alea-institute/kl3m-data-sample-004-shuffled huggingface dataset:
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Analysis with TRACE Code of Rosa Test 1.2: Small LOCA in the Hot-Leg with HPI and Accumulator Actuation (NUREG/IA-0420)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0420 (PDF - 5.89 MB)

## Publication Information

**Manuscript Completed:** December 2012**Date Published:** April 2013

**Prepared by:** J.L. Munoz-Cobo, A. Romero, S. Chiva

Instituto de Ingeniería Energética Universitat Politècnica de Valencia Camí de Vera s/n 46022 Valencia, Spain

A. Calvo, NRC Project Manager

**Prepared as part of:** The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

**Published by:** Division of Systems Analysis Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 

Availability Notice

## Abstract

The goal of this report is to explain the main results obtained in the simulations performed with the consolidated code TRACE for the OCDE stratification test ROSA 1.2. The transient was produced by a small break in the hot leg of the loop B of the LSTF facility in Japan. In the experiment, the small break was simulated by a small diameter fissure located at the bottom of the hot-leg. The goal of this report is to analyze the capabilities of the TRACE code to cope with cases where thermal stratifications in the cold and hot legs take place. For this transient is very important the ability of TRACE to predict correctly the fluid regime in the hot leg. At the beginning of the transient the fluid discharged through the bottom of the hot leg is at liquid state and the mass flow rate discharged through the break is very high, and as a consequence the pressure drop very fast during the first seconds of the transient until the beginning of the HPI injection. This behaviour is predicted very well by TRACE code. Later, the flow at the hot leg becomes two-phase with low void fraction, and the mass flow rate discharged through the break is still high because the TRACE off-take model considers the fact that at the bottom of the hot leg we have liquid. Finally, the flow in the hot leg becomes biphasic with high void fraction and we discharge mainly steam through the break. In this test, the contraction of the fluid vein during the steam discharge has an important influence on the depressurization rate during the steam regime. The injection of the HPI in the cold leg produces a significant thermal stratification in the cold leg that attains the value of 100 oC, but the TRACE code predicts well the average temperature in the cold leg.

Page Last Reviewed/Updated Tuesday, March 09, 2021
[Federal Register Volume 80, Number 18 (Wednesday, January 28, 2015)]
[Notices]
[Pages 4592-4593]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2015-01587]


-----------------------------------------------------------------------

DEPARTMENT OF JUSTICE

Drug Enforcement Administration

[Docket No. DEA-392]


Importer of Controlled Substances Application: Cambrex Charles 
City

ACTION: Notice of application.

-----------------------------------------------------------------------

DATES: Registered bulk manufacturers of the affected basic classes, and 
applicants therefore, may file written comments on or objections to the 
issuance of the proposed registration in accordance with 21 CFR 
1301.34(a) on or before February 27, 2015. Such persons may also file a 
written request for a hearing on the application pursuant to 21 CFR 
1301.43 on or before February 27, 2015.

ADDRESSES: Written comments should be sent to: Drug Enforcement 
Administration, Attention: DEA Federal Register Representative/ODW, 
8701 Morrissette Drive, Springfield, Virginia 22152. Comments and 
requests for hearings on applications to import narcotic raw materials 
are not appropriate. 72 FR 3417 (January 25, 2007).

SUPPLEMENTARY INFORMATION:  The Attorney General has delegated his 
authority under the Controlled Substances Act to the Administrator of 
the Drug Enforcement Administration (DEA), 28 CFR 0.100(b). Authority 
to exercise all necessary functions with respect to the promulgation 
and implementation of 21 CFR part 1301, incident to the registration of 
manufacturers, distributors, dispensers, importers, and exporters of 
controlled substances (other than final orders in connection with 
suspension, denial, or revocation of registration) has been redelegated 
to the Deputy Assistant Administrator of the DEA Office of Diversion 
Control (``Deputy Assistant Administrator'') pursuant to section 7 of 
28 CFR part 0, appendix to subpart R.
    In accordance with 21 CFR 1301.34(a), this is notice that on May 
15, 2014, Cambrex Charles City, 1205 11th Street, Charles City, Iowa 
50616-3466, applied to be registered as an importer of the following 
basic classes of controlled substances:

[[Page 4593]]



------------------------------------------------------------------------
            Controlled substance                       Schedule
------------------------------------------------------------------------
4-Anilino-N-phenethyl-4-piperidine (8333)..  II
Phenylacetone (8501).......................  II
Cocaine (9041).............................  II
Opium, raw (9600)..........................  II
Poppy Straw Concentrate (9670).............  II
------------------------------------------------------------------------

    The company plans to import the listed controlled substances for 
internal use, and to manufacture bulk intermediates for sale to its 
customers.

