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in subjects: "Pnc"

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Criticality experiments with mixed oxide fuel pin arrays in plutonium-uranium nitrate solution

A series of critical experiments was completed with mixed plutonium-uranium solutions having a Pu/(Pu + U) ratio of approximately 0.22 in a boiler tube-type lattice assembly. These experiments were conducted as part of the Criticality Data Development Program between the United States Department of Energy (USDOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. A complete description of the experiments and data are included in this report. The experiments were perf… more

Date: August 1, 1988

Creator: Lloyd, R.C. (Pacific Northwest Lab., Richland, WA (United States)) & Smolen, G.R. (Oak Ridge National Lab., TN (United States))

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Reliability of fast reactor mixed-oxide fuel during operational transients

Results are presented from the cooperative DOE and PNC Phase 1 and 2 operational transient testing programs conducted in the EBR-2 reactor. The program includes second (D9 and PNC 316 cladding) and third (FSM, AST and ODS cladding) generation mixed-oxide fuel pins. The irradiation tests include duty cycle operation and extended overpower tests. the results demonstrate the capability of second generation fuel pins to survive a wide range of duty cycle and extended overpower events. 15 refs., 9 f… more

Date: July 1, 1991

Creator: Boltax, A.; Neimark, L.A.; Tsai, Hanchung (Argonne National Lab., IL (United States)); Katsuragawa, M. & Shikakura, S. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Performance of fast reactor mixed-oxide fuels pins during extended overpower transients

The Operational Reliability Testing (ORT) program, a collaborative effort between the US Department of Energy and the Power Reactor and Nuclear Fuel Development Corp. (PNC) of Japan, was initiated in 1982 to investigate the behavior of mixed-oxide fuel pin under various slow-ramp transient and duty-cycle conditions. In the first phase of the program, a series of four extended overpower transient tests, with severity sufficient to challenge the pin cladding integrity, was conducted. The objectiv… more

Date: February 1, 1991

Creator: Tsai, H.; Neimark, L.A. (Argonne National Lab., IL (USA)); Asaga, T. & Shikakura, S. (Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Development of fast breeder reactor fuel reprocessing technology at the Power Reactor and Nuclear Fuel Development Corporation

For the past two decades, a broad range of research development (R D) programs to establish fast breeder reactor (FBR) system and its associated fuel cycle technology have been pursued by the Power Reactor and Nuclear Fuel Development Corporation (PNC). Developmental activities for FBR fuel reprocessing technology have been primarily conducted at PNC Tokai Works where many important R D facilities for nuclear fuel cycle are located. These include cold and uranium tests for process equipment dev… more

Date: January 1, 1991

Creator: Kawata, T.; Takeda, H.; Togashi, A.; Hayashi, S. (Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works) & Stradley, J.G. (Oak Ridge National Lab., TN (USA))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Activities of the PNC Nuclear Safety Working Group

The Nuclear Safety Working Group of the Pacific Nuclear Council promotes nuclear safety cooperation among its members. Status of safety research, emergency planning, development of lists of technical experts, severe accident prevention and mitigation have been the topics of discussion in the NSWG. This paper reviews and compares the severe accident prevention and mitigation program activities in some of the areas of the Pacific Basin region based on papers presented at a special session organiz… more

Date: January 1, 1991

Creator: Kato, W.Y.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Experiments and analysis for an axially heterogeneous LMR assembly at ZPPR

Experiments in ZPPR-17 provided physics data for a full-scale (700 MWe) axially heterogeneous LMR. Measurements and analysis are reported for control rod worths, reaction rate distributions, gamma dose distribution, sodium void worths and criticality. Agreement between measurement and calculation are generally satisfactory, but the axial heterogeneity did introduce analytical complications. Some calculational methods gave less good agreement with measurements than in previous homogeneous or rad… more

Date: January 1, 1988

Creator: Collins, P.J. & Brumbach, S. B.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Systems work for Plutonium Fuel Production Facility (PFPF) near-real-time accounting

A joint effort by the Los Alamos National Laboratory and the Power Reactor and Nuclear Fuel Development Corporation of Japan examines materials accounting for the Plutonium Fuel Production Facility. A unique feature of the systems work is a sophisticated data generator. This software follows individual items throughout the process, creating detailed data files for variance propagation. The data generator deals with user-specified process operations and handles related accounting problems, such … more

