the TRAC-PlA code. Modifications to the model will be made to enable modeling of such effects as the effect of the pressurizer spray valve, injection of emergency core coolant, and the initiation of voiding in the primary coolant.
The model will include the following effects:
homogeneous droplet formation, diffusional and collisional droplet growth, stochastic droplet coalescence, droplet transport, release of latent heat, and kinetic corrections to droplet growth due to the effects of accommodation.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research A description of the model developed will be submitted to an appropriate journal for referred publication. Under Phase II the model will be installed in TRAC and RELAP.
The model will be potentially useful in modeling a variety of other industrial steam condensation applications.
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e APPENDIX B U.S. NUCLEAR REGULATORY COMMIS3 ION SMALL EUSINESS IhNOVATION RESEARCH PROGRAM (SI. M 3)
PHASE 1 - FY IcSS
~
PROJECT
SUMMARY
FOR NRC USE ONLY Prcgram Office TIM Proposal ho.
Toaic ho.
TO EE COMPLETED EY PROPOSER hame and Accress of Preposer Advanced Technology 6 Research, Inc.
3933 Sand:. Spring Road Surtensville, Maryland 20S66 hame ano istle or Principal Investigator Dr. Jackson C. S. Yang Title of Project C
Pre-Failure Monitoring of Aging Safety /Refief Valves Tecnnoiocy, Researcn inrust ana/or Potential-Commercial Application (Limit to 10 worcs)-
~
Non-Destructive Examination of Safety / Relief ' Valves Tecnnical Abstract (Limit to 200 worcs) yailure of valves and pumps account for 25" of plant reportable events.
Of particular safety concerns are the safety / relief valves. Valve failure could be due to many causes such as seat damage, stem cis-alignment, pilot line blockage, spring fatigue, bellow leakage, etc.
Most of these causes are related to the aging of cocponents or parts.
A pre-failure conitoring tr.chnique has been developed by the proposers by monitoring valve ncise, pressure, acceleration, displacement under dynamic condition during valve ope.;in; and closing. The ncise spectra can be analyzed by'"Randcc Decrement Technique" wisch c:n highlf;nt the'sympton of a " sick" calve before the actual failure of the valve.
Such Dynamic Pre-failure Monitoring enables one to prolong the service life of a valve ner-r<n; its end of life e x;.e c t a n cy without the risk-of failure.
Tnis prcposal covers two tasks:
The development of a cceprehensive dynamic pre-failure technicue for safety / relief valves, and the compilation of life expectancy statistics frez plant records.
Anticipatea Results/irplication of the Approacn (botn Pnase i anc II/ Potential CC.Tet e: 1.
Aoplication of P.esearcn' The result of this study will enable one to develop an optical valve-health maintenance program with realistic replacenent schedule based upon life expectant statistics in combina-tion with pre-failure r.onitoring to fere-warn any imminent failure.
Such a program can prolong the useful life of the valves without the risk of unexpected failure. Perhaps nore importantly, it may prevent component failure that could result it. a costly prolonged system shutdown.
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APPENDIX B U. S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SSIR-85)
" PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office IIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer MOHR AND ASSOCIATES 1440 Agnes St.
Richland, Washington 99352 Name and Title of Principal Investigator Dr. Charles L. Mohr, Principal Investigator Title of Project Void Fraction and Liquid Level Assessment for Def ormed Fuel Bundles Under Low Reflood Rates and Boil Off Conditions Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
Assess Conservatism of Appendix K f or Low Reflood Conditions Technical Abstract (Limit to 200 words)
This program deals with using the digitized video TDR liquid level data prepared under Contract (NRC-04-84-146) of the MT-4 test from the LOCA Simulation in NRU Program.
These new data and techniques will be applied to estimate the void fraction, liquid level, and local heat transf er conditions for the other NRU t ests where only Self Powered Neutron Detectors (SPND's) and thermocouple data are available. The technique produces excellent results and makes it possible to measure cooling fronts, quench fronts, froth zones, and provide a qualitative estimate of density. The mothod will be used to evaluate very low reflood rat es of.1 in/s to 1 In/s (.25cm/s - 2.5cm/s).
Trausient beat t r,nsf er condi tions f or local temperatures will be determined. These results will be compared with electrically heated tests which do not have t he thermal resistance and local power variations of nuclear fuel.
J l
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial
)
Application of Research j
The calculated coolability of deformed fuel bundles under Appendix K criteria limits the operating flexibility of some PWR's.
This work will determine the conservatism in the low reflood rate coolability for full length nuclear fuel and provide a j
reference point in interpreting the electrically heated data in this regime.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Na e and Address of Proposer PAUL-MUNROE INC.
1701 West Sequoia Avenue Orange, CA 97668 Name and Title of Principal Investigator Raymond M. Calantine, P.E.
m Title of Project F
Large Bore Hydraulic Snubber Tester (detect presence trapped air)
Technology, Research Thrust and/or Potential Comercial Application (Limit to 10 words)
Failure Modes Fluid Systems - Absorbed versus free air - Develop Tester Technical Abstract (Limit to 200 words) Develop equipment required to test Large Bore Hydraulic Snubbers for presence of trapped air in pockets while the snubbers are in the installed position.
Snubbers are carefully filled and tested prior to installation to ensure all free air is bled and present methods appear to be satisf actory. However, air can be introduced by improper installation methods, or develop in the snubber af ter installation. There are no methods to test for trapped air at the present time citer the installation has been completed. The trapped air in a snubber could seriously impair the performance of this safety related unit during an accident when the unit is to act as a rigid strut.
Causes of trapped air include: (1) improper use of installation procedures or original testing procedures; (2) after installation, development of free air pockets from release of air absorbed in the fluid at time of filling, and then driven out by temperature change; (3) after installation, development of air pockets released by throttling of the fluid during snuboer motion. Throttling can produce downstream momentary vacuums from the venture effect and release free air bubbles.
These causes of air entrapment and their preventation would be examined during the original parts of the study. Concepts for at least two practical test units would be detailed during Phase 1. Actual building of hardware and prototype testing of snubbers under operation would be performed under Phase 11.
Anticipated Results/Irelication of the Approach (both Phase I and II/ Potential Comercial Application of Research The Phase I and Phase 11 work would result in a final design and one completed prototype unit which could be easily connected to an installed snubber and a test run to prove fluid integrity. The designed test unit would have a value of between $7,000-$15,000, and would be j
suitcase size with an integral manometer, digital and printed readouts to show results. Data input would j
)
be from a hand held HP-41CV computer.
All of the nuclear utilities would be a prospect for this test unit which could total 250-350 units by 1990. The principal economic value, however, would not be to the manuf acturer of the machine but would l
be huge cost saved by the utility user in testing expenses. More important even than that would be the
(
added safety the use of the test machine would add to the nuclear industry by proving fluid integrity I
~
wnenever required and assuring proper snubber performances easily and quickly.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS _ INNOVATION RESEARCH PROGRAM.
(SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TTM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name ar.d Address of Proposer Nazarltronics Company, Applied Computer Electronics P.O. Box 2150 Ann Arbor, Michigan 48106 Name and Title of Principal Investigator Samuels A. Keith, President /Research & Engin6ering Director Title of Project Multifunctional Comprehensive Integrated Display Interface (MCID) k Technology, Research Thrust and/or Potential Comercial Application (Limit to 10 words)
Comprehensive audio, video and graphic computer interface sof tware_ package.
Technical Abstract (Limit to 200 words)
A Multifunctional Comprehensive Integrated Display (MCID) computer software package design is proposed, to address the current and near term computer graphic, audio and video display needs of the United States Nuclear Regulatory Commission as determined by a proposed survey of NRC key personnel and computer programs.
Survey results will be used to modify a tentative MCID design to NRC needs.
The proposed MCID package will provide a common database audio, video and graphic input and output interface to the target computer in an easy-to-use, user-friendly, interactive, programmable format, negating the necessity for extensive preuse training.
MCID will be designed to easily interface with existing computer programs and databases and thereby provide enhanced display capabilities in the form of charts, graphs, audio messages, imaging, animation and text. Any one of the three audio, video or graphic ciisplay formats can be used or any combination of the three, to provide true cybernetic communications.
g A wide variety of government and business uses exist.!
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Comercial Application of Research The proposed MCID software package will of fer a multiplicity of functions which no other current software package offers.
Otherwise, difficult to interpret computer results can easily, quickly and clearly be displayed
-and manipulated by the user of the MCID sof tware package to obtain graphic, q
audio and video formats.
Phase I proposed MCID activity will show the basic feasibility of the multifunction display concept.
PhaFe II proposed MC1D y
a activity will concentrate on streamlining and enhancing the MCID prototype.
l MCID's multisensory computer communications concept has applications unlimited.
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APPENDIX B l
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U.S. NUCLEAR REGULA10RY COMMISSION SMALL BUSINES5 INNOVATION RESEARCH PROGRAF 4 (SBIR-85) l PHASE 1 - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER name and Address of Proposer VM INTERNATIONAL 2106 Stearns Hill Road, Waltham, MA. 02154 (617) 894-4250 Name and Title of Principal Investigator Dr. V. Victor Munjal, Owner / President Title of Project
" Aging and Embrittlement Models for Structural Materials Used in t
Light Water Reactors / Nuclear Power Plants".
Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
Models, Aging, Embrittlement, Ferritic Steels Radiation Effects Technical Abstract (Limit to 200 words)
It is well known that most of the structural materials (namely ferritic steels and stainless steels) used in light water reactors (LWRs)/ nuclear power plants exhibit aging and embrittlement on exposure to radiation at operating temperatures of about 290-350 C for several years. Thus, there is a need to develop aging and embrittlement models which can predict the performance with exposure time, temperature, radiation flux (humidity),
and stress. A unique approach is being suggested for the development of models. During Phase 1, effort will focus on research to demonstrate the potential strength of models. During Phase II, the models will be perfected and extended to several alloy systems (e.g., alloy steels and stainless steels) being used extensively in the construction of LWRs/
nuclear power plants.
j 1
Anticipated Results/ imp'lication of the Approach (both Phase I and II/ Potential Commercial Application of Research o Ability to predict / assess reliable aging and embrittlement performance on the basis of models, thereby minimizing / eliminating the need for lab scale expensive experiments and enhancing the safety of LWRs/ nuclear power plants.
o Development and identification of aging-resistant structural materials suitable for use in LWRs/ nuclear power plants and various aerospace applications.
j i
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APPENDIX 8 U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS ~1NNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY.1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program office TTM Proposal No.
Topic No.
l Nas2 and Address of Proposer 10 BE COMPLETED BY~PEOPOSER Xynet Corporation 265 Bonham Rd.
1 1
Cincinnati, Ohio 45215 e
Name and Title of Principal Investigator Otto G. Wolke _ Vice President Eng b *rYng Technology for Nuclear Powerplants Technology, Research Thrust and/or Potential Conmercial Application (Li it Provide design concept for a FAIL SAFE nuclear reactor to 10 words) i m
Technical Abstract (Limit to 200 words The scope of this Phase 1 ef ort will encompassthe analysis design of a FAIL SAFE PBR type high temperature gas cooled n
.tnd conceptual 5,
The premise is if reactor core fuel is safely removable afteruclear reactor. ;
coolant accident -(LOCA) then there is no basis for sustaining da a loss of p
the core. The topic for study then is definit mage to 1.:
removal of core fuel before damage can occur. ion of a means for rapid adaptable to a rapid fuel removal process. As part of this ProjThe PB enhance the FAIL SAFE feature, a two ball (pebble) system will b ect, to 1.e. larger fuel balls and smaller interstitial control ball e studied, i
balls may be poison or moderator and may form the top reflecto
- s. The control r,
d; I
Application of ResearchAnticipated Results/ Implication of the Approach (both otential Consercial 3,
.;i The result of a successful conclusion of Phase 1 and eventua
.q research will be a p.reliminary design of a FAIL SAFE high temperat y Phase 2 gas cooled nuclear reactorwhich after demonstration will be acceptabl ure to the U.S. Public as a safe nuclear energy source e
reactor industry.'a the U.S.an unlimited availability of energy and a revi
. This would lead to ear
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APPENDIX B
~
U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
{
WiASE I - FY 1985 PROJECT
SUMMARY
a 1
FOR NRC USE ONLY Program Office LIM Proposal No.
Topic No.
~
TO BE COMPLETED BY PROPOSER Name and Address of Proposer h
AUTOMATED DECISION SUPPORT SYSTEMS 455 N. Jackson Ave.
