The current Army Boiling-Water Reactor program is reviewed. Plant design, core analysis, reactor theory development, and health physics studies are discussed for the Portable Low-Power Plants (PL-1 and PL-2). Plans for installing a PL-2 plant in a snow tunnel at Byrd Station in Antarctica are described. (B.O.G.)

A frame-based technique, including physical frame, logical frame, and cognitive frame, was adopted to perform digital I and C failure events derivation and analysis for generic ABWR. The physical frame was structured with a modified PCTran-ABWR plant simulation code, which was extended and enhanced on the feedwater ...

An innovative reactor core concept applying spectral shift rods (SSRs) is proposed to improve the plant economy and the operability of the 1700 MWe ABWR-II reactor. The SSR is a new type of water rod, in which a water level is naturally developed during operation and changed according to the coolant flow rate through the channel. By taking advantage of the ...

An innovative reactor core concept applying spectral shift rods (SSRs) is proposed to improve the plant economy and the operability of the 1700-MW(electric) Advanced Boiling Water Reactor II (ABWR-II). The SSR is a new type of water rod in which a water level is naturally developed during operation and changed according to the coolant flow rate through the ...

The program includes the operation and test evaluation of the SL-1 (ALPR) and an associated design and development program with the objective of obtaining improved, portable, and modularized BWR plants in the low power range. Volume 1 discusses SL-1 plant operational experience, outlines major maintenance and modifications performed, presents plant test activities, including a major ...

In reactor development and evaluation, work is reported on mininzation of the control rod drive mechanism, evaluation of PL-2 core lifetime, response of PL-2 type reactor to steam demand transients, and evaluation of fuel assembly and control system. In plant development and evaluation, work is reported on site adaptation, refueling. modifications to the turbine ...

General Electric Company`s (GE`s) Advanced Boiling Water Reactor (ABWR) has been approved for operation in Japan, and the final design approval (FDA) by the U.S. Nuclear Regulatory Commission is scheduled for mid-1994. One possible utilization of the ABWR would be to operate with mixed oxide (MOX) fuel with the plutonium made available from the U.S. ...

Two advanced boiling water reactors (ABWRs) whose electric output power is 1356 MW have been commercially operated since 1996 and 1997 by the Tokyo Electric Power Company (TEPCO) in Japan. Features of an ABWR are reactor internal pumps (RIPs) placed in the lower plenum and downcomer, peripherally bottom-mounted on the reactor pressure vessel - which should ...

1000 MWe Advanced Boiling Water Reactor has only two main steam lines and six reactor internal pumps, whereas 1350 MWe ABWR has four main steam lines and ten reactor internal pumps. In order to confirm how the differences affect hydrodynamic conditions in the dome and lower plenum of the reactor pressure vessel, fluid analyses have been performed. The results indicate that ...

This paper discusses the safety design of the Toshiba Boiling Water Reactor (TOSBWR) which was created {approx}8 years ago. The design concept is intermediate between conventional boiling water reactors (BWRs) and the advanced BWR (ABWR). It utilizes internal pumps and fine motion control rod drive, but the emergency core cooling system (ECCS) ...

The development of conceptual designs for several reactor cores which meet the original requirements of the SL-1 Reactor is covered. The SL-1 type conceptual core design were developed in an attempt to select a satisfactory core material and configuration for application to the PL-1 and PL-2 Reactors. The primary basis for ...

This report summarizes the results from MELCOR calculations of severe accident sequences in the ABWR and presents comparisons with MAAP calculations for the same sequences. MELCOR was run for two low-pressure and three high-pressure sequences to identify the materials which enter containment and are available for release to the environment (source terms), to study the ...

In order to investigate the stability of a nuclear reactor core with an oxide mixture of uranium and plutonium (MOX) fuel installed, channel stability and regional stability tests were conducted with the SIRIUS-F facility. The SIRIUS-F facility was designed and constructed to provide a highly accurate simulation of thermal-hydraulic (channel) instabilities and coupled ...

This paper is focused on the preliminary analysis of results obtained on the first cores of the first phase of the BASALA (Boiling water reactor Advanced core physics Study Aimed at mox fuel Lattice) programme, aimed at studying the neutronic parameters in ABWR core in hot conditions, currently ...

It is possible to simplify the reactor internal pump power supply system in the ABWR without affecting the core flow supply when a trip of all RIPs event occurs by eliminating the motor-generator sets and increasing the rotating inertia of the RIPs. This inertia increase due to an additional flywheel, which leads to a gain in weight and length, requires a ...

In order to meet utility demands after successful completion of ABWR development, ABWR-II design provides more emphasis on beyond-DBA capability to achieve further enhancement of safety such as the practical exclusion of the probability of emergency evacuation/resettlement. Optimization of safety and economic aspects is also to be strongly pursued. The ...

The purpose of this paper is to provide the quantitative evaluation method with regard to the Digital Protection systems (DPSs) that were newly adopted in the ABWR plants and to show the results of level-1 PSA of the ABWR plants. (authors)

A data summary of the characteristics of the PL-1 and PL-2 plants is given. Revisions were made in the plant systems to improve performance; conserve materials, weight, and space: and to provide for simple operation. Data is included on the reactor, electrical system, environment, fuel elements. core geometry, control, main stream system, condensate system, feedwater ...