Date: January 1, 1990

Creator: Picard, R. R.; Hafer, J. F.; Pillay, K. K. S. (Los Alamos National Lab., NM (USA)); Takahashi, S.; Ohtani, T.; Eguchi, K. et al.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

(Centralized reliability data organization for liquid metal reactor components)

The Centralized Reliability Data Organization is a data bank and data analysis center, focusing on reliability, availability, and maintainability (RAM) data for components (e.g., valves, pumps, etc.) operating in liquid metal reactors and test facilities. PNC staff are using the CREDO data base as a resource for their development of a probabilistic safety assessment (PSA) for the MONJU fast breeder reactor now under construction. The meeting was held to discuss: (a) progress in FY 1989, (b) res… more

Date: February 7, 1991

Creator: Smith, M.S. & Manneschmidt, J.F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Current US Activities and Directions in Shielding Technology for Liquid-Metal-Cooled Reactors

The US shielding development program for liquid-metal-cooled reactors is currently focused on optimization of the shield design for the Advanced Liquid-Metal-Cooled Reactor reference concept and the performance of a series of integral experiments for the verification of shield design methods. The experimental program, co-sponsored by Japan's Power Reactor and Nuclear Fuel Development Corporation, will extend the previous base of integral data, especially for systems employing boron carbide shie… more

Date: January 1, 1990

Creator: Ingersoll, D. T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Consolidated fuel reprocessing program: Criticality experiments with fast test reactor fuel pins in an organic moderator

The results obtained in a series of criticality experiments performed as part of a joint program on criticality data development between the United States Department of Energy and the Power Reactor and Nuclear Fuel Development Corporation of Japan are presented in this report along with a complete description of the experiments. The experiments involved lattices of Fast Test Reactor (FTR) fuel pins in an organic moderator mixture similar to that used in the solvent extraction stage of fuel repr… more

Date: December 1, 1986

Creator: Bierman, S. R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Behavior of mixed-oxide fuel elements during the TOPI-1E transient overpower test

A slow-ramp, extended overpower transient test was conducted on a group of nineteen preirradiated mixed-oxide fuel elements in EBR-II. During the transient two of the test elements with high-density fuel and tempered martensitic cladding (PNC-FMS) breached at an overpower of {approx}75%. Fuel elements with austenitic claddings (D9, PNC316, and PNC150), many with aggressive design features and high burnups, survived the overpower transient and incurred little or no cladding strain. Fuel elements… more

Date: December 1, 1993

Creator: Tsai, H.; Neimark, L. A.; Yamamoto, K.; Hirai, K. & Shikakura, S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Criticality experiments with mixed plutonium and uranium nitrate solution at a plutonium fraction of 0.5 in slab and cylindrical geometry

A series of critical experiments was completed with mixed plutonium-uranium solutions having Pu/(Pu + U) ratios of approximately 0.5. These experiments were a part of the Criticality Data Development Program between the United States Department of Energy (USDOE), and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. A complete description of, and data from, the experiments are included in this report. The experiments were performed with mixed plutonium-uranium solutions… more

Date: December 1, 1986

Creator: Lloyd, R. C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Validation of the generic TRUEX model using data from TRUEX demonstrations with actual high-level waste

The Generic TRUEX Model (GTM) was used to simulate three different countercurrent flowsheet tests performed using mixer-settlers that had been carried out prior to 1993 in the Chemical Processing Facility, Tokai-works, of the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. The feed for the PNC runs was the highly active raffinate from reprocessing of spent fuel from fast breeder reactors. The PNC demonstration runs were planned without using the GTM. Results predicted by … more

Date: August 1, 1995

Creator: Regalbuto, M.C.; Aase, S. & Vandegrift, G.F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

JASPER: A joint US-Japan program of experimental shielding research

A cooperative shielding research program between the US Department of Energy and Japan's Power Reactor and Nuclear Fuel Development Corporation has been initiated. The program includes six specific shielding integral experiments to be performed at the Oak Ridge National Laboratory Tower Shielding Facility and analyzed by both US and Japanese participants. Planned experiments include studies of (1) attenuation in radial shield mockups, (2) neutron streaming in a fission gas plenum, (3) shield ef… more

Date: January 1, 1987

Creator: Ingersoll, D.T. & Ohtani, N.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Activities of the PNC Nuclear Safety Working Group