    Dated: January 21, 2015.
Joseph T. Rannazzisi,
Deputy Assistant Administrator.
[FR Doc. 2015-01587 Filed 1-27-15; 8:45 am]
BILLING CODE P
No. 85-6549.

#### Evans *v.*United States.

C. A. 4th Cir. Motion of petitioner for leave to proceed *in forma pauperis*and certiorari granted. Judgment vacated and case remanded for further consideration in light of *Griffith*v. *Kentucky, ante,*p. 314.
FOR PUBLICATION

UNITED STATES COURT OF APPEALS

FOR THE NINTH CIRCUIT

DAVID TOURGEMAN,

Plaintiff-Appellant,

v.

COLLINS FINANCIAL SERVICES, INC.,

DBA Precision Recovery Analytics,

Inc., a Texas corporation; NELSON &

KENNARD, a partnership; PARAGON

WAY, INC.; COLLINS FINANCIAL

SERVICES USA, INC.,

Defendants-Appellees,

and

DELL FINANCIAL SERVICES, LP,

Defendant.

No. 12-56783

D.C. No.

3:08-cv-01392-

CAB-NLS

ORDER

Filed October 31, 2014

Before: Jerome Farris and Andrew D. Hurwitz, Circuit

Judges, and Paul L. Friedman, District Judge.*

* The Honorable Paul L. Friedman, District Judge, U.S. District Court

for the District of Columbia, sitting by designation.
2 TOURGEMAN V. COLLINS FINANCIAL SERVS.

ORDER

The opinion filed June 25, 2014 is AMENDED as

follows:

1. At page 4 of the slip opinion, the following sentence is

deleted:

We now reverse and hold that judgment

should be entered for Tourgeman.

and replaced with:

We now reverse.

2. At page 24 of the slip opinion, the following sentence is

deleted:

Accordingly, the appellant is entitled to

judgment on his claims against Paragon Way

under subsections 1692e(2) and e(10).

3. At page 30 of the slip opinion, the following sentence is

deleted:

These conclusions are sufficient to warrant

both reversal of the judgment granted to

Nelson & Kennard and entry of judgment in

favor of Tourgeman.

and replaced with:
TOURGEMAN V. COLLINS FINANCIAL SERVS. 3

These conclusions are sufficient to warrant

reversal of the judgment granted to Nelson &

Kennard.

4. At pages 30–31 of the slip opinion, the following

sentence is deleted:

For the foregoing reasons, we conclude that

the judgment of the district court granting

judgment to Collins, Paragon Way, and

Nelson & Kennard must be reversed, and that

judgment should instead be entered for

Tourgeman against Paragon Way and Nelson

& Kennard.

and replaced with:

For the foregoing reasons, we conclude that

the judgment of the district court granting

judgment to Collins, Paragon Way, and

Nelson & Kennard must be reversed.

5. At page 31 of the slip opinion, the following sentence is

deleted:

We express no view regarding whether

Tourgeman is entitled to judgment against

Collins itself, as Tourgeman’s claims against

that entity were based on a theory of vicarious

liability that was neither decided by the

district court nor briefed on this appeal.

With this amendment, JudgesHurwitz and Friedman have

voted to deny the petition for rehearing. Judge Farris did not
4 TOURGEMAN V. COLLINS FINANCIAL SERVS.

vote. Judge Hurwitz voted to deny the petition for rehearing

en banc, Judge Friedman so recommends, and Judge Farris

made no recommendation.

The full court has been advised of the petition for

rehearing en banc and no active judge has requested a vote on

whether to rehear the matter en banc. Fed. R. App. P. 35.