University City, Mo. 63130 j
Name and Title of Principal Investigator Karen 1. Fujimoto, Vice President Title of Project
'4 A Reactor Safety Decision Support System Technology, Research Thrust and/or Potential Comercial Application (Limit to l'd words)
Lowering Reactor Operational Costs by Inplant Monitoring of Reactor Life.
Technical Abstract (Limit to 200 words)
The feasibility of an automated decision support system for (1) reactor safety research and (2) for in-plant surveillance of structural degradation will be studied.
The decision support system will be built around a desktop computer system and will contain all the data, analysis algorithms and database management utilities for tracking the structural degradation of reactor components and for establishing operational limits and inspection or repair schedules in a manner which minimizes economic disruption.
I Much of the bur 6,some, time-consuming work required to track structural degradation will be eliminated via extensive use of (1) automated construction of the analysis models,(2) automated scheduling of the tasks, and (3) use of a database management system to manage the flow of l
information between the various routines.
Anticipated Results/Imolication of the Approach (both Phase I and II/ Potential Comercial Application of Research Significant life cycle operational cost savings will result from (1) elimination of excessive conservatism in current procedures,(2) improved analysis methodology, and from (3) availability of an automated decision support system for in-plant use to provide early warning of repairs or inspectioris as well as to provide timely feedback on
/
effects of changes in plant operating procedures on life extension.
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,f APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS ]NNOVATION RLSEARCH PROGRAM, (SBIR-85)
PHASE 1 - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program.0ffice llM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer
= 0ceanit Laboratories, Inc.
-P.O. Box 10333 Honolulu, Hawaii 96816 j
Name and Title of Principal Investigator Dr. Patrick K. Sullivan, President Title of ProjectA Nondestructive Method for Moriitoring the Influence of dater Chemistry on Heat Exchanger Corrosion and Biofouling.
Technology, Research Thrust and/or Potential Connercial Application (Limit to 10 words)
Nondestructive, Heat Exchanger, Monitoring, Biofouling, Corrosion Technical Abstract (Limit to 200 words)
Sign 1'ficant improvements in nuclear reactor power plant
~
can be safety)
(EIS which achieved by using Electrode Impedance Spectroscopy nondestructively monitors heat exchangers.
Conventional methods for heat exchanger inspection are destructive in that test samples are removed from their fl ow environment and scraped, weighed, ballistically cleaned, acid etched and metallographically examined.
The proposed research examines the feasibility of a stat e-of-th e-a r t engineering technol ogy capable of in situ, nondestructive and_ continuous monitoring of heat exchangers.
EIS is
~ based on the hypothesis that corrosion and biofouling can be characterized by observing the steady state response to a small amplitude sinusoidal perturbing potential imposed on the heat exchanger material.
Resulting spectral plots are then examined to determine - quivalent ' circuit elements e
representative of the fouling film system.
The program objective is to investigate the utility of EIS technology in monitoring the influences of water chemistry on corrosion and biofouline of heat exchanger materials.
Anticipated results include the development of a diagnostic took that will enhance nuclear power plant safety.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Connercial
~
Application of Research i
'The proposed research is leading to an automated, nondestructive and
~
_ continuous heat exchanger monitoring system.
It will enhance the safe operation of nuclear power plants by al e rti ng operators to potentially dangerous corrosion phenomena.
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APPLNDIX B U.S. NUCLEAR REGULATORY CCMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office ITM Proposal No.
Topic No.
TO BE COMPLEfED BY PROPOSER Name and Accress of Proposer Magna-Tech P/M Labs, Inc.
L Green Briar Lane Cinnaminson, New Jersey 03077 Name and Title of Principal Investigator Kenneth H. Moyer, President Title of Project Development of a Tin-Phosphorus-Iron Alloy for Sof t Magnetic Electrical Parts Tecnnology, Research Thrust and/or Potential Commercial Application (Limit to 10 words }
_Allayg, Magnetics, DC Properties. Magnetic Aging, Core Losses, P/M Alloys, Resistivity Technical Abstract (Limit to 200 words) Phosphorus iron alloys fabricated using p7M'tFc'n5fiUes are being engineered into madern electrical equipment because of the improved magnetic and mechanical properties they have exhibited in comparison with oth?r available commercial al-loys. Phosphorus additions are especially useful because they increase the permeability and resistivity, lower coercive force and prevent aging owing to nitrogen contamination.
If a third element, such as tin, is added magnetic properties may be further improved and aging may be further reduced, which could result in a double liquidus, first from tin The ternary alley may have higher permeability and resistivity, and and then phosphorus.
3cwer coercive force than the binary phosphorus irens.
Since additional lattice sites will be occupied by tin as well es phosphorus atoms, less space will be available for carbon Greater densification and nitrcgen atoms, resulting in a stable alloy that will not age.
should occur, resulting in higher msgnetic induction than for other conventionally processed P/M alloys, through the increased liquation f rom tin.
Anticipated Results/ implication of the Approach (both Phase I and II/ Potential Commercial Application of Research Potential applicaticns include development of an alloy that can be used for sof t magnetic parts within electrical or electronic devices. Parts for which the elloy is intended include computer parts, advanced motors (activators, armatures, stators,
ignitions), polc pieces, office machines, magnetic brakes, flux plates, printing heads,
solenoids, speakers, relays, fluctuators, meters and diesel injection, systems.
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APPENDIX B U.5. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM.
(SBIR-85)
PHASE 1 - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Magna-Tech P/M Labs, Inc.
14 Green Briar Lane Cinnacinson, New Jersey 08077 Name and Title of Principal Investigator Kenneth H. Moyer, President Title of Project The DC Magnetic Properties of Phosphorus Irons Containing 0.8% or More Phosphrus and the Effects of Nitrocen and Carbon Contacination on the Aging Charveter}sLLcs Technology, Research Thrust and/or Potential Comercial Application (Limit to 10 words)
~
Magnetic Aging, Magnetic Properties of Phosphorus Irons, Nitrogen, Carbon Contacination Technical Abstract (Limit to 200 words) The DC magnetic properties of phosphorus iron alloys containing more than 0.8% phosphorus are presently unknown. Sufficient data to permit
/
proper design of magnetic components from Phosphalloy 80 is also unavailable. Aging ch racteristics of Phosphalloy 80 resulting from nitrogen and carbon contamination during sintering are also not completely understood.
The purpose of this work is to complote these studies so that Phosphalloy 80 may be used in the design of improved, higher quality, devices. Also, since resistivity of elloys containd sg pho::phor 2s additions to a maximum of 1.9T, increaser, it is the purpose of this work to develop the magnetic properties of these enriched phosphorus-containing iront to provide alloys that can be used for pulsed DC and AC applications as well as currently growing DC applications.
Anticipated Results/ implication of the Approach (both Phase I and II/ Potential Commercial Application of ResearchDocumentation of the magnetic properties of Phosphalloy 60 and d;finition of aging characteristics resulting from nitrogen and carbon contamination should reault in increased use of Phosphalloy 80 parts for newly designed electrical devices.
?
Definition of these magnetic properties could result in the opening of new markets for pulsed DC and AC applications.
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APPENDIX B
'6 "
U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
~ PHASE I - FY 1985 2
PROJECT
SUMMARY
1 FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Creare Incorporated P.O. Box 71 Hanover, NH 03755 Ntme and Title of Principal Investigator Paul H.
Rothe Title of Project Generalized Modeling of Condensation for Reactor Applications Technology, Research Thrust and/or Potential Connercial Application (Limit to 10 words)
Direct Contact Condensation' Modeling for Nuclear Reactor Analysis Technical Abstract (Limit to 200 words)
A constitutive package will be developed for the modeling of direct contact condensation in advanced computer codes for nuclear reactor analysis.
Since current approaches are built upon flow regime maps which do not account for condensation effects, present advanced thennal/ hydraulic codes are unable to model cold leg flow behavior consistently durino condensation, especially if the flow is oscillatory.
During Phase I, a new generalized methodology for modeling condensation will be developed and its feasibility will be demonstrated by implementing a model for a specific condensation configuration in a selected advanced code.
The proposed approach is an extension of existing experimental results and analytical work performed by Creare where flow regime maps and cuantitative analysis were developed for various condensing situations.
In Phase II, models for selected additional condensation configurations will be developed, added to the ceneral constitutive package, and assessed against experimental data for condensation phenomena.
C Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research The anticipated result from this project is a constitutive package, compatible with RELAP5 and TRAC, for the modeling of direct contact condensation. The constitutive package will have general application as a design tool for condensing flow situations.
Since the package will be compatible with widely used comouter codes there is a potentia-1 commercial application of the analytical results to users of these codes for safety analysis of reactors and modeling of experiments.
Commercial applications include safety analysis of.
i unsteady flow processes which can occur as a result of condensation and the evaluation of fir id/ structural interactions. The condensation modeling can also stand along for use in modeling industrial piping systems, e
d 2
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION 2,.
SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
V FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER 1
Name and Address of Proposer Static Synergetics Research Ltd.
183-14 th Ave San Franc.isco,;aueA.94118
.s s
Nime and Title of Principal Investigator Dr. Edward Sieael, President' Title of Project C a t a s t r o p h e T h e o r y S t a t i c S y n e r g e t i c s ?
Algorithm of inelastic Damping St r u c tu r a l' D r e al Technol D e v e lgy, Researc1 Thruft and/or P f.enti i s 10 w d5) b Conmercial #ppl1fation (Limit tinelasfic da-opmen:
o new co predic ing Technical Abstract (Limit to 200 wordshp j p g g g d 3 (p y g t y p g 1 b p g a k j p(
Catastrophe theory equivalence'to th.e Static Syn..
ergetics Algorithm is develo' ped into a
unif'ied mathematical tool for the prediction of. ;inelactic 7 damping,nondamping changes in the elasti'c range-
- nelastic range transition and the breaki<ng poin' of component and structural reliability of' all i
1 types components and structures, including core internals (assembly response cladding structural and containment e,xterna b,...)as well asi, g f l e x Anticipated Results/ Implication of the Approach (both Phase I and I!/FdteMtiat tohmircM '__
Application of Research Development of a
unified universal ver.satile fle>
ible mathemat ical tool for qomputation and pred'i,-
ction of component and structure breaking point f ra ctur e, i nelast i c damp i ng a nd ela st i c-i nela st i c,'
damping
~:ransition for reactor core internals' soc, i
co n t a i nme n t e.x t e rmle B-1
APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985
' PROJECT
SUMMARY
e
~
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Flow Industries, Inc.
s 21414 65th Avenue South
! \\,
Kent, WA 98032 Name and Title of Principal Investigator Frederich R. Reich, Acting Manager - Nondestructive Examination Titie of Project j
Improved Examination and Testing Methods for Steam Generator
)
L Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words) s i Technical Abstract (Limit to 200 words)
' Current studies on the inspection of Steam Generator components have indicated that there is a need for improvements in the examination and test methods used in the inspection of tubes and tube welds. Current inspection is based on the use of Eddy Current techniques and in the recent trials held on the Surry Generator, tube inspection results were produced that are less than satisfactory in regard to reliability and repeatability.
In this proposed Phase 1 work, the feasibility of using advanced developments in acoustical inspection techniques will be evaluated for the detection and sizing of tubing and tube weld flaws.
The proposed inspection concept incorporates data analysis that will reduce the subjective operator interpretation required with the current inspection techniques and will provide a documented output of the test results.
The PISC III program due to start in 1985 includes a section dedicated to Steam Generator tube inspection.
This and the support offered by Combustion Engineering (CE) further indicates the continuing interest for the development of advanced inspection systems to reduce the probability of unplanned shutdowns occurring in Steam Generators.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research Recent trials involving the use of Eddy Current techniques have shown that the by;erpretation of the recorded data and signals is very subjective. The techniques, as presently being applied, do not give quantitative data. This Phase 1 project offers a system which requires little interpretation and produces reliable, repeatable quantitative
\\'
proven recently in Europe and combines tube and tube-to-tube plate weld inspection. Such data. The proposed ultrasonic technique incorporates advanced probe de~ploym'ent designs, r
devices will be essential if the life of aging nuclear plants is to be prolonged.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS. INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
~
FOR NRC USE ONLY Program Office llM Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Name and Address of Proposer Basin Engineering Services, Inc.
