HETFIS: High-Energy Nucleon-Meson Transport Code with Fission

Barish, J.; Gabriel, T. A.; Alsmiller, F.S.; Alsmiller, R.G.

doi:10.2172/6215156

Cited by 27 publications

(16 citation statements)

References 4 publications

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“…3. Calculations were performed for INC models of Bertini [11,12], INCL4 [28] and CEM03 [29,30] in combination with RAL [13], ORNL [31] and ABLA [32] fissionevaporation models. It should be mentioned that CEM03 is a self-contained package and fission-evaporation model is built into the code [6,29,30].…”

Section: Effects Of the Intranuclear Cascade And Fissionevaporation Mmentioning

confidence: 99%

Determination of natural uranium fission rate in fast spallation and fission neutron field: An experimental and Monte Carlo study

Hashemi-Nezhad

Zhuk

Kievets

et al. 2008

Nuclear Instruments and Methods in Physics Research Section A:

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Section: Effects Of the Intranuclear Cascade And Fissionevaporation Mmentioning

confidence: 99%

Determination of natural uranium fission rate in fast spallation and fission neutron field: An experimental and Monte Carlo study

Hashemi-Nezhad

Zhuk

Kievets

et al. 2008

Nuclear Instruments and Methods in Physics Research Section A:

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“…The total in-target fission rate was calculated to be ∼1.5 × 10 13 particles/sec using the code mcnpx. The release rate of 132 Sn at the exit of the transfer line was deduced, using the ORNL model [13], to be ∼2 × 10 9 particles/sec which is comparable to the value of ∼10 9 particles/sec for SPES [3].…”

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confidence: 58%

Design study of 10 kW direct fission target for RISP project

Tshoo

Jang

Kang

et al. 2014

EPJ Web of Conferences

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Abstract. We are developing Isotope Separation On-Line (ISOL) target system, which consists of 1.3 mm-thick uranium-carbide multi-disks and cylindrical tantalum heater, to be installed in new facility for Rare Isotope Science Project in Korea. The intense neutron-rich nuclei are produced via the fission process using the uranium carbide targets with a 70 MeV proton beam. The fission rate was estimated to be ∼1.5 × 10 13 /sec for 10 kW proton beam. The target system has been designed to be operated at a temperature of ∼2000 • C so as to improve the release efficiency.Production and delivery of high purity intense of Rare Isotope Beam (RIB) have been a major concern for fundamental research fields such as astro− and nuclear−physics as well as applied research field such as material and bio-medical science. Rare Isotope Science Project (RISP) of Korea has proposed to construct Isotope Separation On-Line (ISOL) facility in order to provide the intense rare isotopes. The ISOL target enables us not only to produce the nuclei with the medium mass neutronrich region but also to obtain their high production rates. A uniform 70 MeV proton beam with a maximum current of 500 µA, which is delivered from a cyclotron driver, will impinge on an uranium carbide target. The neutron-rich isotopes are produced via proton-induced fission. A singly charged (1+) RIB is produced and extracted from the target and the ion source, respectively, then the beam emittance is reduced by a RF-cooler to be 3 πmm mrad before injecting to the high resolution mass separator (HRMS). The isotopes selected by the HRMS are delivered to an electron beam ion source (EBIS) or an electron cyclotron resonance (ECR) type charge breeder so as to breed the charge from the 1 + charge state to a n + charge state for efficient and economical post-acceleration. An A/q separator is installed at the downstream of the charge breeder to purify the ion beam contaminated during charge breeding. Here, we report on the results of the ISOL target design for 10 kW proton beam.The main issues concerning the design of the ISOL target can be divided into three categories; intarget fission rate, release time, and temperature of the target. Firstly, a total effective thickness of the target should be as thick as possible in order to maximize the in-target fission rate. This requires a large size of the target. Secondly, release time should be as short as possible so as to minimize the losses by the decay of isotopes. A small size of the target helps to reduce the release time by decreasing the flight length of the isotopes. However, it should be noted here that the small size can lead to melt down of the target due to the reduced radiant cooling. Lastly, the temperature of the target should be as high as possible to increase the thermal velocity of the isotopes, which leads to the reduction of the release time. Therefore, the correlations between the three points mentioned above should be investigated so as to find the optimum condition for the ISOL target. a

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“…The first model of intermediate-and high-energy nuclear reactions, used initially in HETC and LAHET (Prael and Lichtenstein, 1989), was the Bertini INC (Bertini, 1963), followed (by default, but not required) by the Multistage Preequilibrium Model (MPM) Prael and Bozoian, 1988, followed by the Dostrovsky et al evaporation model (Dostrovsky et al, 1959) as implemented in the code EVAP by Dresner (1962). If the compound nuclei produced after the INC and MPM stages of reactions are heavy enough to fission, the fission process is simulated either with the semi-phenomenological Atchison fission model, often referred in the literature at the Rutherford Appleton Laboratory (RAL) fission model, which is where Atchison developed it (Atchison, 1980), or with the Fong statistical model of fission as implemented in the ORNL code HETFIS (Barish et al, 1981;Alsmiller et al, 1981), often referred in the literature as the ORNL fission model. Bertini INC,MPM,EVAP,RAL,and HETFIS migrated from LAHET to MCNPX and later,to MCNP6.…”

Section: Physics Modelsmentioning

confidence: 99%

Features of MCNP6

Goorley

James

Booth

et al. 2016

Annals of Nuclear Energy

131

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a b s t r a c t MCNP6 can be described as the merger of MCNP5 and MCNPX capabilities, but it is much more than the sum of these two computer codes. MCNP6 is the result of six years of effort by the MCNP5 and MCNPX code development teams. These groups of people, residing in Los Alamos National Laboratory's X Computational Physics Division, Monte Carlo Codes Group (XCP-3) and Nuclear Engineering and Nonproliferation Division, Radiation Transport Modeling Team (NEN-5) respectively, have combined their code development efforts to produce the next evolution of MCNP. While maintenance and major bug fixes will continue for MCNP5 1.60 and MCNPX 2.7.0 for upcoming years, new code development capabilities only will be developed and released in MCNP6. In fact, the initial release of MCNP6 contains numerous new features not previously found in either code. These new features are summarized in this document. Packaged with MCNP6 is also the new production release of the ENDF/B-VII.1 nuclear data files usable by MCNP. The high quality of the overall merged code, usefulness of these new features, along with the desire in the user community to start using the merged code, have led us to make the first MCNP6 production release: MCNP6 version 1. High confidence in the MCNP6 code is based on its performance with the verification and validation test suites, comparisons to its predecessor codes, our automated nightly software debugger tests, the underlying high quality nuclear and atomic databases, and significant testing by many beta testers.

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HETFIS: High-Energy Nucleon-Meson Transport Code with Fission

Cited by 27 publications

References 4 publications

Determination of natural uranium fission rate in fast spallation and fission neutron field: An experimental and Monte Carlo study

Determination of natural uranium fission rate in fast spallation and fission neutron field: An experimental and Monte Carlo study

Design study of 10 kW direct fission target for RISP project

Features of MCNP6

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