The petition for rehearing and petition for rehearing en

banc, filed August 13, 2014, are DENIED. No further

petition for rehearing and/or petition for rehearing en banc

may be filed.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Heat Transfer Processes During Intermediate and Large Break Loss-of-Coolant Accidents (LOCAs) (NUREG/IA-0002)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0002 (PDF - 5.55 MB)

## Publication Information

**Date Published:**September 1986

**Prepared by:** I. Vojtek

Reactor Safety Corporation Gesellschaft fuer Reaktorsicherheit Porschungsgelaende, 8046 Garching, The Federal Republic of Germany

Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Availability Notice

## Abstract

The general purpose of this project was the- investigation of the heat transfer regimes during the high pressure portion of blowdown. The main attention has been focussed on the evaluation of those phenomena which are most important in reactor safety, such as maximum and minimum critical heat flux and forced convection film boiling heat transfer. The experimental results of the 25-rad bundle blowdown heat transfer tests, which were performed at the KWU heat transfer test facility in Karistein, were used as a database for the verification of different correlations which are used or were developed for the analysis of reactor safety problems. The computer code BRUDI-VA was used for the calculation of local values of Important thermohydraulic parameters in the bundle.

In particular the following correlations have been evaluated in this study: 

Maximum critical heat flux:
        - W-3 correlation
        - B-W-2 correlation
        - Macbeth correlation
        - Zuber-GriffIth correlation
        - Biasi correlation
        - CISE correlation
        - Slifer-GE correlation
        - Smolin correlation
        - Pong correlation
        - Thorgerson correlation
        - Monde-Katto correlation

Minimum critical heat flux and minimum film boiling temperature:
        - Berenson modification of the Zuber correlation
        - Berenson correlation
        - Henry correlation
        - Iloeje correlation

Heat transfer coefficients in flow film boiling:
        - modified Dougal l-Rohsenow correlation
        - Groeneveld-5.7 correlation
        - Condie-Bengston-IV correlation
        - Groeneveld-Delorme correlation
        - Chen-Ozkaynak-Sundaram correlation.

The evaluation of correlations for the prediction of critical heat flux, film boiling heat transfer coefficients and minimum film boiling temperature showed that none of the correlations should be used over the entire range of test parameters investigated.

Using results of this investigations a new equilibrium correlation for the calculation of forced film boiling heat transfer coefficients has been developed. This correlation is shown to agree well. with the experimental data over the following range of testparameter: Mass flow rate 300 to 1400 kg/m2.s, pressure 2 to 12 MPa and quality 0.3 to 1.0.

Page Last Reviewed/Updated Tuesday, March 09, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Contractors

# Guidance for Performing Probabilistic Seismic Hazard Analysis for a Nuclear Plant Site: Example Application to the Southeastern United States (NUREG/CR-6607,UCRL-ID-133494)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/CR-6607            - Cover – Chapter 4 (PDF - 8.05 MB)
          - Appendex A – E (PDF - 5.66 MB)
          - Appendix F – End (PDF - 3.53 MB) 

## Publication Information

**Manuscript Completed:**September 2002**Date Published:**October 2002

**Prepared by:** J.B. Savy, W. Foxall, N. Abrahamson, D. Bernreuter

 Lawrence Livermore National Laboratory Livermore, California 94550

E. Zurflueh and S. Pullani, NRC Project Managers

**Prepared for:** Division of Engineering Technology Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

NRC Job Codes W6496 and Y6245 

Availability Notice

## Abstract

From 1981 to 1989, Lawrence Livermore National Laboratory (LLNL) developed a Probabilistic Seismic Hazard Analysis (PSHA) method for the eastern United States (NUREG/CR-5250), followed in 1993 by improvements in the handling of the uncertainties (NUREG-1488). Differences between these results and those of a utilities-sponsored study (Electric Power Research Institute, 1989) led to the formation of the Senior Seismic Hazard Analysis Committee (SSHAC) to identify the sources of differences and give guidance on how to perform a state-of the-art PSHA (NUREG/CR-6372, 1997).

The present study is a trial implementation of the SSHAC guidance. As part of the project, additional guidance was developed and proposed for performing a PSHA. The trial implementation project tested the issue of development of the seismic zonation and seismicity models for two sites: Watts Bar and Vogtle. It was found that the uncertainty generated by disagreements among experts could be considerably reduced through interaction and discussion of the data, and by concentrating on the elements common to all experts' interpretations. The present study includes analyses of the differences between its results and the NUREG-1488 results (Appendix G).