^
2900 George Washington Way a
Richalnd, WA 99352 Name and Title of Principal Investigator Charles T. Sundquist, P.E.,
Project Manager E
Title of Project
~t m
Vertical Distiller Test y
Technology, Research Thrust and/or Potential Commercial Appl.ication (Limit to 10 words)
Distillation, New Technology / Volume Reduction of Radioactive Waste Water Technical Abstract (Limit to 200 words)
The vertical distiller is a new idea.
Large diameter heating tubes are mounted vertically in solution inside a closed evaporator vessel.
The evaporator vapor space is connected to the vapor inlet of an ejector-condenser discharging downward into a sump.
Condensate from the sump is pumped through a heater into the tops of the heating tubes.s The' condensate then flows ' slowly downward, cooling to a temperature well below that of the vapor.,,
On leaving the heating tubes, the condensato is further cooled and then fed through the,
ejector-condenser spray nozzle, condensing vapor from the evaporator.
The. vertical distiller has an inherent thermodynamic stability that permits it to maintain steady-state conditions without control instrumentation.
The process has the potential of being more simple and more reliable than other distillation processes.
This approach to distiller design is unique because heat transfer un the interior and exterior of the heating tubes is by natural convection.
Heat transfer rates through-the heating tubes are lower and consequently more heat transfer surface is required.
- However, cartain cost advantages can more than compensate for the extra heat transfer surface.
Anticipated Results/ implication of the Approach (both Phase I and II/ Potential Commercial Application of Research
'A multi-tube prototype with sufficient size and. instrumentation would be built to prove the technical feasibility of the approach.
It is anticipated that an improved method }
for reducing the volume of low-level radioactive waste would result.
It would lead to less exposure of maintenance personnel to nuclear radiation.
It could Icad to lowe r first and -
operating costs than present methods.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM(SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY
' Program Of fice TIM Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Name and Address of Proposer Nichols Research Corporation 4040 South Memorial Parkway Huntsville, Alabama 35802-1326 Name and Title of Principal Investigator Jan Smith, Principal Investigator Title of Project Computer Graphics Enhancements for NRC Simulations 1
Tcchnology, Research Thrust and/or Potential Commercial Application (Limit to 10 w Tcchnical Abstract (Limit to 200 words)
The Phase I study of this SBIR will identify the type and scope of computer graphics enhancements for one or more major computer codes under development by the Nuclear Regulatory C'amission.
The purpose of the graphical outputs designed will be to enhance analysis of parameter performance by providing visual representations of the simulation outputs and providing a tool for algorithm and model verification.
I' Application of ResearchAnticipated Results/Im?11 cation of the Approach (both Phase I a It is anticipated that the implementation in Phase II of the Phase defined computer graphic output enhancements to the selected NRC computer codes will provide detailed visual analysis of system and subsystem simulation performance. These outputs will provide timely, interpretive, comparative, and informative data displays for the required analysis by the systems analyst.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
&HASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONL4 Prcgras Office TTM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Professional Analysis, Inc.
P. O. Box 1135 Oak Ridge, TN 37831 Name and Title of Principal Investigator Dr. Doan Lien Phung President Title of Project Risk-Based Framework for Determining Regulatory Requirements of Advanced Reactor Designs Technology, Research Thrust and/or Potential Conmercial Application (Limit to 10 words)
Optimize resources in the regulation of advanced reactor designs
__ Technical Abstract (Limit to 200 words)
'Ihere are several advanced reactor designs with claims of inherent safety, licensability, and constructability. All reactor designers wish to interact with the M C to ascertain their various claims. The NIC is not unsympathetic to the l
industry's desire to reduce prescriptive regulation but is bound by its mandate to assure the health and welfare of the public and to protect the environment.
'Ihe techniques of risk analysis are now suf ficiently advanced to assist in determining the regulatory requirements of power reactors starting with the NC
~
mandate and with performance-oriented criteria.
This SBIR proposes in Phase I to establish a risl+-oriented common framework with which the NIC could determine the requirement of advanced reactor designs and could allocate its limited resources to confirmatory researches in support of the requirements. in Phase Il the various advanced reactor designs will be assessed against the cmmon framework.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Comercial Application of Research Unified and performance oriented evaluation of regulatory requirements for new reactor concepts with view towards consistency and optimum resource utilization.
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APPENDIX B U. S. NUCLEAR REGULATORY COMMISSION SMALL BUSINES.S INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office ITM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Foster-Miller, Inc.
350 second Avenue Waltham, MA 02254 e
Name and litle of Principal Investigator Robert A.
S. Lee, Senior Engineer Title of Project c
Piping Weld Inspection Using Advanced Potential Drop Method Tecnnoiogy, Researcn Thrust and/or Potential Commercial Application (Limit to 10 words)
Improvecent in Inspection Techniques for Critical Pipe Welds Tecnnical Abstract (Limit to 200 woras)
In-service inspection (ISI) of critical nuclear plant pipe welds is currently conducted with a number of costly non-destructive techniques (NDT) which are generally labor intensive and sometimes require measures to minimize radiological exposures.
Interpretation of the results of these NDT procedures often require subjective judgement.
The feasibility of an efficient, automated weld inspection instrument based on the poten-tial drop (PD) method will be demonstrated in Phase I.
To this end FMI will develop a computer +antrolled electronic system which can rapidly impress current to discrete portions of a weld area and simultaneously measure and record voltage gradients at intermediate positions between the current probes.
Software will be developed to control current and voltage multiplexers so that systematic testing of each discrete area can be accomplished.
Phase I research will be conducted with an existing dc PD instrument.
Experiments will be designed to show thac accurate determination of small defect dimensions (length, depth and orientation) can be realized.
In Phase II, a full-scale, automated, track-mounted weld inspection unit will be developed.
After quick mounting of this unit on the pipe, testing will be conducted remotely, with test results output by the control computer in the form of three-dimensional defect maps.
)
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potentia 1 Commercial Application of Research The successful development of the advanced, automated PD weld inspection machine will 1
greatly simplify currently used nuclear plant ISI procedures.
Since the advanced PD
,I technique will require operators only for installing and removing the instrument, radiol-ogical exposures will be reduced drastically.
System decontaminations, now mandatory prior to some ISI testing, will therefore be reduced or eliminated.
Testing time and associated costs will also be reduced.
Most importa ntly, the advanced PD instrument will
}
be able to clearly distinguish between benign defects and those defects which must be removed, without depending on subjective judgement of test results.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TTH Proposal No.
Topic No.
Name and Address of Proposer TO BE COMPLETED BY PROPOSER FUTURE RESOURCES ASSOCIATES, INC.
2000 Center Street, Suite 418 Berkeley.g California 94704 Name and Title of Principal Investigator Robert J. Budnitz, President Title of Project
'l
" Development of a Method for Monitoring Fatigue Degradation of Pump Seals" a
l Technical Abstract (Limit to two hundred words) -
i l
i The failure of a reactor coolant pump seal, which can lead to a sinall LOCA accident is one important initiating event that may, in conjunction with other failures
, lead to g
severe reactor accidents.
Such failures are also an important source of reactor 'down-time.'
adequate to provide early warning of incipient failure.At present, methods This project proposes to develop an advanced monitoring system that can provide real-time information to the operator about the fatigue level of individual seals.
The approach is to measure key thermal parameters in the seal, specifically the temperature change and rate-of-ch for each thermal transient to.which the RCP seal is subjected.
be accumulated, and a cumulative index of fatigue damage would be computed usin The information would algorithm based on an engineering correlation.
The information could be used by opera-tors for two purposes:
limit of its fatigue capability, and to allow an operator to reduce the the thermal transients to which the seals are subjected, thereby reducing the risk of seal failure.
Anticipated Results/ Potential Commercial Applications of the Research developed that will enable utilities that operate nuclear power p status of fatigue in reactor coolant pump seals.
Such a system should be o.f great interest to both the NRC (for safety reasons) and the operating utilities.(for both reliability and safety reasons.)
The ultimate plans of Future Resources Associates, Inc. include firms, both in the U.S. and overseas.the commercial sale of these systems to util l
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APPENDIX B
'/
U.S. NUCLEAR REGULATORY COMMISSION t
j f./
SMALL BUSINESS INNOVATION RESEARCH PROGRAM(SBIR-85) i PHASE 1 - FY 1985 PROJECT
SUMMARY
~
FOR NRC USE ONLY Program Office ITM Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Name and Address of Proposer Dr. Morgan Tsai 4085 Merganser Dr.
Fremont, Ca. 945'56 Name and Title of Principal Investigator ~
Dr. Morgan Tsai, President Title of Project Effects of Traveling waves on Euried Pipes in Saturated Soils and in Dry Soils.
Technology, Research Thrust and/or Potential Comercial Application (Limit to 10 w Traveling waves in saturated soils and in dry soils.
Technical Abstract (Limit to 200 words)
The seismic waves propagating non-vertically in saturated soils and in dry soils are considered. The pipe strains and stresses induced by the traveling waves will be calculated for both the saturated soils and the dry soils.
The variations of the induced pipe strains with respective to the direction of the non-vertically propagating waves will be investigated. The soils are considered to be homogeneous, isotropic, viscoelastic media of the Kelvin-Voigt type. The soil-water interaction is considered in saturated soil. The seismic waves consist of two shear waves (SH, SV), the compress-ion wave transmitted by soils, and the compression wave. transmitted by the water in saturated soils.
Application of ResearchAnticipated Results/ Implication of the Approach (both Phase I a The three dimensional, nonlinear responses of' soil to non-vertically propa-gating seismic waves will be used to evaluate.the seismic int.egrit,y of buried pipes and conduits. The torsional response and rocking response of the foun-dation of the nuclear power plant to the traveling waves can be determined and these two responses at foundation can be used to analyze the safeties of the piping system and mechanical equipments inside the nuclear power plant
{
The poteiltial liquefaction can be predicted for some saturated soils.
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APPENDIX B
~
U.S. NUCLEAR REGULATORY COMMISSION
~
l SMALL BUSINESS INNOVA 110N RESEARCH PROGRAM (SBIR-85)
PHASE 1 - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Applied Science Associates, Inc.
P.
O.
Box 2687 e
Palos Verdes Peninsula, Ca.
90274 Name and Title of Principal Investigator David G.
Swanson, Vice-President Title of Project k
Aging of Materials, Equipment and Components in Reactors Technology, Research Thrust and/or Potential Comer,cial Application (Limit to 10 words)
Improve reactor safety through reactor aging assesment Technical Abstract (Limit to 200 words)
As nuclear plants grow older, environmental conditions may affect the p:rformance of plant equipment and components.
We propose to develop a ctrategy which can be applied to study the aging of equipment and components with the goal of extending plant life.
It will be directed towards the dnvelopment of methods to analyze and understand aging effects, including the codined effects of time, temperature, radiation, humidity, stress, chemical environment and electrical and magnetic fields.
It will include consideration of current methods and technology for surveillance and maintenance of equipment and components.
In addition, aging assessment m3thods will be developed for equipment and components.
The strategy will bs applied to a single component of a nuclear plant in Phase I.
In Phase II, each of the component aging processes will be examined in greater detail.
Plant components in different types of containments will be cxcmined to determine where failures are moet likely to occur and where they cro most significant in terms of reactor safety.
Anticipated Results/ implication of the Approach (both Phase I and II/ Potential Conmercial Application of Research Development of methods to analyze aging effects, post-service 1
cxcmination methods and aging assessment methods will solve an operational 2
problem for the nuclear industry, reduce the cost of plant construction, and
?
increase the life of expectancy of existing reactor systems.
The d;velopment of these methods will enhance the safety of nuclear power plants, reduce the possibility of radiation exposure to the public and provide information on and solutions to a major potential problem in the a
nuclear industry.
O
l APPIN0lx B U.S. NUCLEAR RIGULAIORY COMMISSION SMALL BUSINE5k INNOVA 110N Hl51 ARCH PROGHAM (5BIR-85)
PHASL 1-IY 1986 PROJLCl
SUMMARY
I FOR NRC USE OHLY Prograe Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Applied Science Associates, Inc.
P, O.
Box 2687 Palos Verdes Peninsula, Ca.
90274 f
Name and Title of Principal Investigator D.
G.
Swanson, Vice-President s
Title of Project Aging Processes in Concrete Structures Technology, Research Thrust and/or PotentTaTYo'IIsidrciaT Application TLimit to 10 wordM
~
Improve reactor safety through aging assessment.
