ML20235N277
| ML20235N277 | |
| Person / Time | |
|---|---|
| Issue date: | 10/10/1975 |
| From: | Norberg J NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | Fraley R, Hanauer S NRC, Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML20235M427 | List: |
| References | |
| FOIA-87-40 NUDOCS 8707200013 | |
| Download: ML20235N277 (7) | |
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/ October 10, 1975 REG LATORY COMMiO RECEIVED S. Hanauer, TA " I3 RL/TR AD's and BC's RES/AD's and BC's O S.cen j, .
IE/AD's and BC's ADvisegy c , ajfjMMg j
/AD's and BC's "EACICRS4ESJARDS !
./. Fraley, ACRS (21) l F00 ,Q SAFETY RESEARCH REPORTS Attached is a listing of foreign safety research reports recently )
received by RES. Erief sumaries of these reports have been in-cluded where translations are available.
Please make note that some of these reports are " proprietary" or
" restricted" information and must be treated accordingly. In this regard, the Japanese are using the following definitions:
" Proprietary Informatic,n - Not for External Use
i Being of proprietary nature, the report should not be made j i open to a third party including the U.S. Patent Office, and i no usage is allowed to violate it. !
}
" Restricted" - Being prepared for those who are directly i involved in the study, the report is not open to the public.
Should you have further interest on any of these reports, please ]
contact J.A. Norberg of the Research Coordination Office, RES j (443-6953). ,., l hM..>. O. hahr Ja$esA.Norberg, Acting stant Director for Research Coordination j Office of Nuclear Regulatory Research
Enclosure:
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B707200013 070713 PDR FDIA THOMAG-0740 PDR
- 1. IRS-F-25, "Bundesminister fur Forschung und Technologies," May 1975.
The BUNDESMINISTER FUR FORSCHUNG UND TECHNOLOGIES (BMPT) is promoting financial plans for reactor safety research.
Objective research should improve the safety of light water reactors and minimize the risk for the environment.
The FORSCHUNGSBETREUUNG at IRS (IRS-FB) as consultants to the BMFT provides information about the research planning. In addition, information is given about the projects SR loo (old number RSloo) and ATT 085 A (old number At T 85 a) sponsored by the BUNDESMINISTER DES INNERN (BMI).
Individual reports will be furnished and put into standard faca by the research contractors. Each report gives information about:
- the work accomplished
- the results produced
- the outlook extension of the work.
The initial report of a research project describes in addition the purpose of the work, In this volume for the first time reports of investigations of fast breeders (RS 139, 14o, 143) have been added to those ones concerning the light water reactor safety research.
l IRS - F - 25 is informing of the activities during the first I quarter of 1975 (January 1st - March 31st 1975) .
Detailed technical information can be requested from IRS-PB 1
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- 2. Note Technique Sets 69, " Adaptation of the Sirene Code to the Study of Accidental Transmits of Pressurized Water Reactors,"
May 1975.
S w ary The SDEE code presently developed at Saclay aims at the study of transients resditing from accidental conditions. In its p sent version, SDEE allows for transients which do not lead to dissymetry in the primary loop behaviour or pressure variations such that steam "ccrapression" pheno-mena can no more be neglected.
New develognents are under way to obtain a better description of the expansion of the pressurizer water related to pressure variations in the primary system, the flow-rate in the case of pump shut-down, and the production of steam and the cooling of the primary system when great pressure changes occur in the secondary system.
Abstract A review of the different phenomena which occur in the BWR Mark III containment during a loss of coolant accident is presented. Different cases are studied : short term and long term, small breaks and large breaks. The presently known models are analysed. The principal points where improvements should be made for the realistic prediction of the phenomena are bn:;ught out.
Tney affect the pressure suppression system - especially the vent clearing and recovering, the pool swell, the vent flow - and the prediction of eventual oscillations and their effects.
- 4. Note Technique Sets 72, " Reliability of the Spray System of a PWR Containment. Ccmparison of Calculations Made by Various Codes on WASH-1400 Data " June 1975.
Sunsrer; The spray system avniinhility is evaluated by PATIEC-IE, IDCK ard FREP and h m .
The results obtained disagree with the WASH 1400 data by a factor 2 or even 3, if the dispersion is taken into account. This could be due to the fact 'that dependencies were neglected in WASH 1400 and that a part of the failure tree has not been allowed for.
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- 5. Note Technique Sets 75, " Availability of the Electrical Supply -
System of Emergency Sources of 900 MW PWR's," July 1975. i S'r mary This note ecmpletes a study made by CEA and EdF (see DSN Report 56) i l on the time-dependent probability of simultaneous loss of the electrical j supply system of emergency sources.. J The availability of the electrical supply systern in all possible corditions (2 avaiLsble external sources,1 available external Source...)
and the probability for repair after total loss of supply sources.
- 6. Rapport Sets 34, " Analysis of a Blowdown Experiment with the Dabbous Code," April 1975.
l- Summary This report presents the results cbtained by the DABBOUS code, Which deals with the hydraulics of the blowdown of a pressurized water tank, -
compared to the experiment made at AhBE, Foulness by the UK.A.E.A.