Page Last Reviewed/Updated Thursday, March 25, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Prepared by NRC Staff

# Offsite Dose Calculation Manual Guidance:Standard Radiological Effluent Controls for Boiling Water Reactors, Generic Letter 89-01, Supplement No. 1 (NUREG-1302)

On this page:
        - Publication Information 
        - Abstract

Download complete document
        - NUREG-1302 (PDF – 7.39 MB)

## Publication Information

**Date Published:** April 1991

**Prepared by:** W. W. Meinke, T. H. Essig

Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Availability Notice

## Abstract

This report contains guidance which may be voluntarily used by licensees who choose to implement the provision of Generic Letter 89-01, which allows Radiological Effluent Technical Specifications (RETS) to be removed from the main body of the Technical Specifications and placed in the Offsite Dose Calculation Manual (ODCM). Guidance is provided for Standard Effluent Controls definitions, Controls for effluent monitoring instrumentation, Controls for effluent releases, Controls for radiological environmental monitoring, and the basis for Controls.

 Guidance on the formulation of RETS has been available in draft form (NUREG-0472 and -0473) for a number of years; the current effort simply recasts those RETS into Standard Radiological Effluent Controls for application to the ODCM. Also included for completeness are: (1) radiological environmental monitoring program guidance previously which had been available as a Branch Technical Position (Rev. 1, November 1979); (2) existing ODCM guidance; and (3) a reproduction of Generic Letter 89-01.

Page Last Reviewed/Updated Tuesday, March 09, 2021
DENY; and Opinion Filed July 26, 2013.

S

In The

Court of Appeals

Fifth District of Texas at Dallas

No. 05-13-00844-CV

IN RE CALVIN ERVIN MCNAC, Relator

On Appeal from the 283rd Judicial District Court

Dallas County, Texas

Trial Court Cause No. F03-71678-T

MEMORANDUM OPINION

Before Justices Bridges, Francis, and Lewis 

Opinion by Justice Lewis

Relator contends the trial court violated a ministerial duty by not ruling on his motion for 

access to the trial record. The facts and issues are well known to the parties, so we need not 

recount them herein. Based on the record before us, we conclude relator has not shown he is 

entitled to the relief requested. See TEX. R. APP. P. 52.8(a); Simon v. Levario, 306 S.W.3d 318, 

320-21 (Tex. Crim. App. 2009) (orig. proceeding). Accordingly, we DENY relator=s petition for 

writ of mandamus.

130844F.P05

/David Lewis/

DAVID LEWIS

JUSTICE
#### The People of the State of New York, Respondent, v Oakley T. Griffis, Appellant.

[632 NYS2d 731]

Judgment unanimously affirmed. Memorandum: County Court properly denied defendant’s motion to suppress the shotgun found in plain view by the police during a protective sweep of the motel *869room from which defendant had emerged *(see, People v Smith,*179 AD2d 597, *lv denied*79 NY2d 1008; *People v Febus,*157 AD2d 380, *appeal dismissed*77 NY2d 835). Because the seizure of the shotgun was proper, defendant’s statements made subsequent to the seizure were not tainted by any illegality. (Appeal from Judgment of Ontario County Court, Harvey, J.— Rape, 1st Degree.) Present Pine, J. P., Lawton, Wesley, Callahan and Doerr, JJ.
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsBrochures Prepared by NRC Staff

# Effective Risk Communication: The NuclearRegulatory Commission's Guidelines for Internal Risk Communication (NUREG/BR-0318)

Page Last Reviewed/Updated Wednesday, March 24, 2021
HomeNRC LibraryDocument CollectionsNUREG-Series PublicationsPublications Resulting from International Agreements

# Simulation of ROSA-2 Test-2 Experiment: Application to Nuclear Power Plant (NUREG/IA-0511)

On this page:
        - Publication Information
        - Abstract

Download complete document
        - NUREG/IA-0511 (PDF – 1.85 MB)

## Publication Information

**Manuscript Completed:** April 2018**Date Published:** March 2019

**Prepared by:** S. Gallardo, A. Querol, M. Lorduy and G. Verdú

Universitat Politècnica de València Instituto Universitario de Seguridad Industrial, Radiofísica y Medioambiental Camí de Vera s/n 46022 Valencia, SPAIN

Kirk Tien, NRC Project Manager

Division of Systems Analysis Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

**Prepared as part of:** The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)

**Published by:** U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 

## Abstract

Availability Notice

The purpose of this work is to overview the results provided by a first approach to the simulation of an Intermediate Break Loss-Of-Coolant Accident (IBLOCA) in a 3-loop PWR Nuclear Power Plant (NPP) using the thermal-hydraulic code TRACE5 patch 2 and the Symbolic Nuclear Analysis Packages software (SNAP) version 2.1.2.