~ Tr:chnical Abstract (Limit to 200 words)
As nuclear plants grow older, environmental conditions may affect the i
parformance of plant concrete and steel structures.
We propose to develop a strategy which can be applied to concrete structures.
It will be directed towards the development of methods to analyze and understand aging effects, including the combined effects of time, temperature, radiation, humidity,
-]
stress, chemical environment and electrical and magnetic fields.
It will include consideration of current methods and technology for surveillance and maintenance of concrete structures.
In addition, methods for post-service examination and testing will be proposed.
Finally, aging assessment methods will be developed for concrete structures.
The strategy will be applied to a ningle concrete component of a nuclear plant in Phase I.
In the second phase, each of the concrete aging processes will be exanined in greater detail.
Plant components in difforent types.of containments will be examined to determine where failures are most likely to occur and where they are most significant in terms of reactor safety.
Anticipated Results/lup11 cation of the Approach (both Phase I and ll/ Potential Commercial Application of Research Development of methods to analyze aging effects, post-service exrcination methods and aging assessment methods will solve an operational prcblem for the nuclear industry, reduce the cost of plant construction, and c
increase the life of expectancy of existing reactor systems.
The f
dnvelopment of these methods will enhance the safety of nuclear power plants, reduce the possibility of radiation exposure to the public and pravide information on and solutions to a ma-jor potential problem in the
-nuclear _ industry.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
- PHASE I - FY 1985
^
PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Dr.Eli Yecheskel General Management Advisory Unit,Inc. 13825 Bethpage Lane Silver Spring,MD Name and Title of Principal Investigator Mos Dr.Eli Yecheskel, Chairman of the Board -
Title of Project g
Expert. Knowledge Based and' Integrated Data Support System for NRC Technology, Research Thrust and/or Potential Conmercial Application (Limit to 10 words Expert System, Artificial Intelligence, Integrated decision support System Technical Abstract (Limit to 200 words)
This activity is a systematic study directed specifically toward applying new knowledge to meet a recognized need for a technique that would serve as a tailored expert system generator XXXXXMMMIX for use in a decision environment that is as complex as NRC's The use of on-line experts and GE World Wide Network is the heart of the mechanization process Application of ResearchAn?.icipated Results/ Implication of the Approach (both Phase I an The anticipated results include an integrated, expert based and knowledge based system that could be used in knowledge areas that are of concern to other agencies and the commercial s e c t'o r.
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APPLNDIX B U.S. NUCLEAR REGULA10RY COMMISSION.
SMALL BUSINESS INNOVAT10N RESEARCH PROGRAM (SBIR-85)
PHASE 1 - FY 1985 PROJECT
SUMMARY
C FOR NRC USE ONLY TIM Proposal No.
lopic No.
Progrcm Office 10 BE COMPLETED BY PROPOSER Name and Address of Proposer Science 6 Technology, Inc.
7618 South Memorial parkway Huntsville, AL 35802 Name.snd litle of Principal Investigator,
D.R. Shich - Nuclear Engineer Title of Project j
Thermal Loading of Underground Structures Technology, Research Thrust and/or Potential Conmercial Application (Limit to 10 words) investipation of cause and effect o f Th er-n l l ondi ne near rennni t nri on Technical Abstract (Limit to 200 words)
In the geologic isolation of radioactive vaste, one of the very significant problems encountered is the ef f ect of the heat generated by the deposited waste and the impact of such heat on the immediate surroundings. Excessive heat can cause compressive stress in the heated portions of a medium like rock near a repository and can cause tensile components of stress in regions farther away.
Such stresses can affect the structural integrity of the repository and the surroundings which in turn can af f ect the safety and reliability of the repository. Hence a knowledge of the distribution of temperature around a repository is essential to evaluate the magnitudes and the ef f ects of thermally itbced stresses in geologic media. The present study will evaluate such heat distributions for selected geometry of repositories in predetermined media of known thermal parameters.
Changes in temperature can cause changes in density and viscosity in ground water trapped in a medium like granite which could af f ect the flow of water through existing f ractures.
Hence it will be of interest to investigate thermohydrologic effects also.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research it is expected that the proposed phase 1 and follow-up phase II studies will provide a tabulated or otherwise compiled information on.the impact of Thermal Loading on Underground Structures for various type of geologic media as a function of the relevant parameters. Such informations can be very valuable in selecting repository sites.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION
/
SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85) i
/
PHASE I - FY 1985 PR03ECT
SUMMARY
FOR NRC USE ONLY Progran Office TTH Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Name and Address of Proposer LIBERTY TECHNOLOGY CENTER, INC.
Lee Park,1100 E. Hector Street Conshohocken, PA 19428 Hame and Title of Principal Investigator e
l Anthony L. Moff a, Vice President, Operations Title of Project DEVELOPMENT OF A FATIGUE FUSE
. Technology, Research Thrust and/or Potential Comercial Application (Limit to 10 wo Develoo a fuse to visually display remaining f atique life of a structure j
Technical Abstract (Limit to 200 words)
Fatigue in structures, piping systems and rotating equipment is a significant problem I
adversely effecting operating life and efficiencies and can cause loss of life and costly damage.
the most part are unreliable.Much has been done in the past to monitor fatigue, employing procedures w There exists today a fatigue fuse, presently in the development stage by Tensiodyne Scientific, which af ter extensive testing has been shown stress concentrations with cycles to failure in the range of.2 to 3 (to )to design includes a series of links with well known stress intensity factors which fall i The fuse repeatable pattern providing a series of visual fatigue life measurements.
na the development is the method by which the separate link geometries are evolved in The heart of to produce the predictable series of link failure.
order designed notches for which c Link geometry includes specifically comparison to test results. yy/co ratios are developed using finite element analysis and Libert to f atigue cases in the range of 10y proposes to continue fuse develcpment for high cycle to 100 i
analytical and experimental means to provide accurate S-N curves for these casescycles and
$nticipated Results/ Implication of the Approach (both Phase I and II/ Potential Comme Application of Research It is anticipated that the results of a successful Phase I and Phase II program would be a tecnnique that can be used to tailor a fatigue fuse for application to structures so that the useful remaining life of that structure can be reliably and simply determined envision a range of fuses for all types of structures which can be selected depending on We can the structure's expected life and the stress environment.
Since the fuse would be rela-tively inexpensive and easy to apply and monitor, its potential commercial application is seen in the commercial airline industry, structures and bridges, power plants and many other areas and appears to be extensive.
Note:
i Liberty Technology Center, Inc. acknowledges receipt of Amendment i
No. 1 of FY 1985 SBIR Program, dated 3/25/85.
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e1985 Uberty Technology Center, Inc.
1
U.S. ' NUCLEAR REGULATORY COMMISSI'JN SMALL BUSINESS INNOVATION RESEARCH fROGRAM (SBIR-85)
PHASE I - FY 1985 FROJECT
SUMMARY
FOR NRC USE ONLY Program Office TTM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer International Technical Services, Inc.
60 East 42nd Street, Suite 2316 New York, NY 10165 Name and Title of Principal Investigator Dr. Hideko Komoriya, Precident
~
Title of Project Cuidebook for the New ECCS Evaluation Mothodology 1
Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words:
Provide guidebook describing the new statistical uncertainty nothodology for Appendix E Technical Abstract (Limit to 200 words) 10CFR50.46 and its Appendix K criteria are widely considered to be exceccively conservatite.
In 1983, the NRC staff proposed new cethodolo5 es (SECR-83-472) as an interin ncacure until i
the Appendix K rule revislen is inplenented.
The now nethodology deternines an upper bcund peak cladding tenperature (PCT) value by addin6 a tern, which accounts for computer ccde, nodeling, scaling and plant paraneter uncertainties, to a PCT value calculated using nenina1 inputs. The overall concervatin: in the new nothodology is demonstrated by a comparison wit, n
statistically obtained uncertainty calculations at liniting operating conditions.
Potential benefits from c ploying such nethodology for large break LOCAs are cubstantial,
. including increated flexibility in plant operation and in reduced recource expenditure l
on ECCS nodel revisions.
ITS propones to review, reccarch and docunent the statictical foundation for the new'=ethodology, and provide the HRC with a-source guidebook for F.:7.c which delineates the.new methodology and nothods of inplementation and identifies para:cters
- important to evaluation of PCTs and their associated uncertainties. Such a guidebook will standardize subnittals -and -reviews and nininize NRC resources requirod'for future review.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research 1TS will provide a report-which delineates the new statistical uncertainty methodology fer Appendix K
ECCS evaluation and define its proper inplenentation so that. during subnittal
- review, applicants and reviewers can utilize the source guidebook in order to ctandardize the nethodology.
The report will identify key parameters (plant paraneteE, nodelilng,
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! correlations, ccaling, computer code, etc.) important to the PCT evaluation and their l: associated uncertainticcand plant dependency.
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APPIND]X B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY j
Program Office TIM Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Name and Address of Proposer h
Fracture Proof Design Corporation 77 Maryland Plaza l
St. Louis, MO 63108 i
Name and Title of Principal Investigator h
Dr. Hiroshi Tada j
k Title of Project Crack Arrest Criteria for Pressurized Thermal Shock I
Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
Develop increased margins of safety during PTS events j
Technical Abstract (Limit to 200 words) j NUREG-0744 provided a basis for evaluating the EOL integrity of RPV's using upper-shelf material properties, but it did not specify how to analyze a PTS event. The additional margins demonstrated therein were based on a crack stability criterion that allowed some i
amount of stable crack extension. Because the outer portion of the RPV wall is at upper-shelf temperatures during the crutial times in a PTS transient, the NUREG-o744 approach can be used for the analysis of RPV integrity during a PTS event. The contractor has previously developed methods for analyzing PTS events using EPFM and tearing stability.
That work provides the basis for the current project. The conservatisms inherent in the closed-form expressions for J, previously developed, will be refined. Estimates of J for semi-elliptical part-through crack geometries (circumferential and longitudinal) will be developed. An upper-shelf crack arrest criterion will be provided to augment the stability criterion that exists. Typical W and B&W designs shall be evaluated using 2 PTS transients and material data from 3 of the 8 HSST welds. Results shall be presented in terms of a J-T stability diagram for 5 crack sizes and 5 transient times.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research The results should prove that RPV's have larger margins of safety during a PTS event than can be shown by current analytical methods or that higher EOL fluences could be tolerated. The project will also serve as a basis for developing alternative }TS screening criteria and could serve to check analyses based on LEFM/ fracture toughness methods.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION '
SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE 1 - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Name and Address of Proposer LEAK DETECTION SERVICES, IllC.
1000 Beech Street Annapolis, I.!D 21401 Name and Title of Principal investigator' Joseph G.
Dimmick, Pres.
Title of Project Containment Check Valve Leak Rate I.leasurement Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
Donnnstrnto fonsibility of lonk rato nonnuronent Technical Abstract (Limit to 200 words)
Perform and report experiments to demonstrate the feasibility of the concept.
.~
C Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research Improved testing methods for leak rate measurement.
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U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
t FOR NRC USE ONLY Program Office TTM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer American Research Corporation of Virginia P. O. Box 3406 Radford, VA 24143-3406 Name and Title of Principal Investigator Dr. William Lord, Senior R,esearch Scientist Title of Project Far Field Effect Probe for In-Service Inspection in Nuclear Power Plants.
}
iecnnology, Researcn Thrust ana/or Potential Commercial Application (Limit to 10 words)
Nondestructive evaluation, Remote sensing, Utility in-service inspection Y
Technical Abstract (Limit to 200 words).
Instrumentation is required for the measurement of tube wall thickness and the detection and characterization of defects in reactor ferritic steam generator tubing and tube sheet welds.
Measuring probes must be capable of operating at elevated temperatures, high probe speeds and lend themselves to automated operation.
Most NDT systems including eddy current, ultrasonic and radiographic fail to meet these requirements. To alleviate this situation, this proposal suggests the development of a low. frequency far field effect (FFE) probe for reactor tube testing, and the development of a numerical model for the simulation of probe behavior under field concitions. Successful completion of the Phase I program objectives will result in the conceptual ~ design of a prototype far field effect probe system for enc', neeri ng development and testing in Phase II of the program.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial
]
Applicaticn of Research The anticipated results is a proof of concept system for using the far field effect to test steam generator tubing and tube-to tubesheet welds in nuclear systems.
Commercial applications include impruved nondestructive testing through the utilities industry.