(Standard Problem N' 1). Besides, a brief parametric study is described, where the varying parameters are : the number of nodes, the friction pressure drop and the Moody railtiplier.
Agrement is satisfactory with results obtained with U.S. codes as concerns pressure and tatperature during the transient, although pressure oscillations are greater with IRBBOUS than with other codes.
- 7. Rapport Sets 35, " PREP and KITT - Note for the User " July 1975 l Sumary j This report gives a brief description of the PREP and KIIT codes for the user's sake. A comparison is made with the results obtaired frcan !
PATREC, and the best conditions in Which to use either code' are given.
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Sumary Allowing for the inportance of disequilibrium between phases, a "4 equations" model for the flow is proposed, to be included in the CLYSIEE ' code. This. code is used to evaluate primary system mptures -
from the standpoint of 1) mechanical stresses on NSS structures,
- 2) ECCS efficiency, 3) mechanical and themal solicitations of the containment.
The note gives the theoretical bases of the model and a first comparison with experimest.
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- 9. Note Technique SEMT 74/260, " Brutal Blowdown - Comparison of Results !
Given by Propagation Calculations (Vibraphone Code) and by an f Experiment." 1 Surmary Results given by the US experiment 'IEST 711 am cauW to results given by the 3-D code, VIBRAPHCRE. It was possible to deter.nine the pressum behaviour in a circuit during the first millisecorris of a blow-down. The agreement is satisfactory, although the pressure variation at the rupture level affects the results.
A more ccrnplete study of a simple circuit would be useful to detemine in particular the exact shape of the pressure variation at the rupture level.
- 10. Rapport DSN 71, " Reliability and Availability of a System with Active r out of m Repairable Redundancies - General Solution - FIDIAS Code,"
June 1975. !
Sumary l I
The problem of active r out of m repairable redundancies is frequently !
encountered by the a liability engineer. l Various methods can be used to solve'it. The purpose of this report !
is to describe an adequate methed, based on the Markov process and using 1 operational and matrix calculations. A IVRI'RAN IV code, FIDIAS : Reliability and Availability by an analytical method of redundant r out of m systems, has been developed te evaluate the reliability, the MI'BF, the ' availability ard the mean availability of such systems. ,
1 A sub-routine is used to give the corresponding curves for the graphie :
solution of the problem. j
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. IRS-F-24. "Forschungsberichte." Research Reports, State: Enc of 1974, i dated May 1975. {
- r._ : compilation of researen repcrts is the thira one Oc ce
,ut isnec cnce a year in the frame Of a comprehensive reporting a; ;n :ne current investigations witn regard to reactor safety.
!..sre are three types of reports:
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. e RESEARCH REPORTS
-.~.- .ESEARCH REPORTS 3.ri RESEARCH REPORTE
~. - r.S-RESEARCH REPORTS and the LRA-RESEARCH REPORTS give infor-i
- .E _ cr cr. the investigations sponsored by the Bundesminister fur
.:rocnang und Tecnnologie (EMPT' and partly by the Bundesminister ee. Innern (BMI h3R 100, At T 55 a]) as individual reactor safety e earch projects. The GFK-RESEARCH REPORTS inform aoout theoretical Er.d experimental investigations on reactor safety conducted by th.
3scellschaft fur Kernforschung mbH (GFK), Karlsruhe.
Tr.e Laboratorium fur Reaktorregelung und Anlagensicherung (LRA), )1 l
.2nchen-Garching, executes nine individual research projects compre-ner.ded under the number At O 85 a. The work carried out oy the GFK l 1
.s included in the main project " Nuclear Safety" (PNS). !
. .;s t of the single reports are organized as follows:
.. General aim
- 2. Particular objectives t
3 Experimental facilities and program
. Project status
... Progress to date
.2. Essential results 5 Next steps
- d. Relation with other projects Reference documents l _ ___ ______ _ _ _ -____
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- 12. JAERI-M 6240, ROSA-II Test Data Report 1 (Run 202, 203, 303, 304, 306).
The present report summarizes a part of the results of the ROSA-II Test, which is a simulated test of Loss-of-Coolant i Accident (LOCA) in a Light Water Reactor (LWR). The report gives experimental conditions, experimental data and inter-pretations'to phenomena observed in each' test runs (Run 202, H 203, 303, 304 and 306).
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- 13. JAERI-M 6241 ROSA-II Test Data Report 2 (Run 307, 308,-309).
The present report summarizes a part of the results of the ROSA-II Test, which is a simulated test of Loss-of-Coolant )
Accident (LOCA) in a Light Water Reactor (LWR) . The report gives experimental conditions, experimental data and inter-pretations to phenomena observed in each test runs (Run 307, 308 and 309).
- 14. JAERI-Memo 6212, Summary of Control Equipments and Instrumentation for the Reflooding Test RIG, August 1975, Restricted. No translated summary provided.
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- 15. JAERI-Memo 6204, Study on Film Boiling Heat Transfer During Reflood j Process (on the Effects of Subcooling on Film Boiling Heat Transfer),
l August 1975, Restricted. No translated summary provided.
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