The IBLOCA transient applied to the standard PWR TRACE5 model is the Test 2 (IB-CL-03) handled at the Large Scale Test Facility (LSTF) in the frame of the OECD/NEA ROSA-2 Project. Test 2 simulates a 17% cold leg IBLOCA under the assumption of the single-failure of High Pressure Injection and Low Pressure Injection systems and total failure of the Auxiliary Feedwater.

The LSTF is a Full Height Full Pressure (FHFP) facility designed to simulate a 4-loop W-type PWR (Tsuruga unit II NPP). The volumetric scaling factor is 1/48. The four primary loops of the reference PWR are scaled in LSTF by two equal-volume loops. The core power used to simulate the decay power is 10 MW, corresponding to 14% of the 1/48 volumetrically scaled reference PWR rated power.

The simulation results are provided throughout several graphs, where the main system variables, such as pressures, pressure vessel liquid levels and temperatures are shown. These results represent a contribution to assess the predictability of computer codes such as TRACE5.

Page Last Reviewed/Updated Tuesday, March 09, 2021
### The Honorable De an Whipple, United States District Judge for 1 

### the Western District of Missouri.



# United States Court of Appeals

FOR THE EIGHTH CIRCUIT

___________ No. 96-1181

___________ Joseph H. Brown, Sr., * * Appellant, * * Appeal from the United States v. * District Court for the * Western District of Missouri. United States of America, * * [UNPUBLISHED] Appellee. *

___________ Submitted: April 30, 1997 Filed: May 3, 1997

___________ Before BOWMAN, WOLLMAN, and BEAM, Circuit Judges.

___________ PER CURIAM. Joseph H. Brown, Sr., app eals the district court’s denial of his 28 1 U.S.C. § 2255 motion. Upon a de novo review of the record, we ar e persuaded that the motion, files, and records of the case conclusively sho w Brown is not entitledto relief. See United States v. Duke , 50 F.3d 571, 576 (8th Cir.) (stand ard of review), cert. denied , 116 S. Ct. 224 (1995). Accordi ngly, we affirm for the reasons stated in the district court’ s opinion. See 8th Cir. R. 47B.

### -2- A true copy. Attest: CLERK, U. S. COURT OF APPEALS, EIGHTH CIRCUIT.
I 

115TH CONGRESS 

1ST SESSION H. R. 1768 

To provide that no additional Federal funds may be made available for 

National Heritage Areas, and for other purposes. 

IN THE HOUSE OF REPRESENTATIVES 

MARCH 28, 2017 

Mr. RUSSELL introduced the following bill; which was referred to the 

Committee on Natural Resources 

A BILL 

To provide that no additional Federal funds may be made 

available for National Heritage Areas, and for other purposes. 

1 Be it enacted by the Senate and House of Representa2 tives of the United States of America in Congress assembled, 

3 SECTION 1. SHORT TITLE. 

4 This Act may be cited as the ‘‘End NHA Earmarking 

5 Act’’. 

6 SEC. 2. NO ADDITIONAL FEDERAL FUNDS FOR NATIONAL 

7 HERITAGE AREAS. 

8 (a) PROHIBITION ON FUTURE FUNDING.—No Fed9 eral funds may be made available for the National HeritVerDate Sep 11 2014 02:58 Mar 31, 2017 Jkt 069200 PO 00000 Frm 00001 Fmt 6652 Sfmt 6201 E:\BILLS\H1768.IH H1768

lotter on DSK5VPTVN1PROD with BILLS
2 

•HR 1768 IH

1 age Partnership Program or for any National Heritage 

2 Area. 

3 (b) SAVINGS.—Subsection (a) shall not affect the 

4 availability of Federal funds made appropriated or other5 wise made available before the date of the enactment of 

6 this Act. 

Æ 


lotter on DSK5VPTVN1PROD with BILLS