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APPEllDIX B 2-U.S. IlUCLEAR REGULATORY COMMISSI0ti SMALL BUSIllESS IlitiOVATI0ld RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
r FOR tJRC USE Ot1LY frogram Office TIM Proposal tio.
Topic tio.
I r
10 BE COMPLETED BY PROPOSER GEme and Address of Proposer
~
0'Donnell Consulting Engineers, Inc.
3611 Maplevue Drive Bethel Park, Pa.
15102 tiamo and Title of Principal Investigator William J.'O'Donnell, President Title of Project EXTENDED FATIGUE LIFE EVALUATION METHODS FOR AGED LWR COMPONENTS Technology, Research Thrust and/or Potential Comercial Application (Limit to 10 words)
Fatigue, fracture, safety evaluation methods, aged nuclear facilities Technical Abstract (Limit to 200 words)
Stresses due to pressure and repeated thermal cycling cause pro-gressive material damage during the operation of LWR components and piping The present proposed research would improve the accuracy of systems.
existing S-N fatigue evaluation methods by combining them with the advanced technology of crack propagation and fracture mechanics.
Environmental effects will be included in the crack propagation data used.
Weldments will be included by considering residual stress effects, combined metallur-gical and geometric. notch effects, early crack initiation in the Heat Affected Zone (HAZ), fatigue damage during the welding process and other effects not included in the existing S-N fatigue evaluation methods.
The resulting generar. methods of evaluating the safe extended fatigue life of aged components and piping will be qualified by comparison with operating experience on actual hardware including' relevant'non-nuclear experience.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research The evaluation method research product to be developed in this Project will provide a key element of the technical and Code bases for extending the safe useful life of aged LWR plants.
The inclusion of environmental effects and weldments in de evaluation method, qualified by hardware operating experience, will give utilities a means of quantifying the safe remaining life of billions of dollars a
worth of aged nuclear components and piping.
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s APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM
. (SBlR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Name and Address of Proposer Nuclear Consulting Services, Inc.
P O Box 29151 Columbus Ohio 43229 Name and Title of Principal Investigator Dr. D. R. Sain, Senior Scientist litle of Project Cffectiveness of Radioactivity Removal from Nuclear Roactor Coolant at High Temperatures Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words) nuclear reactor, coolant radioactivity cleaning, magnetite Technical Abstract (Limit to 200 words)
The possibility of replacing currently used low-temperature organic ion-exchange resins in nuclear reactor coolant radioactivity clean-up systems with high-temperature high-pressure products, such as porous magnetite, has been identified.
This would reduce radioactivity leaks and levels and radio-activity exposure of personnel, eliminate intrusion of corrosives from the resin into the coolant, reduce size, cost and complexity of radwaste disposal, etc.
To achieve this the research is proposed to test the ihasibility of this approach by investigating radioactivity removal of Co 0 6
and other radioactive' species from water under_ simulated conditions of nuclear reactor coolant, the effect of coolant chemistry, temperature, time, bed depth, coolant flow rate, etc., as detailed in the proposal.
High-temperature products, such as porous magnetito, would be synthesized and characterized for this purpose.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research The results of this research would form the basis for replacement of Icw-temperature ion-exchangers with high-temperatures high-pressure products.
This would eliminate the need for costly heat exchangers, result in energy and cost savings, simplify operation, eliminate intrusion of corfosive's
~
from the resin into the coolant, reduce cost, size and complexity of radwaste disposal, reduce radioactivity exposure of personnel, etc.
This procedure could potentially be used by all US operating nuclear power plants.
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2 APPENDIX B
,4 U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM.
(SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office ITM Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Name and Address of Proposer Massachusetts Technological Iaboratory, Inc.
312 Austin Street W. Newton, MA 02165 Name and Title of Principal Investigator Tsu-Peng Lee, Princi al Engineer Title of Project Computer Program for the Worst Ioading Combination Analysis of Nuclear y
Power Plant Structures Technology, Research Thrust and/or Potential Connercial Application (Limit to 10 words)
The software package developed will be extremely useful for industries.
Technical Abstract (Limit to 200 words)
For Nuclear power plants, the structure subject to the static, thermal, and dynamic loads at multiple loading locations, the loading combination events are given by:
b N=2 where N - is the number of loading combinationevents, L - the loading cases (loading degrees of freedom) 2 - indicates both the upper and lower bound loads at each degree of freedom.
Each structural member or support has its own worst loading combination.
[
Currently, engineers usually make trial loading combinations by his judgment e We are proposinv to develon such a comnuter ernernm to nni ve thi n nynhlom-Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research A complete structural analysis including the exact solution of the worst loading combination for every structural member and support will be provided. This sof tware package can then be used as a gerteral.. structural analysis program for nuclear power industries.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINES5*lNNOVATION RESEARCH PROGRAM.
(SBIR-85)
PHASE I - FY 1985 PROJECT-
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer.
James D. Freels Technology for Energy Corporation One Energy Center, Pellissippi Parkway Knoxville, TN 37922 Name and Title of Principal Investigator James D. Freels, Engineer,- Engineering--Analysis Department j
Title of Project
.v A Finite Element Penalty Algorithm for Multi-phase Fluid Transients lechnology, Research Thrust and/or Potential Comercial Application (Limit to 10 words)
More efficient, stable, accurate, and versatile alcorithm; LWR transient analvsis Technical Abstract (Limit to 200 words)
A more efficient, stable, accurate, and versatile numerical algorithm for solving multi-phase, time-dependant fluid flow equations typical of LWR systems is needed. Algorithms embedded in existing reactor system simulators are not ideal for various reasons.
This proposal de: scribes an entirely new concept for a finite element penalty algorithm for solving these types of system equations.
This algorithm has proven to have the desired improvement characteri:, tics for high speed compressible, time-dependant, and single-phase fluid flow scenarios typically encountered in the aerospace industry.
The proposed algorithm is directly extendable-to the fluid flow scenarios desired to be simulated in the nuclear industry.
b Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research. A finite element penalty algorithm solution of the 1-D, two-phase, transient, fluid flow equations will result in increased CPU efficiency, solution accuracy, 1
solution stability, and algorithm versatility. The Phase I effort will c,omplete the algorithm derivation and demonstrate the solution for a simple problem. The Phase 11 effort will imple-ment the algorithm on the full equation set, couple the equation system to a heat conduction model at appropriate boundaries, and validate the results against experimental data. Should the project be successful, existing code modification or new code development will significantlj impact the manner in which LWR transient analysis is performed, and would make an engineering simulator more of a reality for operator training, performance, improvement, through model study, etc.
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APPENDIX B i
U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS 1NNOVATION RESEARCH PROGRAM (SBIR-85) l
~
PHASE I - FY 1985 1
PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TTM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Aodress of Proposer SFANEST, Inc.
8205 Harwood Avenue, N.E.
Albuquerque, NM 87110 Name and Title of Principal Investigator H. M. Stoller D. W. Jackson Vice President-Technolcav Develoanent Senior Scientist
=
Title of Project We Investigation of the Ccmplex Resistivity / Induced Polarization Technique for Monitoring of Nuclear Waste Repositories Tecnnology, Research Thrust and/or Potential Connercial Application (Limit to 10 words)
Electrtrugnetic Gecchyscial 'Ibchniaue, Ocmical/Electrochenical Analaysis, Non-Intrusive Technical Abstract (Limit to 200 words)
Diagnostics
%e complex resistivity / induced polarization (CR/IP) geophysical technique is denonstrating the capability to discriminate rock types and mineral ccmplexes when applied to mineral exploration. It has also provided unique signatnre when apolied to hydrrywhnn characterization. mis indicates the potential to develop this technique for the chenical and electrochenical analysis of groundwater / basalt / repository inter-actions. If successfully developed, a non-intrusive method to manitor the integrity of nuclear waste repositories will result.
Representative samoles of basalt, groundwater, associated imourities, recository effluents (e.g., canister materials, radionuclides, etc.) will be subjected to CR/IP test-ing to der _ernine if unique spectral signatures can be associated with each sample and l
mixtures of samples. A nathcratical mcdel will be developed to predict the CR/IP response to be developed as a function of geology / repository configurations and instrumentation systen characteristics. Scoping studies will be conducted to assess the sensitivity of the technique under near-field and far-field measuranent conditions.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research Phase I results should establish the feasibility of the CR/IP technique to monitor and analyze nuclear waste repositories. h e Phase II program would develop a practical CR/IP systen capable of Ironitoring repositories.
In addition to nuclear waste reposi-tories, other applications couldbe the monitoring of toxic waste disposal sites and the monitoring of enhanced oil recovery processes.
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U.5. Il0 CLEAR REGULA10RY C0f tl11SS10tl Si1ALL BUSINESS.lfill0VA110N RESEARCil PROGRAM (SBIR-85)
PilASE I - fY 1985 PRO, JECT SUf4fiARY FOR llRC USE ONLY Program Office-11H Proposal No.
lopic No.
10 BE COMPLEIED BY PROPOSER Hame and Address of Proposer Engineering Science & Analysis, ESA 836 Claire View Street Idaho Falls, Idaho 83402
'llame and litle of Principal Investigator Dr. August W. Cronenberg, President ESA 1itle of Project Hydrogen Generation and Blanketing. Assessment for Severe Accidents t
lechnology, Research ihrust and/or Potential Lomercial Application (Limit to 10 words) l TechnicalAbstractlLimitto200words)Hydrocen Control System Desian/Reaulatory'
~!
' I The accident at IMI demonstrated that large quantities of hydrogen can be generated as a result of zirconium-steam oxidation reaction, which poses a hydrogen burn threat in LWR containments.
The rates at which-the core heats up and which hydrogen is generated depends upon the zirconium-deam reaction rate, which in turn is influenced by local steam starvation and hydrogen blanketing effects.
The purpose of this project is to perform a synthesized analysis of recent PBF, NRU, and ACRR test data in terms of hydrogen generation and its blanketing effect on the reaction Such work is in support of Nuclear Regulatory Research to advance analysis process.
methodology on fuel assembly behavior for severe accidents, e d assess the need for and design limits of containment hydrogen control systems for, *esent and future power plants.
Rnticipated Results/ implication of the Approach (both Phase I and II/ Potential Commercial Rpplication of Research
.The anticipated results are an in-depth analysis and syntheses of the PBF, NRU, and ACRR hydrogen generation. data, and qualification of present steam-zircaloy-reaction correlations con',idering a hydrogen blanketing effect.
Results will be directed at
. qualification of a predictive capability for the steam-zircaloy reaction for severe -
accident analysis codes, such as SCDAP (NRC) and MAAP (IDCOR).
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U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE 1 - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office 1TM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER
-Name and Address of Proposer International Technical Services, Inc.
60 East 42nd Street, Suito 2316 New York, NY 10165 i
Hame and Title of Principal Investigator' Dr. Hideko Komoriya, President Title of Project 5
Hodal Diagran Generator Development Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
Construction of Hodal Diaeran Ganerator to draw nodal diacrann fron unar innut dockn Technical-Abstract (Limit to 200 words)
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A najor disadvantage in every systens code in that their accociated graphics packages do not draw nodal diagrans based on the input decks.
A hand drmm schenatic prepared carly during nodel preparation is highly susceptible to errors because of the lack of a sinplo ncchanita to permit the code user to check his actual numerical input against his conceptual diagran.
ITS proposes developnent of a nodal diagran generatien (UDG) package which would read the nornal user input (TR/.C.EELAP),
together with a celected few key variables which the uscr nust input to guide the UDG, and built from that data a conplete nodal diagran scaled to user specifications in varicus conponents/rc61ons, or a wholo-plant drawing with the voluns and junction nunber identifications.
Such a diagram will serve to eneck tne input and pernit the user to visualico the studies he/she is perforning. Other user aid oriented options will also be pursued.
ITS also propocos to develop the graphics software for micro connuters, so that plotting can be done by the analyst on his desk top personal conputer (PC),
rather than continuing to rely up~on the inefficient and expensive nainfrane for such taskno Anticipated Results/ Implication of the Approach (both Phase I and ll/ Potential Commercial J
Application of Research ITS will develop a Hodal Diagran Generator (HDG) for TRAC during Phase-I (and RELAPS in Phase II) which would read geometrical data directly from an input deck and generates, as its ouput, scaled diagrams for various regions, conponent; and or the whole plant, with or without initial conditions printed on the diagran, with or without spatial nofes, etc.
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similar program for an IBM and its compatible personal conputersvill also be developed.