The Stationary Low Power Reactor No. 1 is a three Mw boiling water reactor designed to demonstrate the feasibility of a nuclear reactor to supply electrical power and space heat for remote sites. In addition to performance evaluation the facility provides training for military personnel. The reactor was operated for 1159 hr during the quarter for a total core burnup ...

A series of calculations were performed to analyze the response of General Electric Company's (GE) advanced boiling water reactor (ABWR) during an anticipated transient without scram (ATWS). This work investigated the early plant response with an assumed failure or manual inhibit of the high pressure core flooder (HPCF). Consequently, the reactor ...

The ABWR Design Verification Program is aimed at restoring confidence in the US licensing process by demonstrating its workability by obtaining USNRC preapproval of GE's ABWR Standard Plant. The purpose of this work is to achieve full NRC approval of the ABWR through the award of an NRC Staff final design approval (FDA) and ...

The reference design of a Portable Boiling Water Reactor Plant with a net electric output of up to 250 kw and a net space heat output of 400 kw is presented. The total reactor thernnal pewer is 3.6 Mw, and the design life of the core is 8 full power years. The principle objectives which have governed the reference design are: (1) the plant shall be air tnansportable ...

The Advanced Boiling Water Reactor-II (ABWR-II) is under development, based on the technologies and experiences of ABWR, to further improve the performance and economy. There are new systems and components developed or under development to incorporate into the primary system of ABWR-II. This paper introduces the primary system and ...

This report describes a plant model of the advanced BWR (ABWR) plant. The model has been jointly developed by CRIEPI and General Electric Company (GE). This model is designed for combining it with the CRIEPI power system dynamics analysis program and for ...

This paper describes an effort by Tokyo Electric Power Company (TEPCO) to shorten the construction time in a drastic manner for the Advanced Boiling Water Reactors (ABWR), thereby aiming at reducing construction costs. First an outline of the actual construction records for the five BWR Units and the two ABWR Units at the Kashiwazaki-Kariwa site is ...

In boiling water reactors (BWRs), traversing incore probes (TIPs) are used for the continuous measurement of the axial distribution of neutron flux in a reactor and the calibration of local power range monitors (LPRMs). One of candidates for a substitute for TIP is gamma thermometers (GTs). Some researches have been conducted so far for the verification of applying GT to BWR plants. In the ...

... PHYSICAL PROPERTIES, *BOUNDARY LAYER, *RADIOCHEMISTRY, *CORE SAMPLING, *SEDIMENTOLOGY, LABORATORY TESTS ...

Page 1. AD-753 834 PHYSICS IN PERSPECTIVE. YOLUME 111. P~ART A. THE CORE SUBFIELDS OF PHYSICS National Academy of Sciences ' ...

Technical papers presented at the ANS Topical Meeting on Advances in Reactor Physics and Core Thermal Hydraulics, September 22-24, 1982, at Kiamesha Lake, N.Y. are included in these Proceedings. Reactor physics, core thermal hydraulics, and the interactions between core ...

Contents: Elementary-particle physics; Nuclear physics; Atomic, electron, and molecular physics; Physics of condensed matter; Optics; Acoustics; Plasma physics and the physics of fluids; Appendix: physics survey-a charge to the survey panels.

The reference design of a Portable Boiling Water Reactor Plant with a net electric output of up to 1000 kw and a net space heat output of 400 kw is presented. The total reactor thermal power is 8.8 Mw and the design life of the core is three full power years. The principle objectives which governed the reference design are: (l) The plant should be air transportable ...

New results derived for application to the earth's outer core using the modern theory of liquids and

Reactor physics, core thermal hydraulics, and the interactions between core physics and thermal hydraulics are covered both for thermal reactors and for fast breeders.

... CORES, CONTROL RODS), CRITICAL ASSEMBLIES, TEMPERATURE COEFFICIENT OF REACTIVITY, REACTOR FUELS, REACTOR FUEL ...

Abstract: This award supports a project for physical properties research on snow pits and firn/ice cores with specific objectives that include stratigraphic ...

NUMBERDENSITY provides core/region atomic densities, Dancoff factors, particle packing fractions for various physics codes, including MICROX, GARGOYLE, and GAUGE.

... core competencies for any undergraduate program in the physical sciences. The importance of undergraduate training in the sciences ... the biological sciences, chemistry, and physics) in the physical scie...

A steam injector (SI) is a simple, compact and passive pump and also acts as a high-performance direct-contact compact heater to heat up feedwater by using extracted steam from the turbine. To develop high performance compact feedwater heater, it is necessary to quantify the characteristics between physical properties of the flow field. Its performance depends on the phenomena ...

...by the applicant's exemptions and departures...and updates to the plant-specific DCD required...Include, in the plant-specific DCD, the...referenced in the U.S. ABWR DCD. B...document for the U.S. ABWR, dated December 1994, for plants referencing this...