Date: December 31, 1991

Creator: Kato, W. Y.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

ZPPR progress report: November 1987-January 1988

This report details activities for the time period of November, 1987 through January, 1988. Further results are presented from the axially heterogeneous assembly ZPPR-17, a part of the JUPITER-III program. The loading of the ZPPR-17C assembly, with 13 half-inserted control rods, is described along with operational measurements, calculation models, and measurements and prediction of criticality. From ZPPR-17A, calculated and measured results are given for reaction rates and measured results for … more

Date: February 15, 1988

Creator: Collins, P.J. & Brumbach, S.B.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Measurements for the JASPER Program fission gas plenum experiment

The Fission Gas Plenum Experiment was conducted at the Oak Ridge National Laboratory Tower Shielding Facility during FY 1987 to: provide data for verification of the assumptions and calculational methods used to determine the neutron leakage from the plenum, and provide an uncertainty evaluation associated with the calculations. The Tower Shielding Reactor source was modified to represent the neutron spectrum leaving a typical liquid-metal-cooled reactor core along its axis. The experimental co… more

Date: June 1, 1987

Creator: Muckenthaler, F.J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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ZPPR progress report: April 1987-July 1987

This report describes the progress in the Jupiter-III program during the time period of April through July, 1987.

Date: August 24, 1987

Creator: Collins, P.J. & Brumbach, S.B.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

ZPPR progress report: August 1987-October 1987

This progress report details activities during the time period of August through October, 1987. Results are presented from the axially heterogeneous assembly ZPPR-17, a part of the Jupiter-III program. The loading of the ZPPR-17B assembly, with 25 control rod positions, is described along with operational measurements, calculation models, measurements and predictions of criticality and measured axial worth profiles for B[sub 4]C. From ZPPR-17A, calculated and measured results are given for bank… more

Date: November 16, 1987

Creator: Brumbach, S.B. & Collins, P.J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Status of JUPITER Program

To obtain the data necessary for evaluating the nuclear design method of a large-scale fast breeder reactor, criticality tests with a large- scale homogeneous reactor were conducted as part of a joint research program by Japan and the U.S. Analyses of the tests are underway in both countries. The purpose of this paper is to describe the status of this project.

Date: March 10, 1981

Creator: Inoue, T.; Shirakata, K.; Kinjo, K.; Ikegami, T. & Yamamoto, M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Cooperative nonproliferation activities

Sandia National Laboratories (SNL) under DOE sponsorship is engaged in nuclear nonproliferation activities with the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. From 1995 to the present SNL and PNC have been participating in a cooperative project to implement and assess the use of remote monitoring to achieve nuclear nonproliferation objectives. Implementation of remote monitoring at the PNC Joyo facility took place during 1996 and continues to date. An International F… more

Date: August 1, 1997

Creator: Ystesund, K.; Furaus, J. & Lucero, R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Reports of Jupiter II: Measurements and analysis

This report provides the reaction rate measurements and analyses and the basic data for reaction rate measurements for ZPPR-13C in: The high [sup 240]Pu zone of ZPPR-13C; The high-heavy-metal-volume- fraction zone;The pin zone; The [sup 235]U fuel zone; and the enriched uranium zone. In-cell reaction rate measurements and cell factors for the zone studies in ZPPR Assembly 13C are provided.

Date: December 31, 1986

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

JASPER [Japanese-American Shielding Program of Experimental Research], USDOE/PNC shielding research program: Analysis of the JASPER fission gas plenum experiment

The results of the analysis of the Fission Gas Plenum Experiment are presented. This experiment is the second in a series of several experiments comprising a joint US DOE-Japan PNC Shielding Research Program (JASPER). The four Fission Gas Plenum Experiment configurations, designed for the measurement of neutron streaming through the fission gas plenum region, were analyzed using Monte Carlo and two-dimensional discrete ordinated methods. Calculated results compared well with measured results in… more

Date: May 1, 1990

Creator: Slater, C. O.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

ANL analysis of ZPPR-13A

The ZPPR-13 experiments provide basic physics data for radial heterogeneous LMFBR cores of approximately 700MWe size. Assemblies ZPPR-13A, ZPPR-13B and ZPPR-13C comprised the JUPITER-II cooperative program between the U.S. Department of Energy (US DOE) and PNC of Japan. The measurements were made between August 1982 and April 1984. The core designs and the measurements were planned jointly by the two parties with substantial input from U.S. industrial interests to ensure coverage of the design … more

Date: August 9, 1984

Creator: Collins, P. J. & Brumbach, S. B.

Item Type: Report

Partner: UNT Libraries Government Documents Department