Use d
of such software will eliminate human errors and result in consistency butween the analysts' intention and the input deck at all tine at a mininal cost.
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U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office ITM Proposal No.
Topic No.
J TO BE COMPLETED BY PROPOSER Name and Address of Proposer Seismic Research Associates, Incorporated 2601 D Street Sacramento, CA 95816 Name and Title of Principal Investigator Mr. James B. Anderson, P.E., CEO Chief of Research and Develonment Title of Project Earthquake Warning Project Technology, Research Thrust and/or Potential Commercial Application (Limi? to 10 words) d"NNN e-Earthouake Enriv ?!arni w Svetem - nrntect nuhlin_ n u ni o n y-The proposea pro' ject is for the cevelobment.
Technical Abstract (Limit to 200 'words)lert system to provide warnings.to the general o f an early warning earthquake a population and shut-down warnings to nuclear power plants immeaiately before an. earthquake occurs.
It may have longer ranged benefits by indicating safe seismic conditions for launching NASA recovery vehicles in earthquake regions.
A recovery vehicle could destroy an entire launching area if struck by an carthquake during launching operations.
The system is based on sensing electronically the same pre-earthquake signals that animals sense prior to major earthquakes. Such a sensing was actually made by an instrument prior to the 1971 Los Angeles Earthquake by a laymen who f ailed to understand the significance of what he observed and did not report it. The same instrument is used as a prototype for the project which will be targeted to predict epicenters to 20 miles, time frames to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and the intensity to an order of 1 Richter magnit'ude.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research Phase I has no suplication; it consists only of developing an operational electronically sensed. recording prototype and fabricating 100 like elements for field installation. (Ferhaps a new type of imprinting digital recorder?)
Phase II has no direct commerical application; it consists of recording a new type of seismic signal at 100 heretofore considered improper rensing sites. Phase II confirms the validity of the research investigation in the field and provides the basis of a major expenditure for final integrated system (Project is back-up for USGS 3362,000,000 research project.)
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APPENDIX B U.S. NUCLEAR. REGULATORY COMMISSION SMALL BUSINESS INNOVA 110N RESEARCH PROGRAM (SBIR-85)
PAASE I - FY 1985 PROJECT
SUMMARY
~
FOR NRC USE 0NLY Program Office TIM Proposal No.
Topic No.
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TO BE COMPLETED BY PROPOSER Name and Address of Proposer SYSTEMS ENGINEERING, INC.
7833 Walker Drive, Suite 308 Greenbelt, MD 20770 Name and Title of Principal Investigator N. Barkakati, Senior Engineer Title of Project Condensation Heat Transf er Model Development Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
Technical Abstract (Limit to 200 words)
Condensation effects are very important in nuclear reactor systems. The pressur e dr op asso-ciated with condensation may result in flow acceleration, flow esci11ations, and other re-lated phenomena. These in turn may result in dynamic loading of pipe lines (waterhammer),
delay in EEC refill-reflood, unstable operation of a system, etc.
In this task, available data on condensation effects observed in nuclear reactor systems are cited.
The condensation models that exist in REIJG and TRAC computer codes are evaluated regarding their ability to model the variety of condensation phenomena and acsociated effects.
Results of condensation calculation using the above codes are discucsed.
T}ie origin of the condensation models is given, compa ri son of the va rious model s are made :-o d is discucsed.
- Finally, the applicability of the:5e models to study the various phenomena
- sreco:x.endations are made for improvements of the condensation modelc.
Anticipated Results/ Implication of the Approach (botn I' nase I and 11/ Potential Coinaercial Application of Research and TRAC to model Evaluate the ability of the condensation heat transfer mudels used in RELAP condensation effects of interest in nuclear reactor systems. Recommend improvements. The cccnercial application will occur following the implementation of the re,cc:=endations into RELAP snd TRAC.
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APPENDIX B i
U.S. NUCLEAR REGULATORY COMMISSION (2)
SMALL BUSINESS INNOVATION RESEARCH PROGRAM
,(EBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
4 i
FOR NRC USE ONLY Program Office 1TM Proposal No.
Topic Ho.
10 BE COMPLETED BY PROPOSER Name and Address of Proposer EcoTech, Incorporated i
5418 Tonnalle Avenue j
North Bergen, NJ 07047
[
Name and litle of Principal Investigator j
Lawrence P. Gradin litle of Project Realistic Aging and Qualification Requirerrents For Elastomeric O-Rings Technology, Research Thrust and/or Potential Conmercial Application (Limit to 10 words)
Reduce Plant Cost, Enhance Plant Safety f
Technical Abstract (Limit to 200 words)
Nuclear Safety Related equipment, especially that exposed to a harsh environtrent as a result
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of Loss-of-Coolant Accidents (LOCA), Main Steam Line-Breaks (MSLB) and High-Energy-Line Breaks (HELB) often depend on clastoneric O-Rings as a neans of sealing devices.
However, the review of the end of life criteria used in industry in regards to suscept-ability of these devices to significant degradation due to thernul and radiation aging reveals mwy inconsistencies.
Criteria selected, typically include reduction in tensile strength, e.longat jon and other
'elastcner cable criteria". Den the concepts of compression set Iray have little nenning in light of the successful cualification programs which must have included nea-100% com-pression~ set 0-Rings.
Rather than 2nadequacy in qualification criteria in regards to O
plant safety, the present practices : rey be leading to toe frequent 0-Ring replaceacnt.
This Phase 1 innovative research effort is based on a comprehensive review of existing doctmentation, discussion with experts in the O-Ring-field t.o provide a realistic hy-1 pothesis and determination of reasonable life values for static 0-Rings used in nuclear j
power plants. The final deliverable is a report and proposed test plan to verify the hypothesis established.
4 Tne proposed innovative research provides an opportunity to reduce plant cost and en-l-
pance plant safety.
i Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Ccm.aercial i
Application of Research i
1.
Reasonable O-Ring replacenent schedules based on need t o enhance plant safety, j
i 2.
Reduced frequency'of O-Ring replacenent where unnecessary to:
- Reduce Utility Resource Burden.
- Reduce challenms to sound equiptent integrity by unnecersary maintenance.
I 3.
Methods to extend component and plant life based on t echnical basis.
4.
Reduction in present uncertainty in acceptability of exist ing qualification data.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS.lNNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE 1 - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office 11M Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Norton Corrosion Limited, Inc.
22327 89th Avenue S.E.
Woodinville, WA 98072 Name and Title of Principal Investigator John S. Tinnea, Senior Project Engineer Title of Project Close Grid Electropotential Mapping for Reinforced. Concrete Aging Evaluation
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Research Thrust and/or Potential Conmercial Application Ilim{it to l'0 words)
Technology, ion of reinforcement. steel oorces).on;1n. concrete through elec ropotential mapping.
Determinat Technical Abstract (Limit to 200 words)
Previous work by this proposal offeror has indicated that close grid electropotential half cell mapping of corrosion distressed steel reinforced concrete may be used as a measurement technique to define existing corrosion activity which may be used in quan-titative or semi-quantitative models to generate time-to-failure predictions. Work to be performed includes reinforcing steel electropotential mapping, conductivity measurements, a mathematical relationship between observed electropotentials and corrosion activity.
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Anticipated Results/loplication of the Approach (both Phase I and ll/Fotential Comaercial Application of Research Develcpment of a mathematical model using electropotential values for determination of l
time-to-corrosion failure of steel reinforced concrete structures.
Such a mdoel would allow the making of clear property management decisions regarding action on. corrosion distressed steel reinforced concrete structures.
By identifying corrosion before signi-
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ficant structural damage is incurred, cathodic protection could be employed with savings 3
realized in the billions of dollars.
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APPENDIX B i?
U.S. NUCLEAR REGULATORY COMMISSION
/
SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
/
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer GANDHI ENGINEERS & ASSOCIATES, INC.
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2446 Reedie Drive, Sujie # 12 Wheaton, Maryland 20902 Name and Title of Principal Investigator (1) Mahendra R.
Gandhi, P.-E.
(2) Leonard Pinzow Proiect Manacar A cicrant PrnJrce ",", r -
Title of Project c
Validation of the NRC Fire Protection guide lines described in the Guidance material published by NRC since 1975.
.v
'Tecnnology, Research Thrust and/or Potential Conmercial Application (Limit to 10 words) Correct Interpretation of NRC Guidelinne for Nncionr Pinnt ic n e nnrini Technical Abstract (Limit to 200 words) A major fire danaging safe shutdown equipm@
occurred at the Brown Ferry Nuclear Station in March 1975. The fire damaged over 1600 electrical cabics and caused the temporary unavailability of some core cooling system.
Because this fire did substantial damage, the NRC established a review group t o improve the fire protection programs. The review group has prepared the fire protection guidance material, (including 10CFR50, Appendix R) which is listed on page B-2. At present NRC is seeking assistance in validating of the NRC fire protection requirements described in this material and also in determining of the safety nafgins that exists in the fire protection guidelines used in licensing.
c Anticipated Results/ implication of the Approach (both Phase I and II/ Potential Concierciai Application of Research There are several cases when the application and i=plementation of this material (see page B2) has been applied incorrectly because of the wrong interpretation and confusion. The Candhi Engineers & Associates, Inc,. intends to write a simplified guide lines along with the sample illustrations to help utilities to
)
carry out the implementation of the guidance material. By doing that GEA will validate the NRC approach and published material for the fire protection guidelines. GEA will also clarift the NRC approach on safety margins in relation to the fire protection for the Nuclear Power Plants.
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APPLHDIX B
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U.S. NUCLEAR REGULATORY COMMISSION
/^
SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
M1ASE 1 - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office llM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER i5'me and Address of Proposer o".
Fracture Proof Design Corporation s
77 Maryland Plaza I
- s St. Louis, MO 63108 N
1
, Name and Title of Principal Investigator Dr. Hiroshi Tada
- Titie of Project
k Energy Absorbtion Characteristics of Cracked Pipe Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
Demonstrate safety of cracked pipes during seismic / water hammer events Technical Abstract (Limit to 200 words)
Structural ductility methods (SDM) for evaluating the integrity of piping rely on the energy absorption characteristics of cracted sections. The emphasis of the program will be to extend (SDM) to the analysis of water hammer problems. The original SDM formulation was limited to the analysis of bending loads and was based on an elastic perfectly plastic f ormul a ti on.
Thus, the analysis of axial loads and axial pins bending must be included.
The formul a ti on will also be extended to include estimates of J,pp based on hardening essc=ptions. Methods will be developed for bounding the stored energy of various classes of water hammer events such as the steam bubble collapse and valve slam.
The effects of discontinuities on energy absortion charasteristics will be included. As the SDM rell's on tearing stability, this project will also include the development of simplified method.
for the computation of T,pp.
I1is approach will permit computation of T,pp, by hand analyses without having to resort to the use of finite element methods.
e Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research It is expected that a criteria for the analysis-of cracked piping under water haemer loa ding (and combined with. other loads) would be developed.
In conjunction with this, simplified methods for computing T,
wonid be prepared.
Finally alternate design 7
- methods, such as criteria for the e$$mination of snobbers and other restraints, could be 8
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assessed. The resnits would provide a basis for eliminating the requirement to postulate breais for pipe-whip protection in systems prone to water hammer events.
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. APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PWASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Propocal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Daniel & Associates, Inc.
P.O. Box 40 Rheems, Pennsv1vania 17570
- Nama and Title of Principal Investigator' J.A. Daniel. President Title of Project N
SPENT FUEL MODEL ASSESSMENT h
Technology, Research Thrust and/or Potential Connercial Application (Limit to 10 word Accident Analysis: Soent Fuel Storage: Source Term Technical Abstract (Limit to 200 words) t The work proposed in this effort focuses on the ability of existing computer codes to model fission product release from accidents involving the following concepts in spent fuel storage;
- 1) High density spent fuel storage
- 2) Consolidated fuel rods in storage cannisters
- 3) Dry storage of spent fuel 2:
This work will also identify specific areas in which code development or code enhancement is needed, and will also identify key parameters involved in the evaluation of spent fuel storage safety evaluation. This work will be conduct- ~
ed by a team of professional engineers and scientist familiar with NRC regula-tions accident analysis techniques, and a knowledge of the practical solutions to the spent fuel storage problem.
-Anticipated Results/Irplication of the' Approach (both Phase I and II/ Potential Commercial Application' of Research This' work provides a review of existing codes and their ability to evaluate the safety of spent fuel storage. It is of benefit to both the utilities and the NRC for evaluating the safety aspects of. spent fuel storage schemes. It provides an assessment of computer codes that could be used 'in spent fuel storage accidents and ~will' identify deficiencies where improvements must.be I
made. Phase II will. provide the industry-and the NRC with a more consistent, complete and better oriented set of codes for spent f,uel' storage safety eval-uations and accident predictions.
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APPENDIX B
,e#
U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETE 0 BY PRCPOSER Name and Address of Proposer Daniel & Associates, Inc.
P.O. Box 40 Rheems. Pennsylvania 17570 Name and litle of Principal Investigator J.A. Daniel, President Title of Project CORRELATION OF RADIOIODINE RESUSPENSION WITH TEMPERATURE AT TMI-2 Technology, Research Thrutt and/or Potential Commercial Application (Limit to 10 words)
Radiolodine Resuspension: Fission Product Behavior: Accident Analysis Technical Abstract (Limit to 200 words)
The work proposed in this effort is directed towards determining the correla-tion between observed airborne radiciodine concentrations in the Auxiliary and Fuel Hand]Ing Buildings at TMI-2 following the accident in 1979 with diurnal temperature variations. Appro,imately 5000 measurements were made during the period April -July, 1979 in designated areas of the Auxiliary / Fuel Handling Buildings and the data has been collected and compiled by the proposed con-tractor, Daniel & Associates. Inc.
Anticipated Results/ Implication of the Approach (both Phase I and II/Fotential Commercial Application of Research This work would utilize data from an actual accident to increase the indus-try's knowledge of radiciodine resuspension phenomena, and would allow compar-isons to be made between actual accident conditions and controlled laboratory experiments. Follow-up work (Phase II) would develop mathematical models for predicting radioiodine resuspension, and, (using results of other investi-gators) develop models for resuspension by species. It would provide the Industry with a technical basis f or establishing regulatory guidelines and design improvements of safety systems.
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9 U. S. NUCLEAR REGULATORY COMMlSSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SB I R-f35)
PHASE I - FY 1985
" PROJECT
SUMMARY
IOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
10 BE COMPLETED BY PROPOSER Name and Address of Proposer ARIES (Advanced Research in Emergency Simulation) 32 Willow Drive, Suite IB Ocean, New Jersey 07712 Name and Title of Principal Investigator A.
Ben Clymer, P.E.,
Consulting Engineer Title of Project -
Simulators for Risk Analysis Rescarch and Emergency Management
-lechnology, Research Thrust and/or Potential Comnercial ApplicationlLimit to 10 words)' ~
4 Original commercial simulators for risk research analysis and emergency management.
Technical Abstract (Limit to 200 words)
The project will investigate, specify, and evaluate
~~
feasibility of four novel types of simulators intended to support risk analysis and compre-hensive emergency management functions and to enhance safety onsite and offsite of nuclear power plants.
One simulator is a st ochastic emergency generator that uses Monte Carlo to accumulate statistics for a class of compound emergencies t rigg ered by nonlinear algebraic an logical failure criteria for purposes of R&D.
Another simulator daes real time sinulation of preselected onsite emergency, including offsite propagation and evacuation processes, in-a teracting with actual or simulated emergency personnel, and determining cumulative severity of the emergency, for R&D, planning and training exercises.
Another produces fast-time onsite and offsite, and severity, for online emergency management during an emergency.
Another permits adjust abic accel era t ed-t ime int eract ive study of public evacuat!cn prm e
'es with assumed.erning systent in a radicactivity cmergency, with emphasis on arr2Vals of utility an( agencies' personnel, plant deliveries, etc.. and evacuation of plant perso.nel fer the plant's external emergency setpunse planning.
One objective is to e> tend risk and severity assessment methodologies and data i,t o regimes of models that are not purely looir. nrnhabilictic. and evont-oriented.
Anticipated Results/ imp'lication of the Approach (botn Phase I and II/Pctential Comercial Application of Research Project wil1 provide marketing impetus and engin;ering specifica-tions for a maaufacturer to develop, produce, and sell profitably, four simulators that will be valuable to NRC, utilities, and state and local agencies concerned with risk analysis and emergency management in and around nuclear power plants.
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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBTR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Flow Industries, Inc.
21414 68th Avenue South Kent, WA 98032 Name and Title of Principal Investigator Frederich R. Reich Acting Manager, Nondestructive Examination Titl@ of Project Enhanced Quantitative Flaw Detection for Pressure Vessel and Piping Systems Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
Technical Abstract (Limit to 200 words)The current ultrasonic inspection used on welded joints for nuclear pressure vessels and piping is a manual process based on the use of fixed procedures with multiple transducer configurations.
Manually assisted devices such as the "P" scan system and the SWRI (South West Research Institute) S.0.U.T. A.R.S. are currently being used.
In the "P" Scan system, d,eveloped by the Danish Welding Institute, position data from a probe carrying arm is used to produce an acoustical map of the inspection area.
In the S.0.U.T.A.R.S. system, -
flaw dimensions are determined through relative time of flight information using triangulation L-techniques with multiple transducers.
The inspection reliability in both examples is improved c
with the use of multiple probes and array based data processing.
The objective of this Phase I proj ect is to evaluate and demonstrate the feasibility of a unique, multiple probe inspection concept which would increase the reliability and precision in locating defects near welded pipe joints.
In this tandom probe process, acoustical data would be mapped over an area adjacent to the acoustic source such that the flaw dimensions (depth and width) are related to dimen-sions of this mapped pattern. The concept would be verified with both real and manufactured c
crack flaw samples.
Phase 1 data would then be used to develop a Phase I prototype inspection
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s- ^tiiiiVate'd'Resulfs/lI@licaEibn"of th'eAjijiro'aEH~-(fidth ' Phase I and II/ Potential Commercial An Application of Research Both the range of inspectable components and inspection reliability will be improved with this inspection concept. The inspection has a high potential for automation where an operator's subjective judgment factor in the interpretation of acoustical data is eliminated. Since the
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inspection area needs to be accessed frca only one side, difficult welded. areas near elbows and bends can be inspected.
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U.S. NUCLEAR REGULATORY-COMMISSION
.. /
SMALL BUSINESS.JNNOVATION RESEARCH PROGRAM.(SBIR-85)
PHASE I - FY 1985
'/
PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TTM Proposal No.
Topic No.
TO BE COMPLETE 0 BY PROPOSER Name and Address of Proposer ENSA, Inc.
966-Hungerford Dr. (Suite 11B)
Rockville, Maryland 20850 Name and Title of Principal Investigator
'B.
J..Gitnick
~
e Title of Project
~ Microcomputer ~ Based User Interface for Reactor Transient Code 5
Tecnnology, Research Thrust and/or Potential Commercial Application (Limit to 10 wor Reactor Transient Analysis Microcomputer Man-Machine Interface Technical Abstract"(Limit to 200 words)
The Phase I research task will design and test a user-oriented, color graphics input processor which minimizes the effort required to. efficiently develop o,r revise thermal-hydraulics systems code input data.
This processor will rely on an intuitive format to simplify the user interface.
Graphical and-Iconic representations of. reactor systems will be presented which will allow use of pointing devices such as a light pen or a mouse.
c Color graphics will be used to present the information in a compact fashion.
This processor will be linked to a microcomputer based transient code ~for testing and user interface studies.
l Anticipated Results/ implication of the Approach (both Phase I and.II/ Potential Commercial Application of Research Demonstration of.the feasibility of a general preprocessor procedure.in Phase'I,.will provide the basis for development of an operational TRAC-PF1 preprocessor in Phase II.
facilitate the process of developing working system models with TRAC-RF1. Succ 1
It is estimated that an average of one to two man-months of engineering 1
effort will be saved by use of the preprocessor on each system model.
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U.S. NUCl.[AR RIGULA10R'r COvMl.510N i
SMAll BUSIN[M JNNOVAIION RE.5E ARCP PROGRAM (SBIR-CS) l PHASL 1 - FY l'M5 PRO.Il C I
SUMMARY
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l0K NRC USL ONLY Program Of1 ice iIM Proposal No.
Topic No.
~10 l!I CoMPl l ! [ l) !!Y PROPOSI I l
he and Athlress of Proposer p
International Technology Corporation (INTEC) 1670 Highway AlA Satellite Beach, Florida 32937
~Name and Title of Principal I nves ti g'a to r Dr.
J.
B.
Gayle, Project Manager litle of Project Conflict Reduction and Oversight in Risk Analysis Programs Technology, Research Thrust and/or Potential Commer.cial Application (Limit to 10 words)
Datametric Convergence Technology fo'r Opinion / Analytic Content Regimes
-Tecnnical Abstract (Limit to 200 words)
Many risk analysis programs must contain certain amounts of expert opinions.
However, the overall complexities, and the need for large numbers of inputs from widely diverse indepth technologies involved, often lead to broad divergences in thece opinions.
This must, of course, be recognized as being both expectable and desirable.
The broader the spectromatic base from which any risk is analyzed, the greater the credibility of the
)
analysis.
The problem is not one of climinating or reducing divergent input.
It is, rather, one of establishing a statistically sound pro-cedure whereby these divergent inputs can be coalesced into a credible convergent output.
A means of accomplishing this objective, along with a procedure for monitoring and updating results, is presented herein.
Anticipated Results/Irpplication of the Approach (both Phase I and !!/Pctential Commercial Application of Research Development and application of the tools and procedures herein proposed will allow significant increases in credibility and accuracy in any risk analysis scenario involving expert opinion content.
Potential applications, in addition to the nuclear energy field, would include
'such areas as: toxic waste, endangered species, environmental impacts, and new medical advances.
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U. S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
+. o PHASE I - FY 1985 Y
FROJECT
SUMMARY
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24 l7 Y
FOR NRC USE ONLY llM Proposal No.
Topic No.
g ftice TO BE COMPLETED BY PROPOSER Name and Address of Proposer International Technical Serviccc, Inc.
60 East 42nd street, suite 2316 New York, NY 10165 Name and Title of Principal Investigator, Dr. Hideko Konoriya, President Title of Project Plant-Specific Data Collection for Nuclear Plant Data Bank Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
Availability of reliable plant-cpecific data through the NPD3 for cafety analysis Technical Abstract (Limit to 200 words)
In order to develop input decks for plant-specific computer code calculations for cafety analycic, it ic necessary to have sufficient geometric and operating data on the prinary and ceconda'ry cystent, balanco of plant, and the trip and control cystens, etc.
Even with tne close cooperation of the plant oaners, it ucually taica nenths for the analyst tc ;btain catisfactory plant cpecific noainal operating data such as, upper-hcad recirculation ratio, licaid inventory dictribution, ctean Generator conditions, etc. The existing Nuclear Plant i
Lata Bank (NPD3) will sorve to store plant data sufficient to perfern detailed plant and trancient specific safety ana2ysis and Chapter 15 analysis.
In Phase I of this work.
ITS will becone familiar with the data bank, investi ate the feccibility of ctoring plant data 6
with nulti-level of security protection (i.e.,
for proprictary data) exanine existing data and currently available data cources, and develop and detenctrate nethods by which neu data can be rathered, Quality Accured, and entered into the I!FD3.
In Phase II ITS will assist the NhC with prioriticing plants and will then gather and enter into the NPD3 pla,nt specific data baced upon the priorication.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research ITS will gather and O/A conplete geonotric and operating data, sufficient enough details to develop input decks for plant-specific conputer codo calculations for safety analycis, Chapter 15 analy31c a:.d a cpectrun of the liniting transient analyces.
Collected data will include noninal operating conditions on the prinary and secondary systens, balance of plant, the trip and control systens, upper-head recirculation pattern and ratio, core / bypass flow c
ratio, liquid inventory distributior throughout the cysten, etc.
Data and canple input decks will be stored in the Nuclear Plant Data Bank.
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U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85) f PilASE I - FY 1985 PROJELT
SUMMARY
FOR NRC USE ONLY Program Office llM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Expert-dASE Systems, Inc.
932 Santa cruz Avenue Menlo Park, CA 94025 Hame and Title of Principal Investigator Bjorn Frogner, Director of Consulting Services Title of Project Use of Workstation and Expert Systems Technologes to Facilitate Development and Evaluation of Fault Trees Technology, Research Thrust and/or Potential Cormercial Application (Limit to 10 words)
Risk analysis, fault trees, excert systems, works ta ti ons Technical Abstract (Limit to 200 words) potential of Workstation and expert system technologies have a substantially facilitating the development and evaluation of fault trees.
Introducing a workstation philosophy with an interactive set of integrated software tools on a local computer will promote im-proved continuity in the thought process during a fault tree develop-ment.
The expert system technology will simplify the way fault trees are rpecified and it will allow the incorporation of various kinds of pr i or knowledge and experience.
These new technologies will enhance the ability to effectively produce high quality fault t r ees and improve the insight into the plant failure modes.
The objective of the research described in this proposal is to show the validity of these claims by developing a demonstration system.
Anticipated Results/ implication of the Approach (both Phase I and II/ Potential Conaercial Application of Research The result of this research has the potential of simplifying the way probabilistic risk analysis is performed and, thus, expanding the usage of fault tree codes among the electric utilities.
It will be easier to generate and modify the fault trees and new featuies will become available.
Furthermore, several limitations of existing codes will be reduced because the new algorithms are expected to be faster and more flexible due to the use of more suitable software tools.
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f U.S. NUCLEAR REGULATORY COMMISSION SMALL BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TTM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer l
[
Materials Engineering Associates (California) Ltd.
403 Mc Cormick St. San Leandro, Ca. 94577 Name and Title of Principal Investigator Dr. Bruce Maxf ield, President, MEA Title of Project EMAT Defect Characterization of Nuclear Reactor Piping Welds I
Tecnnelvyy, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
EMATs. Ultrasonics. N.D.E.
wold. cinnaf nrncoecinn. e.vnthotic anoc+nrn Technical Abstract-(Limit to 200 words)
~
Within a laboratory environment EMATs have been used to characterize defects in both ferritic useful.fo,and austenitic welds. The use of shear-horizontal (SH) waves has proven particularis r the through wall sizing of planar defects.
For fracture mechanics evaluation of welded ~ structures, it defects. This pro is particularly important to know the through wall extent of planar characterization.posal seeks support for the evaluation of a new approach to weld defect It is p)roposed to use EMATs generating a combination of SH, shear-vertical
( S V) and longitudinal (L waves to interroqate the entire volume of a weld from crown to root. Each ERAT in the combination provides information about defects within a portion of the weld tne EMATs; a complete assessment comes only f rom using inf ormation f rom all EMATs. Some of 1he beam angle. The result of this multiple interrogation of the weld f rom dif ferentin inis evalu used ahgles is a much increased reliability of the ultrasonic evaluation.
(The probability of missing a defect is very small.) Signal processing methods such es temporal averaging spatial averacing and synthetic aperture techniques will be used to increase the accu, racy of def ect sizing,,especia!!y determining the through-wall extent'. of. a def ect. This project will also determine how best to implement automated _ inspection _methocs for one or more combinations of EMATs.
4 Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research This project will demonstrate that more reliable and more accurate weld def ect cha. acterization can be achieved using a combination of EMATs that cenerate a variety of elastic wave modes. Moreover, this project will show that an EMAT approach developed for characterizing defects in a particular type of weld can be incorporated into an automated scanning apparatus, thereby removing the operator dependent ingredients in an ultresonic field evaluation of a weld. This technology would find widespread use for both pre-service quali fications of nuclear reactor piping system welds and in-service inspection. Benefits include the orderly scheduling of downtime, the ability to make a more accurate and reliable assessment of the life remainin0e in a defective component, lecrovc-d n innt cafety and fn a-
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fox, Page 2 of-19 APPENDIX B
'U.S.
NUCLEAR REGULATORY COMMISSION SMALL. BUSINESS INNOVATION RESEARCH PROGRAM (SBIR-85)
PHASE I - FY 1985 PROJECT
SUMMARY
FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer Michael Fox, Ph.D.
7490 Stanford Place Cupertino, CA 95014 Name and Title of Principal Investigator Michael Fox, Ph.D., Independent Consultant Title of Project Aging Effects on Stress Corrosion Cracking Technology, Research Thrust and/or Potential Corinercial Application (Limit to 10 words)
Electrochemistry and Corrosion in BWRs Technical Abstract (Limit to 200 words)
In-reactor measurements ~involving electrochemical potential (ECF) and intergranular stress corrosion cracking (IGSCC) in a number of boiling water reactors (BWRs) suggest that the water chemistry of the primary coolant of each BWR may be unique with respect to its ability to facilitate IGSCC and/or may change with reactor operating time or age.
The work proposed is to gather, revi ew, organize, compi l e, computerize, and analyze in-reactor data pertaining to the potential uniqueness of BWR water chemistry.
The desired goal is to determine if BWR water chemistry is sufficiently un2que and/or time-dependent to affect NRC policy.or regulatory decisions and whether further investigation by the NRC is warranted.
Anticipated Results/ Implication of the Approach (both Phase I and II/ Potential Commercial Application of Research Unique BWR water chemistry has two serious i mpl i c at i on s.'
First, if each reactor 's water chemi stry _ i s uni que, then there can be no -generic remedies for a corrosion-related problem, such nuclear grade materials or hydrogen water chemistry as remedies for IGSCC.
Each reactor may need to
-qualify its chosen remedies using its own primary water.
Second, if reactor water chemistry changes with plant operating time or age, then remedies may need to be re qualified with time or age.
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PROJECT SUMMARk Government Solicitation No.
RS-RES-85-124 Name and Address of Proposer Linsley, Kraeger Associates Ltd.
527 Bayview Drive Aptos, Ca 95003 Name and Title' of Principal Investigator Ray K. Linsley President Title of Project Continuing Research on a ~ System for Generating Long i
Streamflow Records for the Study of Floods of a
Long Return Period I
i Technical Abstract This proposal is dir procedure for genera.ected to the enhancement a'nd te sting of a ting long streamflow sequences to be used
-as a basis for improving flo6d frequency estimates.
The procedure c6mputes a long sequence of hourly rainfall data using This synthetic-reinfall is then transformed into synthetica stocha streamflow using a deterministic hydrologic model.
The Phase I results indicate that this procedure has significant potential for stu'dy of floods of long return period.
The procedure will be applied to 4 to 6 watersheds in the United States selected to represent a range of climatic regimes.
This more extensive of the procedure. testing will help establish the applicability and reliability Anticipated Benefits If the research is successful it will:
i 1.Provideabasjsforestimatingfloodprobabilityat levels of;10-or less.
i 2'. Permit san evaltiation of the probability of the Prob-able Maximum Flood currently used for spillway design.
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'U.S.
NUCLEhR REGijLATORY COMM13510N
~"
SMALL BUSINESS INNOVATION'RESEARCH PROGRAM:
(SBIR-85)
PHASE-I - FY 1985
. PROJECT'
SUMMARY
s FOR NRC USE ONLY Program Office TIM Proposal No.
Topic No.
TO BE COMPLETE 0 BY PROPOSER Name and Address of Proposer a
M09R AND ASSOCIATES 1,440 Agnes St.
,Richl'and, Washington 99352 Name a,nd Title of Principal Investigator I)r. Charles L. Mohr, Principal Investigator Title of Project
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[PHASEII-TIMEDOMAINREFLECT0METRYLIQUIDLEVELDETECTIONCONCEPTASSES D.
EVALUATION R FP 6. RS-REs -fr-m4 Technology, Research Thrust and/or Potential Commercial Application (Limit to 10 words)
Dev'elopment of Reactor Vessel Coolant Inventory and Liquid Level Instruments Technical Abstract (Limit to 200 words)
The results of the Phase I program demonstrated the potential of the TDR-based. coolant liquid les detector concept. The NRU LOCA test program data, from tests using the first version of the prol were analyzed in Phase I.
These results gave, for the first time, a measurement of the coolant conditions during a LOCA in-reactor test on full-length nuclear fuel bundles. These new results provid'e 'the basis to assess the conservatism in the current Appendix K ECCS criteria.c The 'new u 'ctncepts'that were d~eveloped on improved probe designs have greatly expanded the potential of thi instrument and now make it possible to provide detailed assessment of the coolant conditions cluding density, water level, and turbulence.
, in-tha,Eoncepts identified as a result of Phase I and carry them into a developed probe instru Fundamental research on material properties, probe design, signal processing, and computer inter-facing will be performed as part of the work in developing a prototype concept.
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Anticipated Results/Im.dlication of the Approach (both Phase I and II/ Potential Commercial L
Application of Research ju The anticipated result of this program will be the development of a data base to substantiat ltha performance of a reactor coolant inventory system that will significantly improve the accider l man 7gement and control capability of a nuclear reactor. A prototype instrument will be developed
? cod demonstrated which, if implemented on a full scale, would literally allow the reactor operatc to view the condition of the coolant over the entire core at any time under normal operation, as
' v211 as the most severe accident conditions.
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'U.S.
NUC' LEAR REGULATORY COMMISSION
- 5. MALL BUSINESS INNOVATION-RESEARCH PROGRAM FJ0GDDDoecECOI900( PHASE II FY 1985 PROJECT
SUMMARY
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FOR NRC USE ONLY Prcgram Office TTM Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Name and Address of Proposer p
Dynatrek,Inc.,2115E.Jef5ersonSt.,Rockville,MD 20852-Name and Title of Principal Investigator i
Peter S. Andersen, Vice-President Title of Project On-line Plant Analyzer Utilization ir. Control Poan For Surveillance of Plant Safety Technical Abstract (Limit to two hundred words)
The scope of the proposed research is to develop software for a Plant Analyzer Controller I
(PAC) whose purpose is to supply and constantly update the boundary conditions to an i
on-line plant analyzer, enabling it to faithfully track a nunber of the continuously mmeasurW=Wameters..,dIhe, plant enalyzerywineturn, provides, detailed.sinformation.. e to a sophisticated multi-CRT display station mncerning reactor coolant's heat renoval capability and plant diagnostics.
'Ihe proposed concept is not limited to any particular plant analyzer. It is important, however, that the plant analyzer has a verified best estimate prediction capability and that it can run in real time, or faster, on a cmputer that can be installed in the plant control roan cr its vicinity.
Anticipated Results/ Potential Commercial Applications of the Research During Phase II of this reduced scope proposal the capabilities of the PAC will be exterrled to also handle severe transients in PWRs.
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,.y ll.S;. NUCLEAR'REGULATORYCOMMISSION,").
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SMALL BUSINESS INNOVATION RESEARCH PROGRAM I
PHASEII - FY 1985 PROJECT 5.UMMARY II N
FOR NRC USE ONLY
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Prograq Of fice ITli Proposal No.
Topic No.
TO BE COMPLETED BY PROPOSER Nim 2 cnd Address of Proposer Ybarrondo & Associates - Scientech Inc.
P. O. Box 1406
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Idaho Falls, ID 83403-1406.
N:me a'nd Title of Principal Investigator Dr. Larry Toarrondo, Presid ent Titic of Project Phasa II - Nuclear Plant Data Bank: Plant Input and Developnent
.o Technical Abstract (Limit to two h,undred words)
The Nuclear Regulatory Commission (NRCI has sponsored the development of theNuclear Plant D3tc Bank (NPDB) for several years at Technology Development of California INC. was awarded a contract (TDC). SCIENTECH, for Phase I of a Small Business Innovative Rercarch (SBIR
, t$ey;1uate=an6developatostheaewtuntypr ssible*~~a'RESAR-3S generic plank d'escr'iptiG.'~^In~ ^gr.
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h1 cbjectives of Phase II will be to:
inta the. NPDB; (2) develop the blank forms required for a B&W lower lo
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will ba accomplished by dividing the effort into three technical task
- v;r a 24 months time period from the award of the Phase II contract..
inticipated Results/ Potential,, Comme,rcial Applicatbns of the Research Th) reruits of tbe proposed Phase II program will be to provide NRC with an acc' urate"and documente c:n rio RESAR-3S plant description available in the NPDB, a B&W lower loop plant minimum data set de2cription that w.'11 be available,for later NRC use, a PC program which will make NPDB data set entriga user friendy an," determine the feasibility, provide a demonstration, and(develop an!
aut: mated input deck conver ' ion code if.warrented. To accomplish the first two ' objectives, scvtr21 visits to Westinghouse and B&W will be taken to obtain basic plant information and these will provide SCID7PECH with opp'ortunities to discuss the possibility of Phase'III support with thr2 crganizations. If URC priorities are such that another' plant type is needed (i.e.,a Combu; tion Engineering or !!cstinghouse plant), then the possibilit l
acn modste these needs in Phase III.
y and ficxibility exists to l
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